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NRC Operator Licensing Exam Rept 50-263/99-301(including Completed & Graded Tests) for Tests Administered on 990823-26.Both Applicants Passed All Sections of Exam
	ML20216G442
Person / Time
Site:	Monticello
Issue date:	09/27/1999
From:	; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:	;
Shared Package
ML20216G428	List: IR 05000263/1999301; ML20216G422; ML20216G434;
References
	50-263-99-301, NUDOCS 9910010056
	Download: ML20216G442 (151)
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U. S. NUCLEAR REGULATORY COMMISSION REGION lli Docket No: 50-263 License No: DPR-22 i l Report No: 50-263/99301(OL) - l Licensee: Northem States Power Company

Facility: Monticello Nuclear Generating Station l Locat:on: 2807 West Highway 75 Monticello, MN 55362 Dates: August 23-26,1999 i Examiners: R. Bailey, Chief Examiner, Rlli D. Muller, Examiner, Rlli Approved by: David E. Hills. Chief, Operations Branch Division of Reactor Safety I

9910010056 990927 PDR ADOCK 05000263 PDR

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EXECUTIVE SUMMARY Monticello Nuclear Generating Station NRC Examination Report 50-263/99301(OL) A licensee developed and NRC approved initial operator licensing examination was administered to two reactor operator license applicants using the requirements stated in NUREG-1021, " Operator Licensing Examination Standards for Power Reactors," Interim Revision 8, January 1997. This examination process consisted of a one week examination preparation and validation period, and a three day examination administration perio Additionally, the NRC examiners observed a period of routine operations in the control roo Results:

Both reactor operator license applicants passed all portions of their respective examinations and were issued reactor operator licenses for the Monticello Nuclear Generating Station. Based upon the applicants' performance, the examination team concluded that the applicants were well prepared for the licensing examination. (Section 05.4) Report Summarv:

Control room operators demonstrated appropriate control and awareness during abnormal evolutions while maintaining steady state operations. In general, the licensed

- operators demonstrated appropriate knowledge and understanding of plant system status. (Section 01.1)
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The operations procedures were appropriately written to direct the safe operation of the plant. No operational deficiencies were identified during the examination development, validation, or administration. (Section O3.1)

The licensee provided knowledgeable stafMuring the validation process. The licensed operators, who served as surrogate senior reactor operators during a portion of the exam's' administration, demonstrated appropriate operator command and control during all abnormal events. (Section 04.1)

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While the licensee had established appropriate procedures to control test material j integrity, the examination team identified a lack of plant staff understanding regarding current examination security measures that resulted in an examination compromis The licensee took appropriate short-term corrective actions to prevent any additional exam compromise.' (Section 05.1)

: The licensoe developed examination as originally submitted did not meet all of the necessary requirements listed in NUREG-1021 to be a valid licensing test. The written test required substantial modification and the operating test required only moderate .

modification _ to make them consistent with NUREG-1021. The examination team identified the written examination development area as needing improvement. (Section 05.2) 2 .-

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The plant specific simulator provided realistic plant response throughout the operating i test. (Section 05.3) i - The applicants were well prepared for the licensing examination. No programmatic weaknesses were identified. (Section 05.4)

The licensee's performance during post-examination activities was satisfactor f However, the NRC post-examination review revealed a potential weakness in the j licensee's verification process in the job performance measures (JPM) question area of l the operating test. (Section 05.5)

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-   Report Details 1. Operations 01- Conduct of Operations 01.1 Main Control Room Observations     1 l Scooe (71707)      i Using inspection Procedure 71707, Plant Operations, the NRC examination team
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observed control room operations and questioned the licensed operators on plant status during a two-hour period. That observation included operator response to a failed component and performance during a routine surveillance activit Observations and Findinas In general, the examination team observed proper face-to-face communications, operator response to plant alarms, procedure usage, and decision making processes during steady state operations. The examination team also observed surveillance testing for a fire alarm for the emergency diesel generator room and the reactor building ventilation wide range gas monitors (WRGMs). The reactor building ventilation WRGMs testing was partially completed but had to be stopped due to a component failur During the observation period, the examination team noted the following:

Distractions in the main control room were minimized and control room access

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Control room operators were attentive to the control panel indications and anticipated all expected alarms associa*.ed with testing in progres * Plant operators informed the shift supervisor of problems encountered, such as the failure of WRGM's 'B' channel to purge, during surveillance testin The shift manager promptly declared the 'B' channel of WRGM inoperable and entered Technical Specifications as require .When questioned by the examination team, the control room operators appeared knowledgeable of the current plant status. However, the operators were unable to describe the reason for a high pressure coolant injection gland seal condenser's condensate pump control switch being in the "run" position versus the normal " auto" position.. The examination team received clarification on the switch's position from the licensee staff during the administration of the examinatio .4 __ y & Conclusions

Control room operators demonstrated appropriate control and awaren3ss during testing evolutions while maintaining steady state operations. In general, the licensed operators demonstrated appropriate knowledge and understanding of plant system statu ~ O3 Operations Procedures and Documentation 03.1 Operations Procedures Scooe (71707) Using inspection Procedure 71707, Piant Operations, the examination team reviewed portions of selected administrative and operating procedures. This review was part of l the licensing examination verification and validation process, j Observations and Findinas The examination team reviewed a variety of plant procedures that included normal operating procedures, abnormal operating procedures, annunciator response procedures, emergency operating procedures, and administrative procedures. The examination team did not identify any deficiencies with the procedures referenced. In general, the procedures contained appropriate instructions, notes, precautions, limitations, and cautions to direct operations in a safe manne Conclusions The operations procedures were appropriately written to direct the safe operation of the plant. No operational deficiencies were identified during the examination development, validation, or administratio ' Operator Knowledge and Performance 04.1 Examination Development and Suooort Scope The examination team used guidance in NUREG-1021, sections ES-301 and ES-401, to verify and validate the licensee submitted examination material. That verification included the observed performance of two licensed operators, who served as surrogate senior reactor operators, during the administration of the operating tes . Observations and Findinas During the verification and validation phase, the licensee staff demonstrated a high level of plant specific knowledge and understanding. However, the examination team i

identified a common misunderstanding in the construction of acceptable written questions for a multiple choice type examination. The training staff promptly corrected i

e ' all examination team identified errors and provided revised written questions suitable for validation. See section 05.2 for a complete discussion on the quality of the test materia During the administration of the dynamic simulator portion of the operating test, the examination team observed two licensed operators. These operators performed surrogate senior reactor operators duties to augment the crew composition since only two reactor operator applicants were tested. The surrogate operators demonstrated appropriate procedure usage, effective communications, and proper command and control. Their appropriate performance contributed to the validity of the examination as administere Conclusions The licensee provided knowledgeable staff during the validation process. The licensed operators, who served as a surrogate senior reactor operators during a portion of the exam's administration, demonstrated appropriate operator command and control during all event Operator Training and Qualification 05.1 Pre-Examination Activities: Examination Security Scope Licensee's training staff developed the licensing examination outline and test material using guidance in NUREG 1021, sections ES-301 and ES-401. The examination outline and material were reviewed by the NRC examination team using the same guidanc Observations and Findinas The licensee's staff delivered the licensing examination outline and test material as scheduled in properly sealed envelopes. The necessary quality check forms were also included with that deliver Prior to the administration of the examination, the licensee identified one example of a violation of NRC examination integrity requirements and promptly notified the examination team. Specifically,10 CFR 55.49 required all applicants, licensees, and facility licensees to not engage in any activity that compromises the integrity of any application, test, or examination required by 10 CFR 55, which includes initial NRC licensing examination activity. The following details were provided to the NRC: On July 12,1999, one crew of licensed operators signed on to a security agreement form then participated in a review of the written examination questions. On July 19, 1999, the same crew was approached by one of the two license applicants and agreed to orally examine the applicant by conducting an on-the-job-training session relating to

electrical breaker alignment, security key control system, control room logs, reportable

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e ' occurrences, and the reporting of abnomial conditions._ Licensee management became aware of the potential examination compromise on July 21,1999 and promptly informed the NRC. Licensee management provided the examination team supporting documentation which were analyzed to establish the impact on the test material - integrity. The examination team determined that one question on the written examination had to be replaced by the licensee's staff. The examination team determined that appropriate procedures were in place but a lack of management emphasis on examination security led to a violation of NRC requirements. The licensee took prompt corrective action to inform the licensed operators of their responsibilitie This Severity Level IV violation is being treated as a Non-Cited Violation (NCV), consistent with Appendix C of the NRC Enforcement Policy (VIO 50-263/99301-01).

This violation is in the licensee's corrective action program as condition report N . Conclusions While the licensee had established appropriate procedures to control test material integrity, the examination team identified a lack of plant staff understanding regarding current examination security measures that resulted in examination compromise. The licensee took appropriate short-term corrective actions to prevent any additionai exam compromis .2 Pre-Examination Activities: Quality of Submitted Materials Scope The licensee's tr6ining staff developed the test outline and material using guidance in NUREG 1021, sections ES-301 and ES-401. The licensing examination was reviewed by the NRC examination team for validity and consistency with the guidance in NUREG-102 Observations and Findinas (1) Written Test: The written examination as originally submitted did not meet the requirements of NUREG-1021, sections ES-401 and Appendix B. The examination team identified that 22 test items of the 100 question examination i contained deficiencies associated with the question construction. The NRC informed the licensee's oversight manager, who was responsible for the examination development and review process, that a number of deficiencies had been identified. Based on that conversation, the licensee applied additional resources into correcting those deficiencies prior to the administration of the examination. The most significant deficiencies included the following examples: i

a Five questions were not written to match the selected knowledge / ability (K/A) item chosen from NUREG-1023," Knowledge and Abilities Catalog for Nuclear Power Plant Operators-Boiling Water Reactors," Revision 2, June 1998. This was contrary to the guidance of NUREG-1021, Appendix B, Section C. ;

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One question contained a low content validity in that it did not have a direct, important relationship to the applicant's ability to perform the duties of a reactor operator. This was contrary to the guidance of NUREG-1021, Apper; dix B, Section C. Two questions were ambiguous and lacked sufficient focus to elicit the correct answer. This was contrary to the guidance of NUREG-1021, Appendix B, Section C. = Four questions contained more than one plausible answer choice. This was contrary to the guidance of NUREG-1021, Appendix B, Section . Three questions contained no correct answer choice. This was contrary to the guidance of NUREG-1021, Appendix B, Section Five questions contained an unclear answer choice or a highly implausible distractor. This was contrary to the guidance of NUREG-1021, Appendix B, Sections C.1.c, C.2.g, and C. One question contained a collection of true-false statements in the answer choices. This was contrary to guidance of NUREG-1021, Appendix B, Section C. One question contained specific determiners or clues pointing to the correct answer choice. This was contrary to the guidance of NUREG-1021, Appendix B, Section C. The licensee staff replaced or significantly modified each question identified as being unsatisfactory. These changes exceeded the normally required changes of 10% or less that would be expected on a licensee developed examinatio ( 2) Ooeratina Test: The operating examination as submitted did not meet the requirements of NUREG-1021, sections ES-301 and Appendix C & D. These inconsistencies are noted below: I Cateaory A- Administrative Tooles: The administrative items as originally submitted did not meet the requirements in ES-301. Specific deficiencies i included:

One question contained a low discriminatory value when distinguishing j between a competent and an incompetent operator. This was contrary to ] the guidance in section D. I

One question required knowledge of an unrelated duty as associated with a reactor operator. This was contrary to the guidance in section D. I Cateaory B - Control Room Systems & Facility Walk-throuah: The walk-through items as originally submitted did not meet the requirements ES-301 and Appendix C. Specific deficiencies included:

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Two of the 10 job performance measures (JPM) submitted had been used during an audit exam for the applicants. This duplication was contrary to the guidance in section D. + One control room systems JPM contained only one control panel switch manipulation to complete the task. Even though the assigned task was safety significant, the JPM did not provide a legitimate basis for evaluating the applicant's ability to safely operate the facility. This was contrary to the guidance in section D.1.d and Appendix *

 . Five c/ the 10 JPMs lacked meaningful performance standards to allow the eLamination team to evaluate successful progress toward completing the task. This was contrary to the guidance in Appendix Cateaorv C - Intearated Plant Ooerations: The dynamic simulator scenarios as submitted did not meet the requirements in ES-301 and Appendix D. Specific deficiencies included:
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Scenario No.1 lacked specific expected operator actions for 5 of the 8 events. Operator actions such as start a component or verify a plant parameter had not been included. This was contrary to the guidance in Appendix Scenario No. 2 lacked specific expected operator actions for 4 of the 9 events. Operator actions such as start a component or verify a plant parameter had not been included. This was contrary to the guidance in Appendix Scenarios No.1 and' No. 2 contained one event each that lacked any l

measurable performance indicator needed to verify the ability of the applicants to safety operate the plant. This was contrary to the guidance in section D. , Th'e licensee staff replaced or significantly modified each test item on the operating test identified as being unsatisfactory. In general, these changes were consistent with other licensee developed examinations, c. Conclusions The licensee developed examination as originally submitted did not meet all of the necessary requirements listed in NUREG-1021 to be a valid licensing test. The written test required substantial modification and the operating test required moderste modification to make them consistent with NUREG-1021. The examination team identified the written examination development area as needing improvement. Licensee management acknowledged the performance deficiency as needing attentio E 't j

05.3 Examination Administration ar"1 Staff Suooort Scope ) The examination team administered an operating test to two license applicants using '

- guidance in NUREG-1021, ES-302. The training staff administered an NRC approved written test to the same two license applicants using guidance in NUREG-1021, ES-40 Observations and Findinos The examination team identified no significant examination administration or licensee support deficiencies. The licensee's training staff consistently and correctly established the required simulator conditions. The simulator was properly set up for each scenario and the prescripted malfunctions were properly inserted in a timely manner. In addition, the training staff effectively coordinated the availability of the simulator and plant during the walk-through portion of the operating test. Licensee staff, who participated as support personnel (e.g., technicians, engineers, in-plant operators, etc.) during the scenarios, provided appropriate feedback and communications to the applicant Conclusions The training staff provided appropriate support during the administration of all portions of the operating test. The plant specific simulator provided realistic plant response throughout the operating tes .4 License Aoolicant Performance Scope Initial operator licensing examinations were administered to two reactor operator applicants during the week of August 23,1999, in accordance with NUREG-1021. The examination team documented the applicants' performance using guidance in NUREG-1021, ES-50 Qbservations and Findinas-Written Examination Performance: Both applicants achieved greater than 90.0% on the written examination and given a passing score. The relatively high score achieved by each applicant demonstrated an appropriate level of preparation. Only one question was answered incorrectly by both applicants. The subject matter of the missed question related to the operation of the fuel pool cooling system during a loss of the reactor building closed cooling water syste Ooeratina Test Performance: Both applicants passed all portions of the operating tes After the operating test grading was finalized, the examination team identified three generic weaknesse * A knowledge weakness associated with the main steam isolation valve closure scram logic;     l l

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A performance weakness associated with approved procedure adherence; and

A performance weakness associated with using three-way communication These generic items did not constitute a programmatic weakness in the Monticello training program but should be considered for incorporation into the systematic approach to training (SAT) progra Conclusions The examination team concluded that the applicants were well prepared for the licensing examination. The examination team identified no programmatic weaknesse O5.5 Post Examination Activities Examination Scope The examination team conducted post-examination activities using the guidelines contained in NUREG-1021, ES-50 Observations and Findinas The examination team identified no deficiencies with the licensee's staff performance during the post-examination activities. Following the completion of the examination, the NRC examination team requested the assistance of the licensee's training personnel to clarify five JPM question area responses that were somewhat different than the validated answer key. The examination team was informed that the altemate responses were correct answers and should be given full credit. The examination team determined that the licensee's validation of the JPM question area had not been all inclusiv The licensee did not have any post written examination comments. The examination team's post-examination review revealed no changes. The as-administered licensing examination was deemed vali Conclusions The licensee's performance during post-examination activities was satisfactor However, the post-examination review revealed a potential weakness in the licensee's verification process for the job performance measures (JPM) question area of the

operating tes .6 Simulator Fidelity

-. The examination team observed no simulator modeling or simulator performance deficiencies during examination validation or administration.

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08 Miscellaneous Operations issues 08.1 (Closed) Unresolved item 50-263/99010-01(DRS): Licensed operator maintaining active status issue. The licensee's Technical Specifications Table 6.1.1, "Minimurn Shift Crew Composition," only specified four licensed operators (two licensed reactor operators and two licensed senior reactor operators) as being needed to operate the facility. However, the licensee had identified a third licensed senior reactor operator (SRO) position (NLPE&RO) as being required in the control room and had been giving that position credit for maintaining an active SRO licens On June 15,1999, the operations department issued an operations policy statement (No. 99-01) to clarify the expectations for maintaining an active license. Specifically, the NLPE&RO position would not be recognized as a SRO license required position by plant administrative procedures. The duties and responsibilities of the NLPE&RO were consistent with those of a reactor operator (RO) licensed counterpart. The SRO licensed NLPE&RO position would require training, examination, and evaluation in the SRO position during annual requalification training to maintain a current SRO licens This item will be closed based upon the licensee's corrective action to clarify the license status expectations for a NLPE&RO positio V. Manaaement Meetinas X1 Exit Meetina Summary The Chief Examiner presented the examination team's observations and preliminary findings to members of the licensee's management on August 25,1999. The licensee was contacted on September 10,1999, to inform plant management of the examination results. The licensee acknowledged the findings as presented. No proprietary information was identified during the development and administration of the examination or at the exit meetin l k__-__ --'

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PARTIAL LIST OF PERSONS CONTACTED Licensee T. Brian, Operations Instructor D. Fousel, Superintendent, Simulator Services M. Hammer, Site General Manager M. Lechner, Shift Manager K. Markling, Shift Supervisor A. Ward, Training Manager J. Windschill, Radiation Protection Manager T. Witschen, Superintendent, Operations Training NRC D. Wrona, Resident inspector, Monticello Nuclear Generating Station INSPECTION PROCEDURES USED

IP 71707: Plant Operations ITEMS OPENED, CLOSED, AND DISCUSSED 50-263/99301-01 VIO Failure to maintain examination integrity l Qlosed 50-263/99010-01 URI Failure to maintain active license status 50-263/99301-01 VIO Failure to maintain examination integrity Discussed

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'    I LIST OF ACRONYMS USED CFR Code of Federal Regulations *

JPM ' Job Performance Measure NCV Non-Cited Vio!ation NRC Nuclear Regulatory Commation NUREG Nuclear Regulatory Guide OL Operator Licensing RO Reactor Operator SRO Senior Reactor Operator URI Unresolved item VIO Violation WRGM Wide Range Gas Monitor '

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Enclosure 2 SIMULATION FACILITY REPORT < Facility Licensee: Monticello Nuclear Generating Station Facility Licensee Docket No: 50-263

. Operating Tests Administered: August 24-25,1999 The following informatiori documents observations made by the NRC examination team during the August 24 and 25,1999, initiallicense examination. These observations do not constitute
. audit or inspection findings and are not, without further verification and review, indicative of non-l
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compliance with 10 CFR 55.45(b).. These observations do not affect NRC certification or approval of the simulation facility other than to provide information which may be used in future ] evaluations. . No licensee action is required in response to these observation During the conduct of the simulator portion of the operating tests, the following items were observed: ITEM DESCRIPTION 1 None l

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MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION Page 1 of .2 2 6 APPLICANT INFORMATION - NAME MAST ER EXAMINATION TE: -AUGUST 23, 1999 RE'GION: lli LIC. LEVEL: RO RX TYPE: BWR , START TIME: FINISH TIME: INSTRUCTIONS: Use the answer sheets provided to document your answers. Each question has only one cor-rect answer. Staple this cover sheet on top of the answer sheets. Points for each question are indicated in the Exam Number Question bar for each question. The passing grade requires a final grade of at least 80 percent. Examination papers will be picked up four (4) hours after the examination start All work done on this examination is my own. I have neither given nor received ai APPLICANT'S SIGNATURE: Examination Value: 100 Points

Applicant's Score: Points Applicant's Grade: Points

    )e Prepared By: kd  Reviewed By:

Approved By: @ Effective Date: f - 2 6 - //ftf 9 I I/cmb

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MONTICELLO NUCLEAR GENERATING PLANT M81000-gg23 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 2 of 126

l Exam Questior Number: 1 Point Value: 1.00 Time (Minutes): NA During a Reactc,r SCRAM, the Scram Discharge Volume Vent and Drain Valves close due to... De-energizing the Back-up Scram Solenoid Valves from the 125 VDC batterie Energizing the Dump Volume Solenoid Valves from the 125 VDC batterie De-energizing the Pilot Scram Solenoid Valves from the Reactor Protection Syste I Energizing the Pilot Scram Solenoid Valves from the Reactor Protection Syste Answe C > I Question No.: 1-B.01.03-027 ) Reference (s): B.1.3-01 VJA Reference: 201001 Task Number: A1.05 Rating RO/SRO: 3.5/ Monticello JTA- CR201.033 Objective (s): M-8107L-020 EO-13 l I 1/cmb j

MONTICELLO NUCLEAR GENERATING PLANT M81000-gg23 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 4 of 126 l Exam Question Number: 2 Point Value: 1.00 Time (Minutes): NA l ;

During a Reactor startup there are several reactivity concerns associated with the Control Rod Drive System. If initial SRM count rate was 100 cpm, when are continuous rod withdrawals ; allowed? l I Continuous control rod withdrawals are allowed... on a hi-lighted control rod that is to be pulled from position 12 to 48, while power is on the SRM when SRM count rate is equal to 1500 cp any time the SRM period meters indicate a stable period less than 100 second after Reactor power is on the IRMs at range seven or abov l Answer: ; l D Question No.: 1-C.01 -028 Reference (s): C.1 Startup Procedures K/A Reference: 201002 Task Number: K4.05 Rating RO/SRO: 3.3 Monticello JTA: CR201.011 Objective (s): M-8107L-032, EO-4 M-8113L-001, EO-1 1/cmb

MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 5 of 126 l Exam Question Number: 3 Point Value: 1.00 Time (Minutes): NA l While on duty in the Control Room a loss of 4160 KV Bus 16 occurs. While walking down the aanels during your follow-up actions, you notice Alarm 8-A-9 (Y-20 INSTRUMENT AC JNDERVOLTAGE) is flashing slowly.

Which one of the following would be a concern that would require operator action, if a Reactor SCRAM occurs? There is a loss of CRD flow contro J The plant paging system would not functio You are unable to drive the SRM and IRMs i The Recirc Scoop Tubes would be locked.

Answer: D Question No.: 1-C.4.B.09-009 Reference (s): C.4-B.09.13.B K/A Reference: 202002 Task Number: K4.06 Rating RO/SRO: Monticello JTA: CR202.013 Objective (s): M-8107L-029, EO-9 1/cmb

r MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 ! TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 l LICENSE EXAMINATION - ANSWER KEY Page 6 of 126 l Exam Question Number: 4 Point Value: 1.00 Time (Minutes): NA Given the following plant conditions:

Reactor Scram initiated from 100% power due to a loss of offsite powe * Both HPCI and RCIC failed to injec . No.12 EDG is providing power to No.16 Bus. All other 4160 busses are de-energize . No.12 Core Spray pump failed to star * No.12 and No.14 RHR pumps are injecting to the vesse . Three (3) ADS valves are Ope . Reactor pressure is 200 psig and decreasin * Reactor level is -110 inches and increasin i Per the EOPs (C.5.1100) what is the status of the core for the above conditions? Core cooling is... ' assured due to the core being submerge assured due to the steam cooling effects of three (3) Open SRV not assured due to Reactor level being near the top of active fue not assured due to only two LPCI pumps injectin Answer: A Question No.: 1-C.05.01-1000-002 Reference (s): C.05.01-1100 K/A Reference: 203000 Task Number: K5.02 Rating RO/SRO: Monticello JTA: CR304.002 Objective (s): M-8114L-005, EO-2, 3 1/cmb

MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 7 of 126 [ Exam Question Number: 5 Point Value: 1.00 Time (Minutes): NA A loss of normal off-site powerjust occurred coincident with an ECCS signal. When will the Core Spray System receive a start signal? No.11 and No.12 Core Spray Pumps will Auto Start after the loss of power even seconds seconds seconds seconds Answer: A Question No.: 1-B.03.04-031 Reference (s): B.03.04-02 (Page 7 of 18) K/A Reference: 203000 Task Number: K6.01 Rating RO/SRO: 3.6 Monticello JTA: CR209.007 Objective (s): M-8107L-005, EO-4 l l l

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MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 8 of 126 l Exam Question Number: 6 Point Value: 1.00 lime (Minutes): NA During the conduct of the quarterly HPCI surveillance test, the HPCI CST Suction Valve MO-2063 is stroked closed to measure closing and opening times. HPCI receives an initiation signal while MO-2063 was stroking closed.

Choose the correct answe HPCI will start and will automatically realign suction to the Toru HPCI will start and automatically re-open MO-206 HPCl will start and not align to any suction source. HPCI will subsequently trip on low suction pressur HPCI will not start until MO-2063 is manually re-opene )

Answer: B Question No.: 1-B.03.02-024 Reference (s): B.03.02.01 K/A Reference: 206000 . Task Number: K1.05 Rating RO/SRO: Monticello JTA: CR206.003 Objective (s): M-8107L-002, EO-4,7 1/cmb

a l MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 9 of 126

l Exam Question Number: 7 Point Value: 1.00 Time (Minutes): NA l During HPCI operation, Turbine speeds are maintained to prevent damage to HPCI equipmen i Which of the following Turbine speeds shall be avoided to prevent damage to the HPCI l equipment?

     ) Speeds less than 3900 rpm and greater than 4500 rpm   ) Speeds less than 3900 rpm and greater than 5000 rpm Speeds less than 2150 rpm and greater than 5000 rpm Speeds less than 2150 rpm and greater than 3900 rpm Answer:

C Question No.: 1-B.03.02-025 Reference (s): B.03.02-01 B.03.02-05 K/A Reference: 206000 Task Number: A3.01 Rating RO/SRO: Monticello JTA: CR206.003 Objective (s): M-8107L-002, EO-8 1/cmb

MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 10 of 126 l Exam Question Number: 8 Point Value: 1.00 Time (Minutes): NA Given the following conditions:

* A small break LOCA has occurre * The only system injecting is CR *

Reactor pressure is 900 psig and slowly decreasin . DW pressure is 2.6 psig and stabl . RPV level is -55 inches and stabl J

ADS fails to initiate when the ADS timer times out and the SRVs fail to open.

What will be the response of the Core Spray system if the above conditions exist after 20 , minutes?

      { The pumps start and the injection valves open immediatel The pumps do not start due to Reactor pressure being >460 psig,  i The pumps do not start due to the ADS logic failing to initiat t The pumps starts but the injection valves do not open until Reactor pressure is <460 psig.

Answer: D Question No.: 1 B.03.03-020 Reference (s): B.03.03-01 ! K/A Reference: 209001 l Task Number: K6.11 Rating RO/SRO: 3.6/3.7 Monticello JTA: CR209.007, CR218.003 Objective (s): M 8107L-005, M-8107L-025 1/cmb

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MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 12 of 126 l Exam Question Number: 9 Point Value: 1.00 Time (Minutes): NA The plant has just returned to full power following a 40-day outage. The following conditions , apply:

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100% power was achieved approximately 7 hours ag * Outplant operators have begun the SBLO Quarterly Surveillance Tes * 3D Monicore indicates MWT @ 1772.

Soon after receiving a call that No.11 SBLC Pump has been started per test instructions, you notice Reactor power has decreased. Each time 3D Monicore updates Reactor thermal power, I you have to increase recirc speed in small, incremental increases to maintain Reactor power at ) 100 %. l

Which one of the following explains why Reactor power is decreasing? The natural buildup of Xeno Expected SBLC Squib Valve leakage while in test lineu Recirc speed control scoop tube positioner is huntin Recirc MG set oil temperature is decreasing.

Answer: A Question No.: 1-B.03.0so22 Reference (s): B.03.05-02 (Page 6 of 7) K/A Reference: 211000 Task Number: K4.01 Rating RO/SRO: 3.1 Monticello JTA: CR211.007 Objective (s): M-8107L-004, EO-7, 8,13 l/cmb

MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 ) LICENSE EXAMINATION - ANSWER KEY Page 13 of 126

l Exam Question Number: 10 Point Value: 1.00 Time (Minutes): NA Given the following Standby Liquid Control system parameters: )

Boron concentration is 12.1% (wt%).

. Boron Tank levelis 1200 gallon j
. Boron Tank temperature is 66* '
. Room temperature is 70*F.

Using the above parameters, what is the status of the SBLC System? ! Inoperable due to room temperature being too lo Inoperable due to Boron concentration being too low for the tank volume listed abov Inoperable due to tank temperature being too low for the Boron concentratio Operable for the above conditions.

Answer: B PROVIDE FIGURES 3.4-1 AND 3.4-2 FROM TECH SPEC 3.4 FOR THE EXA i Question No.: l-TS-045 Reference (s): Tech Spec 3.4, Figure :1.4-1 and Figure 3.4-2, B.03.05-05.A.3 K/A Reference: 211000 Task Number: A4.01 Rating RO/SRO: 3.9/3.9 Monticello JTA: CR211.007, CR999.004 Ob}ective(s): M8107L-004 EO-10 1/cmb

l MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 ! T!TLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 l LICENSE EXAMINATION - ANSWER KEY Page 14 of 126 l Exam Question Number: 11 Point Value: 1.00 Time (Minutes): NA What is the normal power supply for RPS MG Set A (480 VAC)? MCC-121 MCC-141 1 MCC-133 MCC-111 Answer: D Question No.: 1-B.09.12-008 Reference (s): B.9.12-05, RPS MG Set A (480 V) MCC-111 B1107 K/A Reference: 212000 Task Number: K2.01 Rating RO/SRO: 3.2/ Monticello JTA: CR212.001, CR212.006 Objective (s): M8107L-043 EO-3 1/cmb I

   .
     -

l MONTICELLO NUCLEAL (GENERATING PLANT M61000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 j LICENSE EXAMINATION - ANSWER KEY Page 15 of 126 j l Exam Question Number: 12 Point Value: 1.00 Time (Minutes): NA ! The plant is operating at 100% power when one of the electrical protection assemblies for the #12 RPS MG set inadvertently trips open.

Choose the correct answe ! l The Reactor will SCRAM due to the failure of the Scram Discharge Volume level switche Reactor power indication on APRMs 4,5, and 6 will be los A half scram will occur due to loss of power to IRMs 15-1 Power will automatically transfer to the RPS alternate source.

Answer: B Question No.: 1-B.09.12-009 Reference (s): B.09.12-06, Figure 1; B.09.11-05 l B.05.01.02-05 i K/A Reference: 212000 Task Number: K3.04 l Rating RO/SRO: 3.5 Monticello JTA: CR212.006 Objective (s): M-8107L-043, EO-5 1/cmb

l MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 ' TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 l LICENSE EXAMINATION - ANSWER KEY Page 16 of 126 l Exam Question Number: 13 Point Value: 1.00 Time (Minutes): NA Given:

* The plant is in cold shutdow * All RPS shorting links are remove * AllIRMs are on range * Mode cwitch is in refuel
* IRM 12 fails downscal * IRM 14 fails upscal What is the status of RPS? There is a full SCRAM signal from RP There is a half SCRAM signal on the A channel of RP There is a half SCRAM signal on the B channel of RP There is no SCRAM signal from RP Answer:

A Question No.: 1-B.05.06-029 References: B.5.06-02 K/A Reference: 215003 Task Number: A1.05 Rating RO/SRO: 3.9/ Monticello JTA: CR215.037 Objective (s): M8107L-064 EO-6 1/cmb

MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 17 of 126 I

l Exam Question Number: 14 Point Value: 1.00 Time (Minutes): NA l Regarding the SRM System Detector Drive Control Pushbuttons, which of the following defines the operation of these buttons? Drive in Pushbutton Drive Out Pushbutton Momentarily Depress Continuously Depress Continuously Depress Momentarily Depress Momentarily Depress Momentarily Depress Continuously Depress Continuously Depress

Answer: A Question No.: 1 B.05.01.01-040 Reference (s): B.5.01.1 -05 K/A Reference: 215004 Task Number: A4.04 Rating RO/SRO: 3.2/3.2 Monticello JTA: CR215.011 Objective (s): M-8107L-054 EO-5,6 i i I/cmb l l l

MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 19 of 126 l Exam Question Number: 15 Point Value: 1.00 Time (Minutes): NA Given:

Actual core Flow is 28.8 x 106 lb/hr

- Both recirc pumps are running
*

Rated core flow is 57.6 x 10e Ib/hr What is the setpoint for the APRM Flow Biased SCRAM? .0% of rated thermal power .6% of rated thermal power .0% of rated thermal power .6% of rated thermal power Answer: D Question No.: l-TS-044 Reference (s): Tech Spec 2.3 (FDF CLADOING INTEGRIT() K/A Reference: 215005 Task Number: K5.05 Rating RO/SRO: 3.6/3.6 Monticello JTA: CR215.038 Objective (s): M-8107L-069 EO-3 1/cmb

MONTICELLO NUCLEAR GENERATING PLANT M88000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 21 of 126 l Exam Question Number: 16 Point Value: 1.00 Time (Minutes): NA Operations Manual C.4-B.S.1.2.A" Control of Neutron Flux Oscillations" is entered during a rapid power reduction. The pressure control and recirculation control systems are operating normally.

Which one of the following is used as an indication of neutron flux oscillations? SPDS APRM readings fluctuate greater that 10% peak to pea Two adjacent LPRMs indicate Hi alarm APRM recorders indicate peak to peak oscillations greater than 10% APRM HI or DOWNSCALE alarms come in then clea . Answer: C I Question No.: l-C.4.B.05-006 Reference (s): C.4-B.05.01.02.A K/A Reference: 216000

Task Number: A4.01 Rating RO/SRO: Monticello JTA- CR999.011 Objective (s): M-8114L-002, EO-1 l l I/cmb J

MONTICELLO NUCLEAR GENERATING PLANT M8100C-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 22 of 126 I l Exam Question Number: 17 Point V51ue: 1.00 Time (Minutes): NA l Following a loss of normal offsite power, the current conditions exist: l

. Low-Low Set is controlling Rx pressur l
. No.15 and No.16 Busses are powered from their respective EDG . No pressure boundary leakage has occurre * Reactor water level has been raised to +50 inches by HPCI and RCI . Reactor water level is slowly decreasin l l

Assuming no operator action and Reactor water level is allowed to decrease to the ECCS initiation setpoint, which one of the following will re-initiate RCIC? MO-2080, TRIP THROTTLE VALVE, will Auto OPE MO-2075, RCIC INBOARD STEAM SUPPLY, will Auto OPE RCIC will not re-initiate unless the RCIC Initiation Logic Reset PB is depresse MO-2078, STEAM SUPPLY VALVE, will Auto OPE i Answer: D t Que-stion No.: 1-B.02.03-017

Reference (s): B.02.03-02, Pages 5 and 6 of 13 K/A Reference: 217000 Task Number: A2.01 Rating RO/SRO: ! Monticello JTA: CR217.007 Objective (s): M-8107L-003, EO-5 1/cmb l l

MONTICELLO NUCLEAR GENERATING PLANT M81000-gg23 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 23 of 126

l Exam Question Number: 18 Point Value: 1.00 Time (Minutes): NA A Reactor SCRAM occurred ten (10) minutes ago due to low Reactor water level and a lockout on 4160 Bus No.11 was received.

The following plant conditions were just verified:

* Reactor water level is -60" and slowly decreasin * Reactor pressure is 900 psi *

No.12 Reactor Feed Pump has tripped on low suction pressur * Drywell sumps have high level alarms i * HPCI failed to star * All other plant equipment has performed as expecte * Drywell pressure reached 2.0 psig 10 seconds ago and pressure is rapidly increasing.

When do we expect the ADS valves to open? The ADS valves.... are presently ope will open in 1 minute,37 second will open in 11 minutes,37 second will open when the low pressure ECCS pumps are placed in service.

Answer: B Ouestion No.: 1-B.03.03-018 Reference (s): B.3.3-01 K/A Reference: 218000 Task Number: K1.04 Rating RO/SRO: 3.9/ ) Monticello JTA: CR218.003 j Objective (s): M8107L-025 EO-6 i I/cmb

MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 25 of 126 l Exam Question Number: 19 Point Value: 1.00 Time (Minutes): NA l The Reactor Building to Suppression Chamber Vacuum Breakers AO-2379 and AO-2380 are dual function valves. In addition to containment external pressure protection, what is the other function of these valves? Provide primary containment isolation on increasing Torus pressur Provide a means to control the flow from V-EF-25 (DRYWELL PURGE FAN) to the Toru Provide a flow path from the Torus to the hard pipe ven Provide a Torus air exhaust flow path during containment de-inerting operations Answer: A Question No.: 1-B.04.01-019 Reference (s): B.04.01 -05 P&lD M-143 K/A Reference: 223001 Task Number: K3.06 Rating RO/SRO: Monticello JTA: CR223.006

Objective (s): M-8107L-044, EO-10 I/cmb

i -

MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 26 of 126 l Exam Question Number: 20 Point Value: 1.00 Time (Minutes): NA l Given the following plant conditions:

Reactor Scram with all rods at 00 due to a dual feedwater pump tri . Immediate Scram actions are complet . HPCI automatically starte * Water level is increasing and is currently at + 20 inche * Drywell pressure is 0.5 psig and stead . The Primary Containment Isolation System worked as designe l Choose the correct answe ) The Group 1 Isolation Valves will be Open with pressure controlled by the bypass valves The Group 21 solation Valves will have Closed. SBGTS will not have initiated The Group 3 Isolation Valves will have Closed, and are able to be Reset, if desire i The Group 4 Isolation Valves will Close when level reaches + 48 inche Answer:

C Ouestion No.: 1-B.05.06-030 Reference (s): B.05.06-02 K/A Reference: 223002 Task Number: A3.02 I Rating RO/SRO: l Monticello JTA: CR223.006 Objective (s): M-8107L-070, EO-4 l/cmb

MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 27 of 126 l Exam Question Number: 21 Point Value: 1.00 Time (Minutes): NA i l Given the following plant conditions:

= Reactor pressure is 920 psig and decreasin . Reactor power is 90%
. SRV "D" has a green light ON and an amber light ON for its control switch on C-0 .

SRV "D" has a tailpipe temperature of 220*F and rapidly increasin = 3-A-9 (SRV BLOWDOWN RELIEF VALVE LEAKING) is in Alar . 5-A-96 (SRV OPEN) is in Alar . Which of the following IMMEDIATE actions must be taken? Place the Division ll Low-Low set logic switch to Bypas Cycle the "D" SRV handswitch to Open and then back to Aut Place RHR in Torus coolin Initiate a normal plant shutdown.

Answer: B Ouestion No.: 1-C.04.B.03-009 Reference (s): C.4-B.03.03.A, Bases Page 4 of 5, C.4-B.03.03.B, B.03.03-03 K/A Reference: 239002 Task Number: A2.03 Rating RO/SRO: 4.1 Monticello JTA: CR218.003 Objective (s): M-8107L-025, EO-4 1/cmb

MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 28 of 126 l Exam Question Number: 22 Point Value: 1.00 Time (Minutes): NA Given the following:

* Reactor power is 900 MWth/3 s0 MW * EPR controlling Reactor pressure at 1000 psi * A failure causes the Pressure Regulator Override (PRO) setpoint to increase.

What would be the effect on the Main Steam Pressure Control System and the initial effect on generator load? The bypass valves will start to Open. Generator load will decrease accordingl The bypass valves cannot be controlled by the PRO. Generator load will increas The bypass valves will Open only after the control valves are Full Open. Generator load will increas The bypass valves will Open after the control valves havo opened 3% Generator load will increase slightly, then decrease.

Answer: C Question No.: 1 B.05.09-013 Reference (s): B.05.09-06, Figures 1 and 3 K/A Reference: 241000 Task Number: A1.14 Rating RO/SRO: Monticello JTA: CR239.009 Objective (s): M-8107L-048, EO-5 I/cmb l I

MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 29 of 126 l Exam Question Number: 23 Point Value: 1.00 Time (Minutes): NA Given the following conditions:

* Reactor Shutdown is in progres . Control rods are being inserted with power indicating on the SRM .

Main Turbine is off line and No.1 Bypass Valve is ~10% ope . Reactor Pressure is 915 psig being controlled by the MP . As the shutdown continues, a mechanical failure of the of No.1 Bypass Valve linkage results in the bypass valve failing to close further.

Choose the correct respons A Group 1 Isolation will occur when Reactor pressure reaches 840 psi All rods must be inserted prior to Reactor pressure decreasing to less than 700 psi /s Manual Scram is required if Reactor pressure decreases below 900 psi Control rod withdrawal should be performed to maintain Reactor pressure at 915 psig MPR setpoint.

Answer: B Ouestion No.: 1-C.03-009 Reference (s): C.3 (SHUTDOWN) K/A Reference: 241000 Task Number: A2.03 Rating RO/SRO: 4.1 Monticello JTA: CR999.003 Objective (s): M-8113L-003, EO-1 1/cmb

MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 30 of 126 l Exam Question Number: 24 Point Value: 1.00 Time (Minutes): NA Given the initial plant conditions:

= Reactor at 100% powe * Station power on the 2R Transformer.

Severe weather around the plant resulted in a loss of 345 KV Bus 1.

With no operator action, which of the following automatic actions will be expected to restore Reactor water level? Restart of No.11 RFP Restart of No.11 and No.12 RFP HPCI and RCIC Initiation ADS and LPCI initiation.

Answer: A Question No.: 1-B.09.06-036 Reference (s): B.09.06-01 K/A Reference: 259001 Task Number: K2.01 Rating RO/SRO: 3.3 Monticello JTA: CR259.021 Objective (s): M8107L-039, EO-4 1/cmb l l l I

MONTICELLO NUCLEAR GENERATING PLANT M81000 gg23 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 31 of 126 l Exam Question Number: 25 Point Value: 1.00 Time (Minutes): NA With Reactor power at 90%, the No.12 Condensate Pump Breaker inadvertently trips ope . How would the Condensate and Reactor Feedwater System respond? Which immediate Operator Action would be appropriate for the conditions? . No.12 RFP would tria on low suction pressure after a 5-second time dela . " Monitor and control leactor water level between + 9 and + 48 inches". . No.11 RFP would trip on low suction pressure after a 10-second time dela . " Execute C.4-F (RAPID POWER REDUCTION) concurrently." . Both RFPs trip on low suction pressure immediatel . " Verify all control rods are inserted to or beyond position 04".

i . Both RFPs remain running due to the Recirc pump runbac . " Monitor and control Recirc MG lube oil temperature."

Answer: B Ouestion No.: 1-C.4-B.06.05-020 W Reference (s): C.4-B.6. B.6.05.03 K/A Reference: 259001 Task Number: A2.03 Rating RO/SRO: l

Monticello JTA: CR259.021 i Objective (s): M8107L-068, EO-5

1/cmb l

MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Pay 32 of 126 l Exam Question Number: 26 Point Value: 1.00 Time (Minutes): NA Given the following Plant conditions:

. Reactor Startup is in progres . Reactor pressure is 290 psi . Low Flow Regulator Valve is in Aut * Low Flow Regulator Valve is set at 28".

With the feedwater level control system working properly and with level stabilized and constant, what is the actual water level in the Reactor? inches inches inches inches Answer: C PROVIDE FIGURES 17,18,19 & 21 FROM B.01.01-06.02 WITH EXAM.

Question No.: 1-B.05.07-014 Reference (s): B.05.07-02, Page 6 of 7 B.01.01 -06.02, Figures 18 and 19 K/A Reference: 259002 Task Number: 2. Rating RO/SRO: Monticello JTA: CR259.008, CR259.017 Objective (s): M-8107L-056, EO-4 M-8107L-046, EO-6 1/cmb

l i MONTICELLO NUCLEAR GENERATING PLANT M61000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 I LICENSE EXAMINATION - ANSWER KEY Page 33 of 126 l Exam Question Number: 27 Point Value: 1.00 Time (Minutes): NA Given the following:

- Drywell pressure is 1.0 psi . Reactor levelis 35 inche .
"A" SBGT is isolated for maintenance and "B" SBGT is in Standby.

What is the status of "B" SBGT following a trip of the "A" RPS MG Set? Start immediatel l Start after a 10 second dela Starts when Reactor Building pressure reaches O psi Remains in Standby since no initiation signal is present.

Answer:

l Question No.: 1-B.04.02-021 l

Reference (s): B.04.02-01, paragraph l B.05.11-01 B.05.11 -05

K/A Reference: 261000 Task Number: A3.01 Rating RO/SRO: Monticello JTA: CR261.007 Objective (s): M8107L-008, EO-3,4,11 1/cmb

l MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 34 of 126 ' l Exam Question Number: 28 Point Value: 1.00 Time (Minutes): NA A loss of normal offisite power has occurred resulting in the No.15 and No.16 bus being supplied by the 1 AR Transformer. Subsequent , a leak on the Rx caused Drywell pressure to increase to J

>18 psig. Containment Spray was initi ted per the EOP !

Using the following current conditions:

{
.

Drywell pressure < 2 psi )'

Rx level @ 35 inche . Rx pressure O psi . All RHR pumps in service for Torus Coolin . No.11 Core Spray and No.12 Core Spray prevented per EOP i

Bus 15 and Bus 16 are still being supplied by the 1 AR transforme Which of the following would be required by the operator to start No.11 CRD Pump? Shutdown No.11 EDG, then place No.11 CRD P .np Control Switch to STAR Shutdown No.11 or No.13 RHR Pump, then place No.11 CRD Pump Control Switch ' - STAR Place the Essential Bus Transfer switch on C-08 in Lockout, then place No.11 CRD Pump Control Switch to STAR Shutdown No.11 or No.13 RHR Pump, depress the LPCI Loop Select Reset Pushbutton on C-03, then place No.11 CRD Pump Control Switch to STAR Answer: l B i Question No.: 1-B.09.06-035 Reference (s): B.09.06-01, Page 10 of 11 K/A Reference: 264000 Task Number: K4.05 l Rating RO/SRO: Monticello JTA: CR201.001, CR999.011 Objective (s): M-8107L-020, EOM-4, 7,13 1/cmb

i MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 , TITLE: 1999 NRC INITIAL HEACTOR OPERATOR Revision 0 l LICENSE EXAMINATION - ANSWER KEY Page 35 of 126

l Exam Question Number: 29 Point Value: 1.00 Time (Minutes): NA l The Reactor is at 90% power for control rod exercising. CRD 22-07 has just been moved to i notch 46. While the operator is logging the rod move, Alarm 5-A-11, ROD OVERTRAVEL and 5-A-27, ROD DRIFT ALARM, are receive What operator action is required? t Attempt to withdraw the rod to position 48 and insert back to position 46 in an attempt to re-couple the control ro I Fully insert the rod to 00 and electrically disarm the control ro Declare the control rod inoperable, electrically disarm and hydraulically isolate the control rod at position 4 Fully insert the rod to 00 and perform a coupling chec Answer: B Question No.: 1-B.01.03-028 Reference (s): B.1.3-05 Tech Spec 03.0 K/A Reference: 201003 Task Number: A2.02 Rating RO/SRO: 3.7 / l Monticello JTA: CR201.017, CR201.021 Objective (s): M-8107L-032 EO-3, M-8107L-021 EO-1,8

1/cmb - _

.  .
. .

MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 __ TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 36 of 126 l Exam Question Number: 30 Point Value: 1.00 Time (Minutes): NA l The RWM will enforce an insert block thereby preventing control rod insertion during low power operations. What is the primary purpose of imposing control rod insert blocks? 1 To force the operator to Scram the Reactor if conducting rapid power reductio To prevent the operator from inserting rods that may result in an inverse power respons To limit the rate that rods are inserted during normal shutdown thereby managing the negative reactivity inserted into the cor To maintain sequenced control rod insertions such that high worth rods are not created.

Answer: D Question No.: 1-B.05.02-035 Reference (s): B.05.02-01 K/A Reference: 201006 Task Number: K5.13 Rating RO/SRO: Monticello JTA- CR201.013 Objective (s): M-8107L-032, EO-1 1/cmb

__ MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 37 of 126 l Exam Question Number: 31 Point Value: 1.00 Time (Minutes): NA l The plant is operating at 100% power with RC!C isolated for on-line maintenance. The following events happened in chronological order:

. Both Main Feedwater Regulator Valves fail close . Group I isolation Valves clos . Low Low Set initiate . Eight (8) SRVs cycle open, limiting the Rx pressure spike to <15 psig above SRV safety setpoin . Low Low set controls Rx pressure after the SRVs lif . HPCI Auto initiate Rx Mode Switch placed in Shutdow . Low pressure ECCS Pumps have not Auto initiate Which of the following caused the Recirc MG Set field breaker to trip open? Low Low Rx level High Drywell pressure High Rx pressure Main Generator Lockout Answer:

A Question No.: 1-B.01.04-047 Reference (s): B.01.04-02, Pages 12 and 13 of 14 K/A Reference: 202001 Task Number: K2.02 : Rating RO/SRO: Monticello JTA: CR202.013 Objective (s): M-8107L-029, EO-4 1/cmb Liu i i . . . . .-.-

MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 38 of 126 l Exam Question Number: 32 Point Value: 1.00 Time (Minutes): NA Which one of the following describes the effects on the Reactor water chemistry if there is a RWCU resin intrusion? Increased sulfates, increased conductivity, and decreased p Decreased sulfates, decreased conductivity, and decreased p Increased sulfates, increased conductivity, and increased p Decreased sulfates, decreased conductivity, and increased pH.

Answer: A Question No.: 1-B.02.02-021 Reference (s): B.2.2-05 K/A Reference: 204000 Task Number: K1.10 Rating RO/SRO: 3.3/3.5 Monticello JTA: CR204.014 Objective (s): M-8107L-030 EO-8 l I/cmb l

MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 40 of 126 l Exam Question Number: 33 Point Value: 1.00 Time (Minutes): NA Given the following plant conditions:

- Reactor is Shutdown with mode switch in Shutdow . Reactor water levelis 60 inche . Reactor vessel head is installe . No.11 RHR Pump in Shutdown Cooling maintaining 120 degree . No.11 RHR Pump flow is 3600 gp . "B" Loop RHR is isolated and partially drained for leak rate testin . Both Recirc pumps at minimum speed.

If No.11 Bus feeder breaker trips open during 4160 VAC Breaker testing and cannot be immediately reset, Shutdown Cooling injection... must be immediately removed from servic may continue with System Engineer approva flow must be increased to full rated flo conditions are met with no additional adjustments require Answer: C Question No.: 1-C.03-010 Reference (s): C.3. Vill.1, B.03.04-02 i K/A Reference: 205000 Task Number: K6.03 Rating RO/SRO: Monticello JTA: CR205.031 Objective (s): M-8107L-023, EO-14,17 1/cmb !

MONTICELLO NUCLEAR GENERATING PLANT M81000.gg23 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 41 of 126 l Exam Question Number: 34 Point Value: 1.00 Time (Minutes): NA Under which of the following conditions would an operator lose the ability to determine control rod position from Panel C-05? Loss of Y-30 Loss of Y-20 Loss of Y-10 Loss of RPS Busses A and B l l Answer:

C Question No.: 1-B.05.04-008 Reference (s): B.05.04.-02, Page 6 of 6 C.4-B.09.13.A, Page 8 of 12 K/A Reference: 214000 Task Number: A4.02 Rating RO/SRO: 3.8 Montice:lo JTA: CR214.003 Objective (s): M-8107L-058, EO-6 l

l I/cmb l

MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 42 of 126 l Exam Question Number: 35 Point Value: 1.00 Time (Minutes): NA l When placing the RHR system in Torus cooling, it states to verify that the RHR heat exchanger dP is at least 20 psid.

Where is this dP read and exactly what dP are you maintaining? dP read locally at the H RHRSW pressure > RHR pressur dP read in Control Room on Panel C-0 RHRSW pressure > RHR pressur I

      ! dP read locally at the H RHR pressure > RHRSW pressur l dP read in Control Room on Panel C-0 RHR pressure > RHRSW pressure.

Answer: B Question No.: 1-B.03.04-034 . l Reference (s): B.03.04-05 K/A Reference: 219000 Task Number: 2.1.31 Rating RO/SRO: 4.2/3.9 Monticello JTA: CR205.016 Objective (s): M-8107L-023, EO-9 1/cmb _ _ - _ _ _ - - - -

MONTICELLO NUCLEAR GENERATING PLANT M61000-gg23 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 43 of 126 l Exam Question Number: 36 Point Value: 1.00 Time (Minutes): NA l What is the basis for removing Drywell Spray when Drywell pressure drops below 2 psig following a LOCA? - To allow Drywell-to-Torus vacuum breakers to operate properl To reduce the possibility of chugging in the downcomer To avoid exceeding the Drywell Spray Limi To allow Primary Containment pressure to remain above atmospheric pressure.

Answer: D Question No.: l-C.5-1200-001 Reference (s): C.5 EOP 1200,1200 Bases K/A Reference: 226001 l Task Number: K3.01 Rating RO/SRO: 3.6/ Monticello JTA: CR304.010 Objective (s): M-8114L-005, EO-5,7 l

l I/cmb

I J

MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 44 of 126 l Exam Question Number: 37 Point Value: 1.00 Time (Minutes): NA The Shift Supervisor has instructed you to re-open the MSIVs following a Group I isolation.

Which of the following is a concern with outboard air pressure? Mair. air supply pressure must be greater than... psig to assure the MSIVs will close against steam line pressure dPs of 100 psig or greate psig to overcome the weight of the MSIV valve body dis psig to assure proper opening and closing time psig to assure sufficient pressure is available to prevent other MSIVs from drifting close ! Answer: D ) Question No.: 1-B.02.04-015 Reference (s): B-02.04-05 K/A Reference: 239001 Task Number: K4.09 l Rating RO/SRO: 3.3 Monticello JTA: CR240.004 Objective (s): M-8107L-007, EO-2, 6 1/cmb i

MONTICELLO NUCLEAR GENERATING PLANT M81000-gg23 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 45 of 126 l Exam Question Number: 38 Point Value: 1.00 Tme (Minutes): NA l Given the following conditions:

. Plant Startup is in progres * Reactor power is 30%.
. No.11 Feedwater Pump is in servic *

No.11 and No.12 Feedwater Recirculation Flow Control Valves are in AUT * Condensate Recirculation control valves are in AUT . Hotwell level 0 inches with level control in AUTO.

If a trip of No.11 Feedwater Pump were to occur, which of the following valves would be open 30 seconds after the feedwater pump trip? The Condensate Demin Bypass Valv The Reactor Feedwater Recirculation Valve The Condensate Recirculation Valve The Hotwell Makeup Valves.

Answer: C Ouestion No.: 1-B.06.05-020 Reference (s): 8.06.05-02 K/A Reference: 256000 Task Number: K6.06 Rating RO/SRO: 3.3 Monticello JTA- CR259.021 Objective (s): M-8107L-068, EO-3 1/cmb ,

- MONTICELLO NUCLEAR GENEREhUG PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 46 of 126 l Exam Question Number: 39 Point Value: 1.00 Time (Minutes): NA Which of the following is a concern while operating an Emergency Diesel Generator in parallel with the AC Distribution System? Circulatin currents develop within the enerator windi s due to the voltage differences between e system (345KV) and the G output (416 C). During this time the EDG operates in a high voltage low load condition resulting in an increased carbon buildup within the engin l A failure of the grid could overload the EDG resulting in an overs eed trip when the out aut breaker opens. The EDG would not be immediately available if a Station Blackout wou:d occu During this time the EDG is operated at normal speeds and loads are above 50% The ! EDG Turbocharger operating life is significantly reduced as a result of this type of operatio Answer: C Question No.: 1-B.09.08-047 Reference (s): 1-B.09.08-05, Page 5 of 52 K/A Reference: 262001 l Task Number: K1.01 Rating RO/SRO: Monticello JTA: CR264.003 l Objective (s): M-8107L-042, EO-2,4

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i MONTICELLO NUCLEAR GENERATING PLANT M81000-gg23 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 l LICENSE EXAMINATION - ANSWER KEY Page 47 of 126 I l Exam Question Number: 40 Point Value: 1.00 Time (Minutes): NA A fault on the Uninterru atible AC System resulted in a low output voltage (108V) on Y-71. The static switch transferrec to the alternate source. How does the Uninterruptible AC System respond following the automatic transfer to the alternate power source? The Inverter will remain lined up to the alternate until it is manually transferred back to the normal sourc The Inverter will ramp power to the 150% current limit for about 30 seconds and then ramp down to 125% curren The static switch will automatically transfer back to the normal source once the fault has been cleare The static switch will remain lined up to the alternate; the Inverter will go into the ZIP mode.

Answer: C Ouestion No.: 1-B.09.13-012 Reference (s): B.09.13-01 K/A Reference: 262002 Task Number: K4.01 Rating RO/SRO: 3.1 /3.4 Monticello JTA: CR262.006 l Objective (s): M-8107L-063, EO-2 1/cmb

MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 49 of 126 l Exam Question Number: 41 Point Value: 1.00 Time (Minutes): NA Which one of the following components is affected by a complete loss of Div II,250 VDC Distribution Panel, D-1007 MO-2398, RWCU INLET - OUTBOARD VALVE, loses powe MO-2076, RCIC STEAM LINE ISOLATION - OUTBOARD VALVE, loses powe MO-2030, SHUTDOWN COOLING ISOLATION - OUTBOARD VALVE, loses powe MO-2035, HPCI STEAM LINE ISOLATION - OUTBOARD VALVE, loses power.

Answer: D Ouestion No.: 1-B.09.09-007 Reference (s): B.9.9-06, Figures 1 and 2; C.4-B.09.09.A K/A Reference: 263000 Task Number: K2.01 Rating RO/SRO: 3.1/ Monticello JTA: CR206.003 Objective (s): M8107L-002 EO-5 1/cmb

MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 51 of 126 l Exam Question Number: 42 Point Value: 1.00 Time (Minutes): NA Using the following conditions:

. MCC 125 is isolated to investigate a groun . Rx power is 100%
. No.11 and No.12 Circulating Water Pumps are in servic . "B" Recombiner is in Operat . A lockout on Load Center 101 occurs.

For the above conditions, what would be a reason for a loss of condenser vacuum? Loss of Y-25 would result in a trip of the operating recombine Loss of Y-26 would result in a trip of the operating recombine Loss of MCC-116 would result in a loss of excitation to No.12 Circulating Water Pum Loss of MCC-116 would de-energize the solenoids for the air ejector suction valves. These valves fail Closed.

Answer: B Question No.: 1-C.4.B.09-010 Reference (s): C.4-B.00.1 C.4 B.09.1 C.4-B.09.07.A K/A Reference: 271000 Task Number: K3.01 Rating RO/SRO: 3.5 Monticello JTA: CR262.006 Objective (s): M-8107L-063, EO-6 1/cmb

MONTICELLO NUCLEAR GENERATING PLANT MB1000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 52 of 126 l Exam Question Number: 43 Point Value: 1.00 Time (Minutes): NA l During a test of the Process Radiation Monitor (PRM) system a high level trip is in on channel A of the Steam Jet Air Ejector (Off-Gas) Monitor.

What are the automatic actions, related to the PRM system, that occur if there is a loss of RPS MG Set B concurrently with the test? SJAE AUTO ISOLATION TRIP alarms and the Steam Jet Air Ejector suction valves go closed after a 5 second time dela OFF-GAS TIMER ACTUATED alarms are received and the recombiners will trip after a thirty minute time dela There are no automatic actions due to an One-Out-of-Two Taken Twice logic scheme not being satisfie A Group I isolation will occur with a trip of the MVP and an isolation of the MVP suction valves.

Answer: B Question No.: 1-B.',6. ;1 -038 Reference (s): B.5.1 ! -02 K/A Reference: 272000 Task Number: K4.03 Rating RO/SRO: 3.6/3.9 Monticello JTA: CR273.004, CR271.007 Objective (s): M-8107L-077 EO-4, M-8107L-091 EO-11 1/cmb

MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 54 of 126 l Exam Question Number: 44 Point Value: 1.00 Time (Minutes): NA An On-Duty Operator inadvertently depresses the Turbine Building siding deluge initiation button on C-20.

The clapper valve will open resulting in the... Diesel Fire Pump Auto Starting at 70 psig, and flow through the spray nozzle will begin when the fusible links mel Electric Fire Pump Auto Starting at 70 psig and flow through the spray nozzle will begin when the fusible links mel Diesel Fire Pump Auto Starting at 80 psig and flow through the nozzle will begin when sufficient air pressure develops in the HA Electric Fire Pump Auto Starting at 80 psig and flow through the nozzles will begin immediately.

Answer: D Question No.: 1-B.08.05-016 Reference (s): B.08.05-01, Pgs 5,6, and 11 of 20 K/A Reference: 286000 Task Number: A3.04 Rating RO/SRO: 3.2 Monticello JTA: CR286.005 Objective (s): M-8107L-010, EO-4 l l

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l l MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 55 of 126 l Exam Question Number: 45 Point Value: 1.00 Time (Minutes): NA A train derailment has occurred by SHERCO and the resultant gas plume has drifted over the Monticello Plant. The operators have implemented C.4-J (OPERATIONS DURING A TOXIC GAS EVENT) and the proper A-Manual procedures. Two (2) hours into the event a team is preparing to start changing out air supply bottles for the Contro: Room Air Supply Syste ; What does the team need to consider before leaving the Control Room? The team SHALL... don protective gear (i.e., SCBA and chemical suit) before exiting the Control Room into an ' unknown environmen Ensure the toxic gas level is below the IDLH (Immediately Dangerous to Life or Health) i level in the plan ' have at least four people on the team, one for each bottle being replace wait until the SCBA tanks are in alarm before proceeding to change out the Control Room Air Supply bottle i

Answer: A l Question No.: 1-C.4.J-001 Reference (s): C.4-J K/A Reference: 290003 Task Number: A2.02 Rating RO/SRO: 3.1/ Monticello JTA: CR999.011 Objective (s): M-8114L-004, EO-1 1/cmb

I MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 \ TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 56 of 126 ' l l Exam Question Number: 46 Point Value: 1.00 Time (Minutes): NA j During maintenance activities an instrument air line supplying the Main Feedwater Reg Valves was severe ] Which of the following is correct? The Feedwater Regulator Valves will fail... OPEN and may drift CLOSE CLOSED and may drift OPE CLOSED until the Master Flow Control Station is placed in MANUA AS IS and may drift in either direction.

Answer: D

I Question No.: 1-C.4.B.08-004 Reference (s): C.4-B.08.04.0 C.4-B.05.0 K/A Reference: 30000 Task Number: K3.02 Rating RO/SRO: Monticello JTA: CR259.017 Objective (s): M-8107L-046, EO-3 1/cmb

MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 57 of 126 l Exam Question Number: 47 Point Value: 1.00 Time (Minutes): NA The plant is at 100% normal operation. The following alarms are received in the Control Room:

4-B-5 (RECIRC PUMP A LOW COOL WATER FLOW)

4-B-10 (RECIRC PUMP B LOW COOL WATER FLOW)

6-B-32 (RCT BLDG CLG WTR LOW DISCH PRESS) The operator is attempting to restart a RBCCW Pum Which of the following is a required action by the operator if flow cannot be immediately restored?

      ' Trip both Recirc Pumps and insert a Reactor Manual SCRAM at 30 second Trip the CRD Pumps after 60 second I Monitor Fuel Pool Cooling filter outlet temperature and trip both fuel pool pumps if the fuel pool temperature exceeds 150* Close RBCCW Drywell isolation Valves MO-1426, MO-4229, and MO-4230 at 60 seconds.

Answer: D Question No.: 1-C.4.B.02-010 Reference (s): C.4-B.2.5.A K/A Reference: 400000 Task Number: A2.01

Rating RO/SRO: 3.3/ Monticello JTA: CR999.011 Objective (s): M-8114L-002, EO-1 1/cmb

MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 59 of 126 l Exam Question Number: 48 Point Value: 1.00 Time (Minutes): NA l Following a loss of RBCCW, which of the following will minimize fuel pool heatup? Place both fuel pool pumps in service so that RHR Heat Exchangers can be lined u Place available fuel pool pumps in service to mix the pool and prevent thermal stratificatio Place both filter demins in service to maintain fuel pool water chemistr Discharge water to the Condenser Hotwell, then provide makeup from the CSTs.

Answer: B Ouestion No.: 1-B.02.01-013 Reference (s): B.02.01-05 K/A Reference: 233000 Task Number: Al.03 Rating RO/SRO: 3.1/3.3 Monticello JTA: CR999.011, NL233.011 Objective (s): M8107L-022 EO-2,4,5 I

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MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 61 of 126 l Exam Question Number: 49 Point Value: 1.00 Time (Minutes): NA With the plant in a refueling outage, which of the following will place a control rod withdraw block on the Reactor Manual Control System? The Bridge is over the fuel pool with the main grapple lowering a fuel bundle into a fuel pool storage rac The Bridge is over the core, the grapples are all full up, and the Bridge is moving a fuel ; bundle towards the fuel poo The Bridge is over the core, all grapples are full up, and nothing is loaded on any of the grapple The Bridge is over the core, only the frame mounted hoist is not full up, and nothing is loaded on any of the grapple ' Answer: 1 B

Question No.: 1-B.05.05-020 Reference (s): B.5.5-06 K/A Reference: 234000 Task Number: K1.04 Rating RO/SRO: 3.3/3.6 Monticello JTA: CR234.017 Objective (s): M8107L-019 EO-7 1/cmb i

MONTICELLO NUCLEAR GENERATING PLANT M81000-gg23 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 62 of 126 l Exam Question Number: 50 Point Value: 1.00 Time (Minutes): NA An inadvertent Group ll isolation occurred. The cause of the isolation has been identified snd rectified. The operators are in the process of resetting the Group 11 Isolation.

Which cf the following fans automatically start when the isolation reset pushbuttons are depressed? V-FU-5 RWCU Pump Area Filter Unit V-MZ-1 Turb Bldg 951' NW H&V Unit (Supply to 4KV Areas) V EF-28 Reactor Building Fuel Pool Exhaust Fan V-EF-26 SJAE and Pipe Tunnel Exhaust Fan Answer: C Ouestion No.: 1-C.4.B.04-008 Reference (s): C.4-B.4.1.B K/A Reference: 288000 Task Number: K4.02 Rating RO/SRO: 3.7/3.8 Monticello JTA: CR999.011 Objective (s): M8114L-002 EO-1,2 1/cmb

MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 64 of 126 l Exam Question Number: 51 Point Value: 1.00 Time (Minutes): NA You have been instructed to increase Rx power from 50% to 100% using recirc flow control.

Using the following information from the current 3-D Monicore edit:

* MFLCPR .723
* MAPRAT .759
= MFLPD .511     j
      '
* 33 LPRMs rejected
* Rx power 885 MWt I

Which of the following is correct? Increase Rx power 1% for every 0.01 that the closest node is below the MFLPD Action Limi )

      ) A new Full Core Tip Scan (OD-1) and 3-D Monicore must be run prior to increasing the Rx )

powe { A new 3-D Monicore must be run prior to increasing Rx power above 85%. Reactor power may be increased at a rate of up to 15% per minute.

Answer: B Ouestion No.: 1-C.2-004 Reference (s): C.2-01, Page 5 of 15 K/A Reference: 290002 Task Number: K5.01 Rating RO/SRO: Monticello JTA: CR283.011 Objective (s): M-8113L-002 1 i I/cmb l j

MONTIGcLLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 65 of 126 l Exam Question Number: 52 Point Value: 1.00 Time (Minutes): NA l Given the following plant conditions:

* Reactor at 100% power
. Site Power is from the 2R Transformer
. 8N11 GCB is open
. Sudden pressure relays in the main generator transformer cause a main generator lockout (286/G) to occur.

For the above conditions, which of the following is correct? Knife Switch 16/C31 needs to be opened in order to prevent a trip of the circulating water pumps when 8N4 and 8N5 are opene N4 and 8N5 will automatically trip open when the main generator output reaches 0 MWe, J Site power needs to be manually transferred from the 2R Transformer to the 1R Transformer to ensure that the recirculation pumps remain runnin An automatic transfer from 2R Transformer to the 1 R Transformer will have occurred due to the loss of 345kv Bus 1.

Answer: D l

Question No.: 1-C.4.A-022 Reference (s): C.4-A B.09.02-02 B.09.06-01 K/A Reference: 295005 Task Number: AK3.06 Rating RO/SRO: 3.3 Monticello JTA: CR262,006 Objective (s): M-8107L-036, EO-4, 9 1/cmb l

MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 66 of 126 l Exam Question Number: 53 Point Value: 1.00 Ome (Minutes): NA l The plant is operating at 100% power with Feedwater Level Control in MANUAL. A Turbine trip causes a Reactor SCRAM. How does actual water level respond IMMEDIATELY followirig the Reactor SCRAM and why? Increases due to increased feed water flo Decreases due to the loss of recirculation flo Decreases due to the collapse of void Increases due to Feedwater Level Control in MANUAL.

Answer: C ' Question No.: 1-C.4.A-020 Reference (s): C.4-A Bases K/A Reference: 295006 Task Number: AA2.03 . Rating RO/SRO: 4.0/4.2 Monticello JTA: CR999.011 Objective (s): M-8114L-001 EO-3

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MONTICELLO NUCLEAR GENERATING PLANT M81000-gg23 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 68 of 126 Point Value: 1.00 Time (Minutes): NA { Exam Question Number: 54 Using the following information: All SCRAM signals are bypassed per C.5-3101 (ALTERNATE ROD INSERTION)

* Group i isolation Valves CLOSED
= RPS Busses A and B amber lights ON
* Rx power ~ 30%
= Rx water level- 55 inches Which of the following will control Reactor pressure? Low-Low Set will actuat Relief valves will rapidly cycl Turbine Bypass Valves and Low-Low Set will actuat Turbine operation will prevent other actuations.

Answer: B Ouestion No.: l-C.05.01-2000-003 Reference (s): C.05.01-2007, Page 46 of 64 K/A Reference: 295007 Task Number: AA1.04 Rating RO/SRO: 3.9 Monticello JTA: CR314.006 Objective (s): M-8114L-005, EO-7 1/cmb

l i MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 i LICENSE EXAMINATION - ANSWER KEY Page 69 of 126 l Exam Question Number: 55 Point Value: 1.00 Time (Minutes): NA Using the following information:

* Reactor power 4%      l
. MSIVs closed
. Feedwater Level Controlin Manual
* Reactor water level at 0 inches indicated and increasing 1 inch / minute  l
= Reactor pressure 982 psig
* Low-Low set controlling pressure if water level is increasing at a rate of 1 inch / minute and 12 minutes later "H" relief valve opens for 1 minute and then closes, which of the following is the expected range of level indication one minute after the SRV closes? (Assume no operator action.) +12 to +15 inches +6 to +8 inches to -12 inches to -6 inches Answer:

D Question No.: 1-B.03.03-019 Reference (s): B.03.03-05 j K/A Reference: 295009 l Task Number: AK2.02 Rating RO/SRO: Monticello JTA: CR259.017, CR218.004 Objective (s): M-8107L-025, EO-10 1/cmb

MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 l TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 70 of 126 l l Exam Question Number: 56 Point Value: 1.00 Time (Minutes): NA l

Using the following information: l

Rx SCRAM from 80% powe * Rx water level decreased to -60 inches and was then restored to 30 inche * Rx pressure is 820 psig and slowly increasing.

Which of the following describes the status of the Recirc System due to the above events and conditions? l The LPCI Loop Select Logic will... close the Recirc Pump Discharge Valve on the selected loo trip the Recirc Pump Field Breaker for the selected loo lock the scoop tube for the selected loo not initiate unless Reactor pressure decreases to 450 psi I Answer: A Question No.: 1-B.03.04.030 Reference (s): B.03.04-02 (Page 8 of 18) K/A Reference: 295009 Task Number: AA1.03 Rating RO/SRO: Monticello JTA: CR202.013 Objective (s): M-8107L-029, EO-9 1/cmb ___

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MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 71 of 126 i l Exam Question Number: 57 Point Value: 1.00 Tme (Minutes): NA l Using the following conditions:

Mode switch in S/D

. HPCI Auto initiated and is injecting at 3000 gp .

No.11 and No.12 Core Spray Pumps Auto initiate . No.11,12,13, and 14 RHR Pumps Auto Initiate * Rx prerso;e is 950 psi * Rx level decreased to -35 inches and is currently at 0 inches and slowly increasin Which of the following is correct? DW cooling fans are trippe RCIC failed to Auto Star ADS timer is activate Group I Valves Auto Close Answer: A Question No.: 1-B.08.16-001 Reference (s): B.8.16-02 (Page 3 of 5) l l K/A Refercree: 295010 i l Task Number: AK2.05 Rating RO/SRO: Monticello JTA: CR273.006 i Objective (s): M-8107L-044, EO-8 1/cmb

MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 72 of 126 l Exam Question Number: 58 Point Value: 1.00 Time (Minutes): NA During operation at 100% power, the dump valves for the 14A and 15A heaters fail open.

Which of the following describes the plant response to this failure? Condenser Absolute Power Pressure Reactor Level Increase increase Remain Constant Increase Decrease Decrease Decrease increase Remain Constant Decrease Decrease Decrease Answer: A Question No.: 1-B.06.05-021 Refere 4(s): B.06.05-05.01, C.4-B.09.1 K/A h m ance: 295014 Task Number: AK1.06 Rating RO/SRO: Monticello JTA: CR259.021 l Objective (s): M-8107L-068, EO-7, 8 l I l I/cmb

MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 73 of 126 l Exam Question Number: 59 Point Value: 1.00 Time (Minutes): NA The plant is operating at 100% power when a Reactor coolant leak in the Drywell results in the following plant conditions:

. Drywell pressure is at 6 psi * Fifteen control rods are not in past the 04 positio . The EOPs have been entered.

The SS directs you to insert rods per C.5-3101 (ALTERNATE ROD INSERTION). Why does C.5-3101 direct you to close the following valves?

- CRD-79-1, RV-7364A INLET
. CRD-79-2, RV-7364B INLET
= CRD-168, CRD PUMP BYPASS ISOL To minimize radioactive water going to the CST To maximize drive pressure above 400 psi To minimize charging water flo To maximize cooling header dP.

Answer: D Question No.: 1-C.5-3000-009 Reference (s): C.5-3103, Part C K/A Reference: 295015 Task Number: AK2.07 Rating RO/SRO: 3.3/ Monticello JTA: CR314.009 Objective (s): M8114L-011, EO-3 1/cmb

MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 75 of 126 l Exam Question Number: 60 Point Value: 1.00 Time (Minutes): NA Using the following information:

Rx water level - 55 inches and slowly increasing

. Rx pressure 280 psig
.

DW pressure 15 psig and decreasing

. Div I DW spray in service
.

Div I and Div ll Torus Spray in service Ten minutes later Rx water level is being maintained at +35 inches by Feedwater level control system. DW pressure is 6 psig and slowly decreasing.

If the reactor operator depresses the RHR Div i CTMT SPRAY PERM INTERLOCK RESET PB 10A-S23A with DW pressure at 6 psig and slowly decreasing, the Div i Containment Spray Valves will... remain open and will NOT automatically clos remain open and automatically close when DW pressure decreases to approximately 2 psi remain open and automatically close when DW pressure decreases to approximately O.75 psi l close immediately.

Answer: C j Question No.: 1-B.03.04-029 Reference (s): B.03.04-02 K/A Reference: 295024 Task Number: EA1.17 Rating RO/SRO: 3.9 Monticello JTA: CR205.035 Objective (s): M-8107L-023, EO-8,10 1/cmb

MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 76 of 126 l Exam Question Number: 61 Point Value: 1.00 Time (Minutes): NA What is the function of the Low-Low-Set System? I Provides overpressure relief operation to prevent overpressurization of the primary nuclear syste Provides a backup to the HPCI System for automatically depressurizing the Reacto Provides about a 30 psig blowdown of the Reactor Vessel on high pressur Minimize the possibility of a safety relief valve reopening while an elevated water leg exists in the discharge line.

Answer: D Question No.: 1-B.03.03.-016 Reference (s): B.03.03-01 K/A Reference: 295025 Task Number: EK3.09 Rating RO/SRO: 3.7/3.7 Monticello JTA: CR218.003, CR999.003 Objective (s): M-8107L-025, EO-7, 9 l 1/cmb

MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 78 of 126 l Exam Question Number: 62 , Point Value: 1.00 Time (Minutes): NA Given the following Plant conditions:

- Mode Switch in Shutdown
* Reactor power ~20%
* Reactor pressure at 1090 psig
. Procedure C.5-3101 in progress
. SBLC System 1 injecting
. Torus water temperature 115 degrees and increasing.

Per the Emergency Operating Procedures, answer the following two (2) question . Why would the operators lower water level during the above event? At what water !evel would the operators stop lowering water level? . To increase core void fractio . -174 inches . To increase core vold fractio . -126 inches . To increase natural circulatio inches . To increase natural circulatio . -126 inches Answer: l Question No.: 1-C.05.01-2000-001 Reference (s): C.5.1-2007; C.5-2007 K/A Reference: 295031 Task Number: EA2.02 Rating RO/SRO: Monticello JTA: CR314.007 Objective (s): M-8114L-005, EO-6 1/cmb ;

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MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 , LICENSE EXAMINATION - ANSWER KEY Page 79 of 126 l l l l Exam Question Number: 63 Point Value: 1.00 Time (Minutes): NA l Given the following conditions:

- ATWS Event in progress
. SBLC System 1 injecting
* Immediate SCRAM actions complete
. Reactor pressure being maintained by the Turbine Bypass Valves What effect could an inadvertent Reactor cooldown during an ATWS event have regarding the plant?

l

A Cooldown of the Reactor will cause... SBLC effectiveness to increase due to more boron being dissolved in the Reactor coolant at lower temperature the MSIVs to close at 840 psig thereby further challenging primary containmen Reactor power to increase or cause the Reactor to return to criticalit l unreliable Safeguards level instrument readings due to the instruments being calibrated Ho Answer: C Question No.: 1-C.05.01-2000-002 Reference (s): C.5.1 -2007 K/A Reference: 295037 Task Number: EK1.06 Rating RO/SRO: Monticello JTA: CR314.007 Objective (s): M-8114L-005, EO-6 1/cmb

610NTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 80 of 126 l Exam Question Number: 64 Point Value: 1.00 Time (Minutes): NA During Loss of Coolant (LOCA) conditions CGCS is used to control the build-up of combustible gasses in the Drywell and Torus.

Which gas and at what concentration is CGCS designed to prevent exceeding? ,6%. O2,5%. I H,8%. 2 H,4%.

Answer: B Ouestion No.: 1-B.04.03.02-010 Reference (s): B.04.03.02-05 K/A Reference: 500000 Task Number: EK3.03 Rating RO/SRO: 3.0/3.5 Monticello JTA: CR244.003 Objective (s): M81071-079, EO-01 1/cmb

MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSW'ER KEY Page 82 of 126 l Exam Question Number: 65 Point Value: 1.00 Time (Minutes): NA Following a trip of No.11 Recirculation Pump, the following conditions exist:

. Reactor power 1065 MWth
.

SPDS core flow indicates 29 Mlbm/Hr

. No.11 Recirc Jet Pump flow indicates 3.5 Mibm/Hr
- No.12 Recirc Jet Pump Flow indicates 26.5 Mlbm/Hr Using the above conditions, choose the correct answe The Buffer region of the Power / Flow Map has been entered and must be exited by driving control rods or increasing recirculation flo The Exclusion Region of the Power / Flow Map has been entered and an immediate Reactor Scram is require Power distribution controls are not required at this time. The operator should continue to monitor for entry into either the Buffer or Exclusion Region The Buffer Region of the Power / Flow Map has been entered, however, no action is rec ulred. Operators should notify the Nuclear Engineering Staff for guidance to exit the Bu'fer Region.

Answer: A PROVIDE POWER - FLOW MAP WITH EXA Question No.: 1-C.4-B.05-005 Reference (s): C.4-B.05.01.02-A K/A Reference: 295001 Task Number: AK2.07 Rating RO/SRO: Monticello JTA: CR999.011; CR202.013 Objective (s): M-8107L-029, EO-8 1/cmb

_ MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 83 of 126 l Exam Question Number: 66 Point Value: 1.00 Time (Minutes): NA l While performing Rapid Power Reduction due to a Off-Gas Recombiner trip, the following conditions occur:

. Condenser Vacuum 24 inches Hg and slowly decreasing
. Generator output 190 MWe
* Rx water level +35 inches
* Reactor Recirc for both loops at minimum The Shift Supervisor orders the C-05 Operator to redace Reactor power an additional 10% in an attempt to increase condenser vacuu . If condenser vacuum does not improve from the power reduction, what action is required? Why is this action required? . Open the Condenser Crosstie Valve . To protect the Turbine bladin . Open the Condenser Crosstie Valve . To allow the MVP to be placed in-servic . A manual SCRAM is rec uire . To protect the Turbine b'adin . A manual SCRAM is re uire . To allow the MVP to be laced in-service.

Answer: C Question No.: 1-C.4-B.06-007 Reference (s): C.4-B.6.3.A (DECREASING CONDENSER VACUUM) K/A Reference: 295002 l

Task Number: AK3.02 Rating RO/SRO: , Monticello JTA: CR999.011, CR255.002

Objective (s): M-8104L-002, EO-1, M-8107L-011, EO-5 l 1/cmb l

MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 84 of 126 l Exam Question Number: 67 Point Value: 1.00 Time (Minutes): NA l The plant was operating at 100% power when an electrical disturbance on the NSP System resu ts in a loss of offsite powe The following conditions exist:

. Busses 11 through 16 show 0 volt . RCIC is injecting at full flo . Bus 16 has a Lock Ou . HPCI is injecting at full flo .

No.11 EDG failed to star * MSIVs are close * Reactor water levelis at -10 inches * All control rods are full i and increasin What is the preferred method for maximizing battery availability and maintaining Reactor water level control? Manually tria RCIC, then verify RCIC Testable Check Valve AO-13-22 is closed. Use HPCI to maintain level -126 inches to +48 inche Manually trip RCIC, then Isolate the steam lines by closing the Steam isolation Valve Use HPCI to control level -150 inches to +48 inche Manually trip HPCI, then place the HPCI Aux Oil pump and HPCI Gland Seal Condenser Blower in Pull-To-Lock. Use RCIC to maintain level -126 inches to +48 inche Manually trip HPCI, then place the HPCI Aux Oil Pump and HPCI Gland Seal Condenser Drain Pump in Pull-To-Lock. Use RCIC to control level -150 inches to +48 inche l Answer: C

..

Question No.: 1-C.4-B.09-012 Reference (s): C.4-B.09.02.A (STATION BLACKOUT)

K/A Reference: 295003 Tas'k Number: AK1.06 Rating RO/SRO: 3.8/ Monticello JTA: CR999.011, VR217.007 Objective (s): M-8114L-003, EO-1,2; M-8107L-003, EO-10 l I/cmb ] l -

MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 . TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 86 of 126 l Exam Question Number: 68 Point Value: 1.00 Time (Minutes): NA Using the following information:

- Mode Switch in Shutdown following a Reactor SCRAM
. Reactor water level currently +30 inches and slowly decreasing
. Drywell pressure is 1.9 psig and increasing
. White light above HPCI High Level Trip Reset Pushbutton is Of For the above conditions, what will be the response of the HPCI System and why? Fail to initiate on low-low Reactor water level unless the high level trip is rese Fall to initiate on high Drywell pressure unless the high level trip is rese Automatically initiate on Low Low Reactor level or high Drywell pressure, due to the high Reactor water level trip having already been rese Automatically initiate on high Drywell pressure as long as Reactor level is below +48 inche .

Answer: B Ouestion No.: 1-B.03.02-023 Reference (s): B.3.2-01 K/A Reference: 295008 Task Number: AA1.04 Rating RO/SRO: Monticello JTA: CR206.003 Objective (s): M-8107L-002, EO-7 1/cmb -. _- _

MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 87 of 126 > l Exam Question Number: 69 Point Value: 1.00 Time (Minutes): NA Following a loss of coolant accident, the SS orders that an RPV Emergency Depressurization be initiated based on Drywell temperatures approaching 281* What is the basis for depressurizing the Reactor when Drywell temperatures approach 281*F? To ensure... energy within the Reactor is directed to the Torus before the Torus Heat Capacity Limit is exceede the blowdown is performed such that the RPV water level instruments remain vali the blowdown is performed while the ADS Valves are still operable and before temperature rises high enoug a to damage the Drywel that additional damage to the RPV is prevented when the ability to maintain Primary Containment integrity is being challenge Answer: C l Question No.: 1-C.5-01-1200-001 l Reference (s): C.5.01-1200 K/A Reference: 295028 Task Number: EK3.01 Rating RO/SRO: Monticello JTA: CR999.012, CR304.010 Objective (s): M-8107L-028, EO-3 M-8114L-005, EO-6 1/cmb _

MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 88 of 126 l Exam Question Number: 70 Point Value: 1.00 Time (Minutes): NA The plant is performing a startup with HPCI testing in progress. RCIC and SRV testing are scheduled to follow. Plant parameters are as follows:

= Reactor Pressure 140 psig
= Reactor Level +38 inches
* Drywell Temp 120'F
= Drywell Pressure +0.3 psig
=

Torus Level +0.3 inches

- Torus Temp  80'F The RHR System should be placed in which mode of operation? RHR is not required to be in service at this tim . Shutdown Cooling Torus Drain to Radwaste Torus Cooling Answer:

D Question No.: 1-B.03.02-022 Reference (s): B.03.02-05; B.03.03-05 VJA Reference: 295013 Task Number: AK1.03 Rating RO/SRO: 3.0/ j Monticello JTA: CR205.016 l Objective (s): M-8107L-025, EO-10

1/cmb l .

MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 90 of 126 l Exam Question Number: 71 Point Value: 1.00 Time (Minutes): NA I There has been a Control Room fire that has forced an evacuation of the Control Room. The oprators have entered C.4-0 (SHUTDOWN OUTSIDE OF THE CONTROL ROOM) procedur The operators have started a cooldown using SRV TIME LINE: Time (In mins.) Reactor Pressure (in osia) j 0 1005 SCRAM per C.4-C l 20 800 ' 30 690 40 550 50 510 60 400 Given the time line from the event for Reactor pressure, determine if the operators violated the l i cooldown requirements for the above condition I No, all points on the chart trace stay within the operation allowed area of the Reactor Depressurization Rate Curv Yes, the time line shows that Reactor pressure dropped into the operation not allowed area , for one data point on the above time l,ne, i i Yes, the time line shows that Reactor 3ressure dropped into the operation not allowed area for two data points on the above time in { 1 Yes, the time line shows that Reactor pressure dropped into the operation not allowed area i for three data points on the above time lin > Answer: C PROVIDE FIGURE 2, RX DEPRESSURIZATION RATE, C.4-C WITH EXA Question No.: 1-C.4.C-001 Reference (s): C.4-C, Revision 15, Page 29 of 29 K/A Reference: 295016 Task Number: 2.1.25 Rating RO/SRO: 2.8/ Monticello JTA: CR218.004, CR999.011 Objective (s): M-8107L-025, EO-1,2,4; M-8114L-004, EO-1 1/cmb l l l . J

MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 92 of 126 l Exam Question Number: 72 Point Value: 1.00 Time (Minutes): NA A leak in the Reactor Building has caused SBGT to initiate on High Radiation in the Reactor CIATOR). Duri(ng investigation of the alarm, ANNUh the operator notices that "B" SBGT hasBu Automatically initiated and "A" SBGT has tripped.

What action will the operator perform to protect the SBGT System from damage? Place "A" SBGT Train in the Cooling Mod Isolate "A" SBG Place "B" SBGT in Manual operatio Swap Stack Dilution Fans.

Answer: A Question No.: 1-B.04.02-022 , Reference (s): 8.04.02-02 B.04.02-05 K/A Reference: 295017 Task Number: AA1.09 Rating RO/SRO: Mcnticello JTA: CR261.008 Objective (s): M-8107L-008, EO-11 1/cmb

MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 93 of 126 l Exam Question Number: 73 Point Value: 1.00 Time (Minutes): NA Given the following current conditions:

. Loss of normal off-site power has occurre No.11 EDG runnin * No.12 EDG runnin * No.15 bus and LC-103 de-energize = No.16 bus and LC-104 energized.

Which of the following is an operational concern? Loss of condenser cooling to RCI Loss of room cooling to HPC Loss of cooling to No.11 ED Loss of cooling to No.12 EDG, Answer: C Ouestion No.: 1-C.4-B.09.02-001 Reference (s): C.4-B.09.02.A K/A Reference: 295018 Task Number: AK1.01 Rating RO/SRO: 3.5 Monticello JTA: CR999.011 Objective (s): M-8114L-002, EO-1, 2 i I 1/cmb I

MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 94 of 126 l Exam Question Number: 74 Point Value: 1.00 Time (Minutes): NA A Reactor startup is in progress. The following plant conditions exist:

* Reactor pressure 100 psi * No.14 Air Compressor is isolated for maintenanc * No. 'l Air Compressor trippe * No.13 Air Compressor failed to star * 6-B-24, INSTRUMENT AIR DRYER BYPASSED, is in alar . 6-B-30, INST AIR HEADER LOW PRESS, is in alar Which of the following conditions effects system operability?

l CRD flow control valves fail closed preventing normal control rod drive movemen ! 1 RHR pump minimum flow valves fail open causing a decrease in Reactor water level, i EDG ventilation supply dampers fail closed preventing room coolin SBGT valves fail closed preventing continued operatio Answer: A Question No.: 1-B.03.04-035 Reference (s): B.03.04-02, C.4-B.08.04.0 ~ K/A Reference: 295019 Task Number: AA2.02 Rating RO/SRO: Monticello JTA: CR278.004 Objective (s): M-8107L-023, EO-8 1/cmb .

MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 95 of 126 l l Exam Question Number: 75 Point Value: 1.00 Time (Minutes): NA While performing the quarterly SBLC Functional Test, a miscommunicabn results in a Control Room Operator starting the No.11 SBLC Pump from C05 rather than lo cally, as directed by the { procedur Due to this error, which of the following would be correct? Both Squib Valves would be 3 re The operating RWCU Pump will receive a direct trip from the SBLC logi SBLC Pump injection to the Reactor will be prevented due to system alignment in test statu An RWCU lsolation will occur causing MO-2399, MO-2397 and MO-2398 to Clos . Answe D l Question No.: 1-B.02.02-022 Reference (s): B.02.02-01, B.03.05-01, 8.03.05-02 i K/A Reference: 295020 Task Number: AK2.04 l ( Rating RO/SRO: Monticello JTA- CR211.012 Objective (s): M-8107L-004, EO-8 l 1/cmb _

MONTICELLO NUCLEAR GENERATING PLANT M81000-gg23 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 96 of 126 l Exam Question Number: 76 Point Value: 1.00 T:me (Minutes): NA Given the following Plant conditions:

* Reactor is at 90% power for monthly valve testin * Drywell pressure is 1 psi . Reactor water level is +35 inche . No.11 RBCCW Pump in service
.

No.11 CRD Pump is isolated for replacement of the pump bearing = No.12 CRD Pump in service

Alarm 5-B-38 (CRD ACCUMULATOR LO/ PRESS Hl/ LEVEL) is in Alarm for HCU 26 27.

A fault on Bus 16 occurs causing the 4160 Bus to Lock Out.

While the operators are responding to the Bus Lockout, HCU 10-39 has its orange accumulator light come o ( What actions are required for the above conditions? Trip both Recirc pumps in 60 second Manually SCRAM the Reacto Isolate the CRD Pump Start a Condensate Pump.

Answer: B l Question No.: 1-C.4-B.01-020 l Reference (s): C.4-B.1. j K/A Reference: 295022 I Task Number: AA2.01 l Rating RO/SRO: 3.5/ Monticello JTA: CR999.011, CR201.021 Objective (s): M-8114L-002, EO-1; M-81071-020, EO-7,12 1/cmb

MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 98 of 126 , l Exam Question Number: 77 Point Value: 1.00 Time (Minutes): NA Using the following conditions:

Drywell pressure 7.3 psig and increasing

Rx water level -40 inches (manual control)

Rx pressure 1008 psig and decreasing

. 67 control rods not Full-in
. Torus temperature 110*' and increasing
. MSIVs Closed
. Torus water level +1 foo Which of the following EOP actions is appropriate for these conditions and why? Spray Drywell to prevent SRVs from exceeding the Torus Boundary Design Loa Maintain water level +9" to +48" to prevent large power swings on the Reactor Cor Emergency Depressurize to prevent Drywell pressure from exceeding Primary Containment Pressure Limi Inject SBLC to prevent Torus temperature from exceeding the Heat Capacity Limi Answer:

D Question No.: 1-C.5-2000-013 Reference (s): C.5-2007, C.5.1-2007, C.5.1-1200 f K/A Reference: 295026 Task Number: EK3.04 Rating RO/SRO: Monticello JTA: CR314.007 Objective (s): M-8114L-005, EO-6,7 1/cmb -_ .__

MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 ! LICENSE EXAMINATION - ANSWER KEY Page 99 of 126 f l l Exam Question Number: 78 Point Value: 1.00 Time (Minutes): NA Given the following conditions:

. SPDS failed due to a computer software proble * TR 23-115 pt. 21 = 156' F
. The plant was manually scrammed following a stuck open "B" SR . TR 23-115 pt. 22 = 129' F
. Reactor levelis being maintained at 30 inche . TR 23-115 pt. 23 = 152* F
* Annunciator 5-B-53 "DW-TORUS  TR 23-115 pt. 24 = 164" F AIR HI TEMP" is in alarmed conditio The SS directs the Control Room Operator to closely monitor the primary containment I parameters due to the failure of SPDS concurrent with changing plant condition Using the above conditions, determine the value for bulk Drywell temperatur .1* F     ' .4* F .3* F .0" F Answer:

A PROVIDE OPERATOR AID C-13 (BULK DRYWELL TEMP CALC) WITH EXAM l Question No.: 1-C.05.01-1000-001 Reference (s): C.S.1-1200 K/A Reference: 295028 ) l Task Number: EA2.01 Rating RO/SRO: Monticello JTA- CR304.010 Objective (s): M-8114L-005, EO-4,5 1/cmb -

. MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 100 of 126 l Exam Question Number: 79 Point Value: 1.00 Time (Minutes): NA The EOPs direct the operator to remove HPCI from service at a Torus level of -3.7 fee Why does HPCI have to be removed from service at this Torus level? The level is low enough to allow air to enter the HPCI Pump Suctio HPCI exhaust would pressurize the Torus air spac Minimum flow requirements cannot be met because of flow vortex limit The Drywell-Torus Vacuum Breakers are completely uncovered allowing HPCI exhaust to discharge directly into the Drywel Answer: B Question No.: 1-C.5-1000-070 Reference (s): C.5.1-1200 EOP K/A Reference: 295030 Task Number: EK2.01 Rating RO/SRO: l Monticello JTA: CR304.010, CR206.003 Objective (s): M-8114L-005, EO 6 M-8107L-002, EO-5 1/cmb

MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 101 of 126 l Exam Question Number: 80 Point Value: 1.00 Time (Minutes): NA When resetting Floor and a Reactor Equipment SCRAM, Drain Tank Room why?are you directed to evacuate the Reactor Building 8 The Scram Discharge Volume vent and drains empty into the Floor and Equipment Drain Tanks when unisolating the vent and drains causing radiation levels to possibly increas The Scram Discharge Volume vents will blow steam directly into the Floor and Equipment Drain Tank Room when the SCRAM signal is reset causing airborne radiation levels to possibly increas I l The SCRAM valves will discharge a burst of air into the Floor and Equipment Drain Tank Room causing the airborne radiation levels to possibly increas { The SCRAM valves will vent the Reactor pressure into the Floor and Equipment Drain Tanks causing radiation levels to possibly increase.

Answer: A Question No.: 1-C.4.A-021 Reference (s): C 4-A K/A Reference: 295033 Task Number: EK3.04 Rating RO/SRO: 4.0/4.4 Monticello JTA- CR999.011 Objective (s): M-8114L-005 EO-6,7

1/cmb i

l MONTICELLO NUCLEAR GENERATING PLANT M81000-gg23 l TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 103 of 126 l Exam Question Number: 81 Point Value: 1.00 Time (Minutes): NA A Primary Containment Group 2 Isolation is initiated as a result of high radiation conditions in the Reactor Building plenum. The SBGT System initiates and the Reactor and Turbine Building ventilation systems operate properly.

If indications of a significant radioactive leak were identified in the Turbine Building, which of the following would be correct? The SBGT System should be re-aligned to take suction from the Turbine Buildin l Operation of the SBGT System should be secured to prevent contaminants from being drawn into the Reactor Buildin The Turbine Building supply fans should remain tripped to prevent circulating contaminants in the Turbine Buildin The Reactor Building plenum exhaust fans should be started to assure the release is 1 monitored by the RBV WRGM J l l l I l Answer: i i l I i Question No.: 1-C.4-B.04-009 C.4-B.4. I Reference (s): K/A Reference: 295034 Task Number: EK2.04 I

Rating RO/SRO: Monticello JTA: CR999.011; CR261.007 Objective (s): M-8114L-002, EO-1,2 M-8107L-008, EO-11 1/cmb

MONTICELLO NUCLEAR GENERATING PLANT

M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 104 of 126 l Exam Question Number: 82 Point Value: 1.00 Time (Minutes): NA l Reactor power is approximately 3% during a Reactor startup. Main Steam Line radiation levels are increasing due to a leaking fuel bundle. -A short time later, condenser vacuum begins to decrease.

Choose the correct answer.

Condenser vacuum is decreasing due to the... trip of the Hydrogen Water Chemistry Syste trip of the MechanicalVacuum Pum trip of the Steam Jet Air Ejector Suction Valve , auto isolation of the Main Steam isolation Valve l Answer: I B Ouestion No.: 1-8.05.11-039 Reference (s): B.05.11-02 K/A Reference: 295038 Task Number: EK2.10 Rating RO/SRO: Monticello JTA: CR255.002 Objective (s): M-8107L-011, EO-3 1/cmb

MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 105 of 126 , l Exam Question Number: 83 Point Value: 1.00 Time (Minutes): NA If a Fire Alarm is activated on Panel C-348 (REACTOR BUILDING ELEVATOR LOBBY AND MACHINE ROOM SMOKE DETECTOR ANNUNCIATOR PANEL), what automatic actions occur? A Trouble Alarm is sent to... the Control Room on C-20 and the Reactor Building elevator goes into phase 1 operatio the Control Room on C-20 and the Reactor Building elevator goes into phase ll operatio C-300 (ZONALERT CONTROL ROOM ANNUNCIATOR) and the Reactor Building elevator goes into phase I operatio C-300 (ZONALERT CONTROL ROOM ANNUNCIATOR) and the Reactor Building elevator goes into phase ll operatio I I

Answer: C 1

Question No.: 1-B.08.05-017 Reference (s): B.08.05-01 B.08.15-02 K/A Reference: 60000 Task Number: AA1.06 Rating RO/SRO: ,

Monticello JTA: CR286.005 l Objective (s): M-8107L-010, EO-2,6 i I/cmb

MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 106 of 126 l Exam Question Number: 84 Point Value: 1.00 Time (Minutes): NA What is the reason that the operator is directed to control Reactor water level greater than +55 inches when in RHR Shutdown Cooling operations? Reactor water level is maintained greater than 55 inches to ensure... the feedwater spargers effectively mix the feedwater added to the Reactor Vesse the Reactor water level instrumentation remains on scale when the Reactor water temperature increase the water from the annulus area of the Reactor flows into the core shroud area as level decreases inside the shrou the availability of natural circulation as a backup to forced circulation flow.

Answer: D Question No.: 1-C.4.8.03-010 Reference (s): C.4-B.03.04.A K/A Referenca; 295021 Task Number: AK3.05 Rating RO/SRO: 3.6 Monticello JTA: CR999.011 Objective (s): M-8114L-002, EO-1,2 1/cmb

MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision

LICENSE EXAMINATION - ANSWER KEY Pagt. ED7 of 126 l Exam Question Number: 85 Point Value: 1.00 Time (Minutes): NA I During a Refuel Outage, half-way through a Full Core Unload, the refueling crew notifies the i Control Room that they dropped a fuel bundle and it is balancing over the edge of the cattle j shoot. Using the following information: , a Refuel Floor radiation levels are normal

* Rx Building radiation levels are normal
. Rx Building Plenum radiation levels are normal Immediately following the incident, which of the following is a correct action for the refueling crew? Attempt to move the fuel bundle to a stable orientatio Evacuate the Rafuel Floor of all personnelimmediatel Move the bundle to a stable location and then evacuate the Refuel Floor of all personne Halt refuelin monitoring. g operations and notify the Radiation Protection Coordinator to initiate Answer:

B Question No.: 1-D.02-05-001 Reference (s): D.2-05 - K/A Reference: 295023 Task Number: AA1.04 Rating RO/SRO: Monticello JTA: CR234.014

Objective (s): M-8107L-019, EO-5 1/cmb

MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 108 of 126 l Exam Question Number: 86 Point Value: 1.00 Time (Minutes): NA Given the following plant conditions:

Reactor SCRAM from 90% powe * A steam leak in the 935' Reactor Building West CRD HCU area has just been reporte . Local report is that the area is too hot to enter.

Which of the following is correct concerning EOPs? There are no EOP entry conditions associated with a high temperature in this are EOPs will be entered if local reports on temperature in the area indicate that temperature is greater than 120o EOPs will be entered when the area temperature monitoring equipment indicates greater than 130oF in the are EOPs will be entered due to the spread of airborne contamination caused by the steam leak.

Answer: B Ouestion No.: 1-C.5-1000-067 Reference (s): C.5-1300 Bases K/A Reference: 295032 Task Number: EK2.06 Rating RO/SRO: 3.3/3.4 Monticello JTA: CR304.012 Objective (s): M-8114L-005 EO-6,7 1/cmb

- .. MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 110 of 126 l Exam Question Number: 87 Point Value: 1.00 Time (Minutes): NA l Thirty (30) minutes after an earthquake, the following conditions exist:

. Reactor water levelis norma . All control rods are at position 0 . One (1) foot of water is on the Torus floor due to a leaking Torus drain flang . The MSIVs are Close . Reactor Scram has been rese . RPS Busses A & B amber lights are o . Torus levelis -2 fee For the above conditions, which of the following is correct? Water will be flooding the 250 VDC MCC-31 RHR Room ECCS surnp pumps are runnin RHR and Core Spray pumps are unavailabl Full core display " Blue" Scram lights are O .

Answer: B

Question No.: 1-B.07.01 -001 Reference (s): B.07.01-02 (Page 28 of 47) K/A Reference: 295036 Task Number: EA2.02 Rating RO/SRO: Monticello JTA: CR209.007, CR205.010 Objective (s): M-8107L-005, EO-3; M-8107L-101, EO-2, 4 I 1/cmb

.       J

MONTICELLO NUCLEAR GENERATING PLANT M81000-gg23 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 111 of 126 l Exam Question Number: 88 Point Value: 1.00 Time (Minutes): NA A Duty Control Room Operator received a call from the Turbine Building Operator. The Turbine Building Operator states that a small fire has started on No.11 EDG Oil System and he was unable to put it out with a fire extinguisher.

The Control Room Operator's FIRST action is to... sound the fire alar Initiate an evacuation of the EDG Roo Instruct the Turbine Building Operator to secure the No.11 ED notify the System Engineer to investigate with the Turbine Building Operator.

Answer: A Question No.: 1-C.04.B.08-006 Reference (s): 0.04-B.08.05.A K/A Reference: Generic Knowledge and Ability Task Number: 2.4.27 Rating RO/SRO: 3.0 Monticello JTA: CR999.011 Objective (s): M-8114L-002, EO-1 1/cmb

i MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 112 of 126 l l Exam Question Number: 89 Point Value: 1.00 Time (Minutes): NA While conducting a plant tour you come across an injured individual that appears to have fallen.

Which of the following is the proper response? Notify the SS at Ext.1140 and report to the Fire Brigade Assembly Roo Notify the Control Room at Ext. 9111, and move the victim from any immediate hazard Retrieve the emergency medical kit from the Fire Brigade Room and administer first aid while waiting for the emergency medical team to arriv Notify the Control Room at Ext. 5111 and stay with the victim until the Fire Brigade arrives.

Answer: D Question No.: 1-A.5-001 Reference (s): A.5-100 K/A Reference: Generic Knowledge and Ability l Task Number: 2.1.16 Rating RO/SRO: 2.9 Monticello JTA: CR999.008 Objective (s): M-7702L-004, EO-27 M-8108L-033, EO-1 1/cmb

MONTICELLO NUCLEAR GENERATING PLANT M81000-gg23 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 113 of 126 l Exam Question Number: 90 Point Value: 1.00 Time (Minutes): NA During a plant outage, No.11 Core Spray System was tagged out for maintenance. The breaker for the pump motor needs to be removed from the cubicle for preventative maintenance and inspection. What action (s) are required when the breaker is removed from the cubicle? Additional tags are added to the cubicle to identify the. component as tagged ou The Hold or Secure cards are transferred to the empty cubicl The Hold or Secure cards SHALL be removed and maintained in the physical possession of the maintenance personne An operator SHALL ensure that the electrical equipment has been de-energized by performing a test for DEA ,

Answer: B

Question No.: l-AW1.04-031 Reference (s): 4 AWi-04.04.01 K/A Reference: 2.1, Conduct of Operations Task Number: 2. Rating RO/SRO: 3.0 - Monticello JTA: CR299.012, CR999.007 Objective (s): M-8108L-029, EO 1 1/cmb

MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC !NITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 114 of 126 gm Quecilon Number: 91 Point Value: 1.00 Time (Minutes): NA l The C.4 Abnormal Procedures are written to address a wide variety of plant condition If, while performing one of these procedures, a SUBSEQUENT ACTION STEP does not apply to the current conditions, what is the operator required to do? Process Form 3087 (DOCUMENT CHANGE, HOLD AND COMMENT FORM) to have the , STEP changed before proceeding to the next ste Process a temporary change before proceeding in the procedur Omit the step and continue in the procedur Make an entry in the Control Room Log describing compensatory actions take Answer: C Ouestion No.: 1-C.4-003 Reference (s): C.4 (GENERAL INSTRUCTIONS), Page 2 of 4 K/A Reference: Generic Knowledge and Ability Task Number: 2.1.20 Rating RO/SRO: Monticello JTA: CR999.011 Objective (s): M-8114L-001, EO-1 1/cmb

MONTICELLO NUCLEAR GENER4 TING PLANT M81000-9923 , TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 115 of 126 l Exam Question Number: 92 Point Value: 1.00 Time (Minutes): NA l Given the following plant parameters:

. Reactor is shutdow * Refueling is in progres * Reactor level is -40 inches on the safeguards indicator * No.11 SBGT system is isolate . No.11 EDG is tagged out for maintenanc . Calibration of the Turbine first stage pressure transducer is in progres * All other plant equipment is normal.

What does the Monticello Technical Specifications have to say about the above conditions? A Safety Limit is being exceeded due to Reactor water leve A LSSS is being exceeded due to the Turbine Control Valve Fast Closure Scram being inoperabl A LCO is in effect due to SBGT system being inoperabl A LCO is in effect due to No.11 EDG being out of service, l Answer: I C

Question No.: 1-TS-046 Reference (s): T.S. 3.7-4.7 - (CONTAINMENT SYSTEMS) i Ops Manual B.04.02-05 j I K/A Reference: GENERIC KNOWLEDGES AND ABILITIES Task Number: 2.1.33 Rating RO/SRO: 3.4/ l Monticello JTA: CR999.004 Objective (s): M-81081-003, EO-3 i

1/cmb

MONT7 CELLO NUCLEAR GENERATING PLANT M81000-gg23 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 116 of 126 l Exam Question Number: 93 Point Value: 1.00 Tme (Minutes): NA l While conducting a routine surveillance test, the Turbine Building APEO calls the Control Room requesting permission to complete STEP 46 of the procedure pnor to completing STEP 45.

Which one of the following actions is required to allow performance of STEP 46 prior to STEP 45? Completion of the steps out-of-order is allowed only if a temporary change to the procedure is processed by the SS or S Completion of the steps out-of-order is allowed if the operator places a note in the Comments Section of the procedur OC Review is required prior to performing the procedure. Stop the surveillance and submit a procedure change for Completion of the steps out-of-order is allowed if the System Engineer approves the step sequenc { Answer: A Question No.: 1-4AWI.04-027 Reference (s): 4 awl-04.05.07 (PROCEDURE IMPLEMENTATION) K/A Reference: Generic Knowledge and Ability Task Number: 2.1.20 Rating RO/SRO: Monticello JTA: CR999.007 Objective (s): M4108L-029, EO-1 1/cmb

MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 117 of 126 l Exam Question Number: 94 Point Value: 1.00 Time (Minutes): NA l Electricians have called the Control Room to request that operations stroke a motor-operated valve for VOTES testing. When the operator goes to stroke the valve per the Electrician's request, both a VOTES tag and a Secure Card are found on the valve handswitch for the valve.

What course of action is required by the operator? Stroke the valve per the Electrician's reques Notify the SS that there is a Secure Card on the valve handswitc Notify the Site Safety Coordinator of an unsafe conditio Remove the Secure card, stroke the valve, then replace the Secure car l l I Answer: j B I e Question No.: 1-4 awl-04-028 Reference (s): 4 awl-04.04.01 (EQUIPMENT ISOLATION) K/A Reference: Generic Knowledges and Abilities Task Number: 2.2.13 Rating RO/SRO: 3.6/ Monticello JTA: CR299.012 Objective (s): M-8108L-029, EO-1 1/cmb l

l

MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Rev sion 0 LICENSE EXAMINATION - ANSWER KEY Page 119 of 126 l Exam Question Number: 95 Point Value: 1.00 Time (Minutes): NA You are currently assigned as the Control Room Operator on C-05 during refueling activities. You have not heard from the refuel bridge for 10 minutes and contact them to inquire about their activities. The operator doing accountability informs you that a blade guide was inadvertently alaced in the wrong cell in the Reactor and that they have just completed moving it to the correct ocatio ! Choose the correct answe The Supervisor on the Refuel Floor is responsible for the error and no action on your part is require j You should note the additional steps taken on the master refuel procedure in the Control Room and have the Refuel Floor Supervisor initial the Steps when he comes down from the Refuel Floo The mistake is considered a refueling error and refuel activities should be stopped until an evaluation of the event is complet Blade guides pose no reactivity concerns, therefore, incorrect placement of a blade guide is insignificant and no actions are required.

Answer: C l

I Question No.: 1-D.02-05-002 i Reference (s): D.02-05 (REACTOR AND CORE COMPONENTS HANDLING EQUIPMENT) K/A Reference: Generic Knowledge and Ability

Task Number: 2.2.30 i Rating RO/SRO: Monticello JTA: CR234.017 l Objective (s): M-8107L-019, EO-9 I/cmb

MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 120 of 126 l Exam Question Number: 96 Point Value: 1.00 Time (Minutes): NA l The HWC System affects several plant area radiation levels.

If HWC injection rate is increased, radiation levels will increase in the... Steam Chase and Turbine Operating Floo Condenser Hot Side and Air Ejector Roo Steam Chase and Recor.1biner Roo Condenser Hot Side and Recombiner Room.

Answer: A

Question No.: 1-B.02.06-012 I

Reference (s): B.02.06-05, Page 4 of 24 ! K/A Reference: Generic Knowledge and Ability Task Number: 2.3.10 Rating RO/SRO: 2.9 Monticello JTA: CR301.001 Objective (s): M-8107L-085, EO-4 t/cmb

MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY

Page 121 of 126 l Exam Question Number: 97 Point Value: 1.00 Time (Minutes): NA Given the following plant conditions:

. Reactor is manually scrammed due to an identified Reactor coolant lea . All rods are inserted to 0 Reactor levelis 35 inche . There is a Group 1 Isolation on high steam flo . The Low-Low Set system has faile .

Reactor pressure is being controlled by SRV safety actuatio . Drywell pressure is 1.7 psi . Drywell bulk average temperature is 145 degrees . West CRD ARM is in Alar . An Alert has been declared based on the Reactor coolant lea Which EOP procedures require entry based on the current plant conditions? C.5-1100 and C.5-1200 C.5-1200 and 0.5-1300 C.5-1100 and C.51300 C.5-1300 and C.51400 Answer: C I Question No.: 1-C.5-1000-068 ) Reference (s): C.5 EOPs K/A Reference: Generic Knowledge and Ability Task Number: 2. Rating RO/SRO: Monticello JTA: vR304.002, CR304.012 Objective (s): M-8114L-005, EO-4 1/cmb s

. .

. . MONTICELLO NUCLEAR GENERATING PLANT M81000 9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 122 of 126 l Exam Question Number: 98 Point Value: 1.00 Time (Minutes): NA Which of the following is a Reactor Coolant sample point used by the Post Accident Sampling System? ! Core Spray Discharge Lin Recirc Pump Casin I RHR Loop in shutdown Coolin j Drywell Equipment Drain Sum ! Answer: C Question No.: 1-B.05.18-001 Reference (s): B.05.18-01 K/A Reference: Generic Knowledges and Abilities Task Number: 2. Rating RO/SRO: 3.5/ Monticello JTA: CR999.006 Objective (s): M-8107L-023, EO-18 1/cmb

     .
 .

MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 124 of 126 l Exam Question Number: 99 Point Value: 1.00 Time (Minutes): NA Given the following plant conditions:

      )
* Reactor manually scrammed after a Group I isolatio !
-

Drywell pressure 8.5 psi * Torus temperature 125' * Reactor level -100 inche * Fuel damage has occurre I Which of the following Control Room instruments can be used to determine the severity of fuel failure? ] Control Room Radiation Monitor IRM or SRM indications Plant Area Radiation Monitors Containment Radiation Monitor Answer: D Question No.: 1-A.2-003 Reference (s): A.2-101, B.5.12-02 K/A Reference: Generic Knowledge and Ability Task Number: 2.4.21 Rating RO/SRO: j Monticello JTA: CR999.021

Objective (s): M'-8110L-014, EO-4, 8 I/cmb i

MONTICELLO Nl4: EAR GENERATING PLANT M81000-9923 TITLE: 1999 WRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 125 of 126 l l Exam Question Number: 100 Point Value: 1.00 Tme (Minutes): NA While in C.5-2007 (FAILURE TO SCRAM ) the following plant conditions were noted:

. Reactor power at 16% on APRM . IRMs are being inserte . MSIVs are Close . Control rods are being inserted using procedure C.5-310 .

The SBLC Tank drain has cracked and is spilling borated water on the floo * SBLC Tank is 3/4 full and decreasin . Torus temperature is 108' F and increasing.

Which of the following methods will effectively shutdown the Reactor in the above conditions? Goron injection with RWC . Boron injection with CR Shutdown both CRD pump Place RWCU system in dump flow mode.

__ Answer: A Question No.: 1-C.5-2000-014 Reference (s): C.5-2007 K/A Reference: Generic Knowledges and Abilities Task Number: 2.4.34 Rating RO/SRO: 3.8/ Monticello JTA: CR314.007, CR314.013 Objective (s): M-8114L-005, EO-6,7; M-8114L-011, EO-1 1/cmb _

PAGE 126 0F 126 1999 INITIAL NRC RO LICENSE EXAM ANSWER KEY Name: MASTER EXAMINATTON Date: AUGUST 23, 1999 1 C 21 B 41 D 61 D 81 D 2- D 22 C 42 B 62 B 82 B 3 D 23 B- 43 B 63 C 83 C 4 A' 24 A 44 D 64 B 84 D 5 A 25 8 45 A 65 A 85 B 6 B 26 C 46 D 66 C 86 B _ 7 C 27 B 47 D 67 C 87 B 8 D 28 8 48 B 68 B 88 A 9 A 29 B 49 B 69 C 89 D 10 B 30 D 50 C 70 D 90 B 11 D 31 A 51 B 71 C 91 C 12 B 32 A 52 D 72 A 92 C 13 A 33 C 53 C 73 C 93 A 14 A 34 C 54 B 74 A 94 B 15 D 35 B 55 D 75 D 95 C 16 C 36 D 56 A 76 B 96 A , 17 D 37 D 57 A 77 D 97 C 18 B 38 C 58 A 78 A 98 C 19 A 39 C 59 D 79 8 99 D 20 C 40 C 60 C- 80 A 100 A . . . . . . .

. . .. Monticello Nuclear Generating Plant August 1999 RO Exam l Student RO Exam Handouts

MONTICELLO NUCLEAR GENERATING PLANT Ops Man B.1.1-06.02 ' Revision 10 <- - Page 20 of 42 Figure 17 Core Flooding instruments CORE FLOODING INSTRUMENTS ACTUAL VERSUS INDICATED LEVEL for Selected P.eactor Ver:el Pressurer INSTRUMENT t_0 CATION INSTRUMENT LOCATION LIS-2-3-73A & B C121 & C122 LR-2-3-113 C03 LT-2-3-il2 A & B C121 & Cl22 LI-4108 C292 LI-2-3 91 A & B C03 LR-4102 C292 CAUTION: VALID ONLY WITH NO RECIRC FLOW 1000 PSIC 545'r

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i MONTICELLO NUCLEAR GENERATING PLANT Ops Man B.1.1-06.02 l Revision 10 j Page 21 of 42 .j - }. ] Figure 18 Feedwater Level Instruments

FEEDWATER LEVEL INSTRUMENTS ACTUAL VERSUS INDICATED LEVEL For Selected Reactor Vessel Pressures USE FOR INSTRUMENTS LOCATION LT-6-52A C55 LT-6-52B c56 LI-6-94 A, B C05 ELR-6-96 C05 1000 PSIG & 545 *r

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. MONTICELLO NUCLEAR GENERATING PLANT Ops Man B.1.1-06.02 Revision 10

..                Page 22 of 42
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Figure 19 Vessel Flooding Instruments VESSEL FLOODING INSTRUMENTS ACTUAL VERSUS INDICATED LEVEL FOR SELECTED REACTOR VESSEL PRESSURES USE FOR INSTRUMENTS LOCATION w w w w w 0 o o o o LI-2-3-86 C03 e s e e e 7.;

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. .         1 MONTICELLO NUCLEAR GENERATING PLANT    Ops Man B.1.1-06.02 Revision 10 Page 24 of 42
        !

Figure 21 Safeguards Water Level Instruments SAFEGUARDS WATER LEVEL INSTRUMENTS ACTUAL VERSUS INDICATED LEVEL For Selected Reactor Vessel Pressures IMTR

USE FOR INSTRUMENTS LO EUNCTION L15 2-3-657 C55 RPS LS 2-5-657C. D C55 MS ISOL & PRI CONT LIS 2-3-650A, B C56 RPS C LS 2-3-650 C56 MS ISCL & PRI CONT 3 a-LIS 2-3-672A C C55 ECCS LIS 2 ~j-672B, D C56 ECCS $ LS 2-3-672E C55 RCIC/HFCI HI TRIP d LS 2-3-672E C56 RCIC/HPCI HI TRIP W LI 2-3-85A C56 C05 LEVEL IND d LI 2-3-85B C55 C05 LEVEL IND g i l 1000 PstG L 545 Dev I ! O I/ 620 Psta L 492 Dec

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1000 1100 1200 1300 1400 1500 1600 1700 1800 1900 2000 Indicated Tank Volume (Gallons) M l Amendment No. 57 Figure 3.4-1 Sodium Pentaborate Solution Volume Concentration Requirements 97 9/23/88 2 r Amendment No. 57

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i:b , . . s'\N . . ., '". .~f: . . k., .J j\l\s \ :\ hj 8- 10 12 14' 16 18 20 Weight Percent Sodium Pentaborate in Solution w/o Na2 BioO1 s.H2O E Figure 3.4-2 Sodium Pentaborate Solution Temperature Requirements

98 12/11/87 j Amendment No. 56

L5

l A Y N Y L D E TP A L HM B A GE ET I Y U W B NG D E AN T MI A D E W = = = = = I L BO L A NL TR L) V A

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MONTICELLO NUCLEAR GENERATING PLANT Ops Man C.4-C Revision 15 Page 29 of 29 g , 1 Figure 2 Reactor Depressurization Rate

 '1200 1100 -

1000 - Operation

'
, $2 W hIs   U wed in O- 000
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A sn - ~

    - - - - - -

Time, Minutes l

e cs<iG2 C.4-C 1

'e C

< I/cmb . }}

v t e Inspection Report - Monticello - 1999301 (Operator Exams)
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 \|
1999 Quarterly Integrated 1Q (0) 2Q (0) 3Q (0) 4Q (0) Assessments Mid Cycle End of Cycle 10(0) 11(0) 12(0) Security Operator Exams 301(0) Emergency Planning Other

IR 05000263/1999301

Text

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