IR 05000369/1992301
| ML20127G633 | |
| Person / Time | |
|---|---|
| Site: | McGuire  |
| Issue date: | 01/11/1993 |
| From: | Ernstes M, Harris G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20127G629 | List: |
| References | |
| 50-369-92-301, NUDOCS 9301220020 | |
| Download: ML20127G633 (239) | |
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0 %,' UNITED STATES -
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_,,. NUCLEAR REGULATORY COMMISs10N o REGION 11 -
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ENCLOSURE-1 EXAMINATION REPORT - 50-369/92-301'
Facility Licensee: Duke Power Company Facility Name: McGuire Nuclear Station Facility Docket Nos.: 50-369 and 50-370 The NRC administered examinations at the McGuire Nuclear Station near Cornelius, North Carolin .
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l Chief Examiner: ~
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I44, ////[92 l arry arris D'at( Signed )
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, Approved By: #f2
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Michael E. Ernstes, Chief Date Signed Operator Licensing Section 2 Operations Branch Division of Reactor Safety l.-
SUMMARY Scope: Written examinations and operating: tests were administered to-_two__
Reactor Operator (RO) and seven_ Senior Reactor-Operator (SRO);
applicants during the week of December 7, 1992. In addition, requalification retake examinations were administered on-December 7,1992, to four 5R0s wha-failed the requalification examinations given during the weeks of June 22 and-June 29,-199 Results: - All candidates passed these examinations. Strengths were noted in plant cleanl_iness and housekeeping,-diagnosis of events, training-department cooperation, and improved use of annunciator response
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procedures. . ' Weaknesses. were identified in the following' area ~si- -
Emergency Operating Procedure (EOP) usage'(paragraph.4.b),.and E0P content.(paragraph 4.c).
-9301220020 930112
- . _ . _ - _ _ _ REPORT DETAILS Persons Contacted
- D, Baxter, Operations-Support Maaager
- B. Caldwell, Site Training Manager -
- Geddie, Station Manager
- Hamilton, Superintendent of Operations >
Lindsay, Operations Shift Coordinator
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- * Massie, Operations Coordinator
- McGinnis, Director, Operations 1 raining
- McMeekin, Site Vice President 1 2-, NRC Personnel
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- J. Bumgardner, PNL
- T. Cooper, Resident Inspector
+*G, Harris, Examiner, NRC
- N. Moffitt, PNL
- J. Moorman, Senior Examiner, NRC
- Attended Exit Interview
+ Chief Examiner
, Discussion Initial Written Examination All candidates passed the written examinations. The test scores ranged from 85 percent- to 94 percent for the initial examinatio ,
The written exam identified some weak knowledge areas. There wer .
two questions which were missed by the majority.of the candidates
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l For example, eight out of nine candidates incorrectly answered at t question that was designed to evaluate the plant response from i- control room indications resulting from a pressurizer vapor space Loss of Coolant _ Accident'(LOCA). This indicates a weakness-in the ability to diagnosis this type of LOCA based on control room -
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indications, in another example, a question required--the candidates.to. recognize
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actions required upon-the determination that:noth channels of the-Solid State Protection System-(SSPS) were inoperable.while in
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Mode 4. Four_of.seven SR0 candidates. failed to recognize that thel correct act_ ion was to enter Technical Specification 3.0.3, and decided to remain in MODE-4. This would be a direct violation of-Technical Specifications and indicates a lack of knowledge. of the safety significance of SSPS in-Mode . . _ , _ , _; . 2 _ .. -.
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' Report Details 2-b; Emergency Operating Procedure Usane During a scenario that involved a s:esmline break, the _ candidates displayed confusion over whether to transition to_an Orange Path if the challenge no longer remained when exiting procedure EP/1/5000/0 Reactor Trip or Safety Iniectio _
The candidates transitioned to the Functional Restoration Procedure (FRP) as directed by the Orange Path even though the orange path was no longer present when they exited EP/1/5000/01. Station administrative procedures instruct operators to implement the FRPs only if conditions requiring the implementation are still present when exiting EP/01, Reactor Trip or Safety injection. Transitioning to the Orange Path caused significant delays in entering the procedure designed'to mitigate the even During the simulator examinations SR0 candidates read the fold-out page of an E0P in detail prior to implementing the procedure, causing significant delays in the implementation of the transient mitigating strategy. The licensee agreed that the length of time spent by the
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SR0s reading the fold-out page was unacceptabl The stathn further stated that it was devising methods to streamline the proces During a requalification scenario, the operator was instructed to refer to EP/1/A/5000/06, Loss of Emergency Coolant Recirculatio Although there was no sump level indication or other condition that would warrant a transition, the operator exercised poor judgement and made a complete transition to the procedure. This transition extensively delayed the implementation of the accident mitigating procedure, in another scenario, operators exercised poor judgement and transitioned to EP\lA\5000\l.2, SI Termination,-following a spurious
- _ SI which required them to terminate safety injection flow, although control room indications suggested that a loss of coolant accident, caused by a stuck open safety, had worsened. This caused a considerable delay in entering the high energy line break accident mitigation procedur c. Emergency Operating Procedure Content The-action steps-of the McGuire Emergency Operating-Procedures are written and ordered such that if they are not expeditiously
implemented, plant conditions can degrade unnecessarily. This degradation can be prevented if operators take' manual control nf som plant systems. ' Crews did not take manual control of plant systems, such as main =or emergency feedwater, to compensate when it appeared that plant conditions were degrading. McGuire station procedures
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require the operators not to manipulate-controls of systems during the implementation of E0Ps unless the E0P requires it.
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Report Details 3 for example, during a steam generator tube rupture feedwater was not terminated to the ruptured generator until it was ai ast completely fille In another example, auxiliary feedwater was not terminated to a faulted generator, causing an excessive vessel cooldown. The licensee has identified these deficiencies and will incorporate them into its E0P upgrade effor Communications Operators were frequently heard to use imprecise terms to communi-cate important informatio In addition, SRO candidates infrequently used crew summaries to communicate plant status, mitigation strategy and other vital informatio Specific Knowledge Weaknesses During a scenario, a safety injection (SI) was actuated with pressurizer level above 17 percent. The A and B pressurizer heaters were de-energized due to the SI, and C and D were still energized due to low primary plant pressure. The fact that the heaters were de-energized confused the candidates. They believed there was a problem with the heaters. The candidates were unaware of the fact -
that, in addition to low pressurizer level, the heaters would de-energize on a safety injectio The simulator instructors confirmed that the candidates had not been taught about the safety injection / heater arrangemen Administrative Task Implementation It was observed that two SR0 instant candidates had diffi ulty in performing some of the administrative duties required of licensed SR0 The candidates were requested to discuss several administrative topics normally performed by an SR0 that included tagout, shift turnover sheets, rad release, and Technical Specification Limiting Condition for Operation (LCO) status boe Consistently the candidates were aware of the forms / activities but could not discuss the process for implementation which included the flow path for conducting the activity, the areas requiring review during the SRO supervisory review process, the routing of required administrative forms following approval, and the responsibilities between the various departments when conducting the work activit SRO candidates must be able to adequately perform the administrative ta<ks required of the licensed position, per station directive Job Performance Measure (JPM) Administration JPM-EP-AP 108, Manual Closure of Main Steam Isolation Valves, tests the operators' ability to perform Enclosure 3 of AP/1/A/5500/17, Loss of Control Roo This JPM required operators to close valves
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. . . , _ . . . . . _ . _ . . . _ . _ . Report Details 4 IVI-830 and IV1-831. The valves are located in the overhead area of a darkened room and were not easily accessible, The implementation-of_this task could be hazardous to personcel safety and/or take an excessive amount of time to complete. The licensee' agreed to evaluate the conditions under which this task would be performe . E0P Upgrade Effort The station's.EOP procedure upgrade effort thus far has been focused on clearing a backlog of 600-700 procedural discrepancies. In addition, the McGuire procedure group has completed drafts of three-Emergency Operating -
Procedures. Catawba has completed eleven drafts. McGuire's full E0P implementation effort is scheduled to begin January 4,1993, with all drafts scheduled to be completed by June 199 McGuire has-dedicated five people to this effort from operations, training, and operations support, Catawba and McGuire have met eight separate times since the July regional
). meeting to ensure continuity in the process. The licensee is confident that this schedule can be me . Plant Material Condition A termination-box near the 1A Motor Driven Feedwater pump was missing a screw that might threaten its environmental qualificatio The 1A Motor Driven Feedwater pump was- observed to have an noticeable oil lea The licensee stated that these discrepancies would be investigate . Requal Examination Administration The proposed written and simulator examinations were effective in-testing -
the individual weak areas identified on the previous requalification examtaations. The critical tasks on the proposed simulator examinations
= met all established criteria and did not have to be modified.- Nine -
questions on the Part A and six questions on-the Part B examination were changed in order to make the distractors more plausible. Operator performance weaknesses were documented in previous sections of this report. No program evaluation was conducted due to the small sample siz < Exit Meeting'
At the conclusion of the site visit,-the examiners met with representatives of the plant staff, indicated in paragraph 1 above, to discuss the results of the examinations and inspection findings. The i-licensee did not identify as proprietary, any material provideda to or reviewed by the examiners. The examiners further described the areas-inspected and discussed in detail the inspection finding .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ . - _ _ _ _ .
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ENCLOSURE 2 SIMULATOR FIDELITY REPORT Facility Licensee: Duke Power Compary Facility Docket Nos.: 50-369 and 50 370 Operating Tests Administered On: December 7 - 12, 1992-This form is to be used only to report observations. These observations, in and of themselves, do not constitute audit or inspection findings and are not, without further verification and review, indicative of non-compliance with 10 ,
CFR 55.45(b). These observations do not affect NRC tertification or approval i of the simulation facility other than to provide information which may be used in future evaluations. No licensee action is required solely in response to these observation J1e_m Comment Pressurizer Pressure During a scenario, pressurizer level only increased 6 percent, but the pressure increase was substantial.
l- Loss of Instrument Air (VI) A scenario.was devised-that caused the plant to.have a substantial loss of _ instrument ai Although the plants' instrument air pressure had
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decreased to 40 lbs., the feed regulation' valves l- remained open and could be manipulated.
p Loss'of-Suction to A scenario required _that the suction valves-Centrifugal Charging would not shift from the volume control tank-to-Pumps (NV) the fuel water storaga tank when required,:
causing cavitation of the NV pumps. The pumps-did not experience _ cavitation for-nearly-two minutes following this lost of sectio .
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- Operator Aide Computer (OAC) During the performance of a Diesel Generator . .
L Operability Test JPM the candidate was remired i L to close the diesel generator output bre .
Although the candidate had closed the~reaner o on ,
i-the board, the OAC indicated that thel breaker was D ,till open, l, +w-,. vvw- w +- r -W M w-
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SITE SPECIFIC EXAMINATION SENIOR OPERATOR LICENSE REGION--2 CANDIDATE'S NAME:-
FACILITY: McGuire-1-& 2 REACTOR TYPE: PWR-WEC4 DATE ADMINISTERED: 92/12/07 ,
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INSTRUCTIONS TO CANDIDATE:
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Use-the answer sheets provided to document your answers. Staple this cover .
' sheet on top of the answer sheets. Points for.each question are-indicated in
--parentheses after the questio The passing grade requires a final grade of at least 80%. Examination papers will be picked up four- (4)- hours af ter the -
examination start CANDIDATE'S TEST VALUE SCORE %
100.00 % TOTALS FINAL ~ GRADE-All work done on this examination is my ow I have neither given nor-received ai Candidate's-Signature
= DRAFT COPY
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fC SENIOR:. REACTOR OPERATOR Page -
' QUESTION: 001 (1.00)
Given the following conditions:
- Unit 1 is operating at 100% power-when a transient. occur Nuclear Instrumentation power range indication is:
Channel 1-- 102% Channel 3 - 105%
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Channel 2 - 101% Channel 4 - 102%
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Assume all trip setpoint penalties and credits are as is expected for 100% power, WHICH ONE (1) of the fol30 wing is the actuation that will occur as a result of the above conditions? NI overpower rod stop NI overpower reactor trip OP Delta T runback OP Delta T reactor trip ANSWER: 001 (1.00) [+1.0)
REFERENCE: LP OP-MC-IC-IPE, pp. 17-18, Objectives 1 G & . LP OP-MC-IC-ENB, pg. 38, Objective 12 KA 001000K407 (3.7/3.8)
001000K407 ..(KA's)'
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-SENIOR REACTOR OPERATOR .3
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QUESTION: 002 (1.00)
Given the following conditions:
Unit--i-is-at 80%-powe Control' Bank D-is at 200 step Power Mismatch is -1-degree *
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Temperature Mismatch ir -1 degree Rod Control is in AUT .
=WHICH ONE (1) of the following statements describes the response-'of'the rod-control system to these conditions? -
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a. The control rods step in at 40 steps per-minut b. The control rods step out at 40 steps per minut c. The control rods step out at 8 steps per minut d. The control rods step in at 8 steps per minut ':
ANSWER: 002 (1.00)
' [+1.0)
REFERENCE:
- LP OP-MC-IC-IRX, p. 23, Objectives 3G, 3H, 3 ~
- 2. - KA 001000K402 (3. 8/3. 8 )
001000K402 ..(KA's)
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SENIOR- REACTVR OPERATOR Page QUESTION: 003 (1.00)
Given the following' conditions:
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-A plant heat-up is in progres NCS temperature increased from 190 degrees F to 196 degrees F in ten minute WHICH ONE (1) of the following actions will result in the administrative MAXIMUM allowable NCS heat up rate (HUR)? Increase HUR by 64 degrees F/h Decrease HUR by 26 degrees F/h Increase HUR by 14 degrees F/h Decrease HUR by 10 degrees F/h +
ANSWER: 003 (1.00) [+1.0)
REFERENCE: LP OP-MC-PS-NC, p. 38, Objective-14, KA 002000A103 (3.7/3.8)
002000A103 ..(KA's)
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Page 5 QUESTION:-004 (1.00)
Given the following ccnditions:
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Unit-1 is in MODE 2 at 3% powe Tavg indication is 539. degrees WHICH ONE (1) of-the following is the MINIMUM action necessary to comply with Technical Specification 3.1.1.4, ' Minimum Temperature For Criticality"? Restore Tavg to GREATER THAN 557 degrees within~15 minutes or be in HOT STANDBY within the next 15 minute . Restore Tavg to GREATER THAN 551 degrees within 15 minutes or be in HOT STANDBY within the next 15 minute Restore Tavg to GREATER THAN 557 degrees within 15 minutes or be in HOT-STANDBY within the next 30 minute Restore Tavg to GREATER THAN 551-degrees within 15 minutes 1 or be in HOT STANDBY within the next 30 minute i
=. ANSWER: 004 (1.00) [+1.0]
. REFERENCE:
1. .LP OP-MC-PS-NC, Objectives 11--& 1 Technical-Specifications 3.1.1.4, pg. 3/4 1-6, 3. KA 002000G005 (3.6/4.1)
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SENIOR REACTOR OPERATOR -
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IQUESTION: 005 (1.00)
-WHICH ONE (1) of the following is-the reason-that all-the NCP breakers open on underfrequency? To' protect the_NCP anti-rotation: device from damage due to abnormal-coastdown, To preserve the NCP flywheel kinetic energ To avoid water hammer transients in the NCS induced 1by rapid NCP-speed' change, To reduce the probability of a stress induced NCP sheared shaft -
acciden ANSWER: 005 (1.00) [+1.0]
REFERENCE: LP OP-MC-IC-IPE,-p. 14, Objective 1 . KA 003000C007 (3.2/3.3)
003000G007 ..(KA's)
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QUESTION: 006 - (1.00)
Given the following condition NCP 1B #1 seal leakoff tempcrature is 215 degrees NCP Seal Return Bypass Header Isolation-(1NV-92A)- is CLOSE WHICH ONE (1) of the following conditions would PREVENT 1NV-92A from being.
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opened, according to OP/1/A/6150/02A " Reactor Coolant Pump Operation", Limits -
and Precautions?
I l NCS pressure is at 400 psi j No. 1 seal leakoff valve is ope No. 1 seal leakoff is 1.5 GP l Seal injection flow to each NCP is 7 GP l ANSWER: 006 (1.00) ( +1. 0]
REFERENCE: LP OP-MC-PS-NCP, p. 31, Objective 1 . KA 003000A201 (3.5/3.9)
003000A201 ..(KA's)
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SENIOR-REACTOR OPERNTO Page '8
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j ; QUESTION: 007 (1.00).
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WHICH ONE - (1) of the;following is tut f.tason-why the Chemical and Volume
. Control System.(NV) auxiliaryfspray should Zie' he used if-letdown is isolated??
- It is incapable of equalizing pressurizer and'NCS. boron-concentration The spray line cannot provide enough flow to control pressurizer pressure, There is no preheating and spray nozzle may be thermally shocke _ It causes excessive vibration in the spray lin . ANSWER: 007 (1.00) [ +1. 0 )
REFERENCE: LP OP-MC-PS-NV, p. 52, Objective . KA 004000K509 (3.7/4.2)
004000K509 ..(KA's)
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QUESTION: 008 (1.00)' '
Given the following~ conditions:
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Unit 1 isfat 80% p6we All control: systems.are in their_ normal operating alignment.
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WHICH ONE (1) of the following leaks could result in a DILUTION of the'NCS?- Regenerative _ Heat Exchanger _ leak Letdown Heat Exchanger-leak
~ ' Reactor Coolant Drain Tank-Heat Exchanger leak-
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d.- Seal' Water Heat Exchanger leak
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SENIOR REACTOR iOPERATOR .Page-- 9 5 ANSWER: -008- (1.00)-
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-REFERENCE:
1.: LP OP-MC-PS-NV, Objective . . McGuire Simulator Malfunction NV-24, NCP Seal Water Heat Exchanger Tube; Lea . KA 004000K118 (2.9/3.2)
004000K118 ..(KA's)
QUESTION:- 009 (1.00)
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WHICH'ONE (1)'of the following conditions must beimet to open ND 2Af(NC loop-
"C" to ND isolation)? ND-1B (Train B suction from C NC loop): open, NI-185A (Containment sump suction) close NI-136B (NI suction from ND) closed, FW27A (ND suction from Refueling Storage Tank)-ope ANSWER: -009 (1.00) (+1.0)
REFERENCE:
1. LP OP-MC-PS-ND, p. 20, Objective I
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2. KA 005000K407 :(3.2/3.5)
-005000K407 ..(KA's)
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vl ISENIOR REACTOR OPERhTOR PageJ10;
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- QUESTION
- -010 L(1.00)
'WHICH ONE (1) of the following parameters.would require declaring a coldt: leg-accumulator INOPERABLE?-
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. [+1.0)
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REFERENCE: , LP OP MC-ECC CLA, p, 13, Objective _7 . Technical Specification 3.5.1, p.'3/4 5- . KA 006000G005 (3.5/4.2)
006000G005 ..(KA's)
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QUESTION: 011 (1.00)
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WHICH ONE (1) of the following components discharges _to the'_ Pressurizer-Relief:
Tank (PRT)?
a '. Positive displacement pump diacharge-relief valv . NC to ND suction relief valv Relief valve (NV-156) downstream of letdown pressure control valve, d. LVCT relief' valv I m
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t ANSWER: 011 (1.00) (+1.0)
R1'FERENCE: LP OP-MC-PS NV, p. 31, Objectives 2 & . KA 007000K103 (3.0/3.2)
007000K103 ..(KA's)
-QUESTION: 012 (1.00)
WHICH ONE (1) of the following statements describes a trip directly associated-with the P 8 permissive? Undervoltage - NCP Busse Pressurizer high pressure tri Uvo loop loss of flow trip.
' Turbine trip.
L ANSWER: 012 (1.00)
- (+1.01-REFERENCE: LP OP-MC IC-IPE, p. 22, Objective 3 . KA-012000K406 (3.2/3.5)
012000K406 ..(KA's)
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SENIOR REACTOR OPERATOR Page 12 QUESTION: 013 (1.00)
WHICH ONE (1) of the following describes how the reactor trip breaker trip coils are affected by a MANUAL reactor trip?
a. UV coils and shunt coils are all de energize b. UV coils are de-energized, the shunt coils are energize c. Only the UV colla are de-energized, the shunt coils are unaffecte d. Only the Shunt coils are energized, the UV coils are unaffecte .
ANSWER: 013 (1.00)
b, [+1.0)
REFERENCE:
' LP OP-MC-IC-IPE, p. 13, Objective 1 . KA 012000K603 (3.1/3.5)
012000K603 ..(KA's)
QUESTION: 014 (1.00)
WHICH ONE (1) of the following will result in a Main Steam Isolation? ASSUME all control switches are in their normal position for operation, Containment pressure equal to 3.0 psig on 1/4 detectors, Pressurizer pressure equal to 1840 psig on 3/4 detector "A" Steamline pressure equal to 575 psig on 2/3 detectors and pressurizer pressure equal to 1970 psig, Tave equal to 545 degrees F and reactor trip breakers ope p ..
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SENIOR REACTOR OPERATOR Pago 13 AMSWER: 014 (1.00) [+1.0]
REFERENCE:
- 1. OP-MC-ECCS-ISE, p. 19, Objective 1 . KA 013000K403 (3.9/4.4)
013000K403 ..(KA's)
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QUESTION: 015 (1.00)
WHICH ONE (1) of the following use P-4 as an input to initiate an ESF actuation signal? Feedwater isolatio Steamline isolatio Auxiliary Feedwater actuatio Containment Spray. actuatio ANSWER: 015 (1.00) [+1.0)
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REFERENCE:-
El . LP OP-MC-ECC-ISE, p. 20, Objective 1 (3.7/3.9)
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- KA 013000A301
'013000A301 ..(KA's)
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SENIOR REACTOR OPERATOR Page 14
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QUESTION: 016 (1.00)
Given the following conditions:
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Unit 1 is in MODE It has been determined'that BOTH SI trains automatic actuation t logic and actuation relays did NOT meet the surveillance acceptance criteria for the test previously conducted in MODE 5- but the ,
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manual initiations passed the surveillance WHICH ONE (1) of the following actions should be taken?
. Stay in MODE 4 and do NOT allow transition to MODE Continue with the plant startup, no restraints appl '
' Enter and comply with Technical Specification 3. Within i hour verify the actuation relays are in the r;;guired state for the existing plant conditio ANSWER: 016 (1.00) (+1.0]
, REFERENCE: .
.1. LP OP-MC-ECC-ISE, p. 5, Objective 3 . Technical Specifications, p. 3/4 3-16, 2 .3. . KA 013000G005 (3.6/4.2)
013000G005 ..(KA's)
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QUESTION: 017 (1 00)
WHICil ONE (1) of the following actions is used to determine the position of the non-indicating rod upon declaring a single DRPI INOPERABLE in Bank D per Technical Specification 3.1.3.2, " Reactivity Control System"? Use incore detectors to perform a flux map of the core, Perform current measurement of coils on CRDM Use incore system with a magnetic proximity probe attachment to detect the rod tip positio _ Monitor and analyze QPTR chang ANSWER: 017 (1.00) [+1.01 REFERENCE:
1. LP OP MC IC-EDA, Objective .' Technical Specifications 3.1.3.2, p. 3/4 1-1 . KA 014000A206 (2.6/3.0)
014000A206 ..(KA's)
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'iE&R REAU1Yr OPERATOR Page 16 .
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'.i- ' ~ R ' 'd ' ,4 : 018 (1.00) l
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i Given the following conditions: l
- Unit 1 is at 100% powe .
- The Digital Rod Position Indicating System (DRPI) has experienced a !
failure of the "A" Data Cabinet, i WHICll ONE (1) of the following is-the accuracy of a lit rod position LED for these conditions? +10 to -4 steps to -10 steps
! +10 to -10 steps +4 to -4 steps -'
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ANSWER: 018 (1.00) [+1.0)
. REFERENCE:
, LP OP-MC-IC-EDA, p. 15, Objective 5 . KA 014000A102 (3.2/3.6)
014000A102 ..(KA's)
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. _ . - . _ _ _ _
SENIOR REACTOR OPERATOR Page 17 QUESTION: 019 (1.00)
WHICH ONE (1) of the following describes the result of OVERCOMPENSATION of the Intermediate Range Nuclear Instrumentation Detectors? The source range nuclear instruments will automatically energize at a higher power level than narma Permissive P-6 will not automatically doenergize on a reactor shutdow The Hi Flux at Shutdown alarm will be automatically blocke Permissive P-10 will not automatically deenergize on a reactor shutdown.
ANSWER: 019 (1.00) [+1.0)
REFERENCE:
1. OP-MC-IC ENB, pp. 14-15, Objectives 6 . KA 015000A303 (3.9/3.9)
015000A303 ..(KA's)
5 c
-. . - . - - ,.........-.-._-.- - , _ . . .. . - _ _ .
,
SENIOR REACTOR OPERATOR Page 18 QUESTION: 020 (1.00)
Given the following conditions:
-
Unit 1 is in MODE 6, refueling is in progres Scaler Timer drawer is in MANUAL mod WHICH ONE (1) of the following will occur if the nuclear instrumentation Audio Count Rate and Scaler Timer Drawer Reset Pushbutton is pushed? The display is reset and the gate is armed so the next pulse starts the count, The display, (decades counter or clock time base) are reset, The instrument is reset and operation is stopped until the start pushbutton is depressed in ANY MOD The audible count rate pulses are reset to a discernable rate.
ANSWER: 020 (1.00) [+1.0)
REFERENCE: LP OP-MC-IC-ENB, p. 35, Objective . KA 015000A301 (3.8/3.8)
015000A301 ..(KA's)
e
.
SENIOR REACTOR OPERATVR Page 19 QUESTION: 021 (1.00)
Given the following conditions:
-
Unit 2 is operating at 90% powe Steam generator water level control is in AUT A significant leak develops on reference leg of the controlling S/G water level instrumen NO operator action is take WHICH ONE (1) of the following describes the plant response? Feed regulating valve will modulate in the closed directio Steam flow will increase on the affected steam generator, Actual steam generator level will equalize at some value higher than original, Indicated steam generator level will decrease on the affected channe ANSWER: 021 (1.00) [+1.0)
REFERENCE:
_ LP OP-MC-CF-IFE, p. 16, Objective 1 . KA 016000G007 (3.1/3.1) Note: Failure removes high pressure reference side of transmitte Results in indicated level reading hig G007 ..(KA's)
_ .. .. .
,
?
SENIOR REACTOR OPERATOR Page 20 QUESTION: 022 (1.00)
WHICH ONE (1) of the following is NOT an input used by-the Train "A" Subcooling Margin Monitor?
' Wide Range Loop Pressure Phase B contact l Core Exit Thermocouple Temperatures ; Wide Range Hot Leg Temperature
..i ANSWER: 022 (1.00) (+1.0)
-i REFERENCE: .
' LP OP-MC-IC-ICM, p. 25, Objective ' KA'017000K401 (3.4/3.7)-
017020K401 . . ( KA' s ). ,
QUESTION: 023 (1.00) ,
WHICH ONE (1) of the following Containment Ventilation systemsEWill restart-following a LOCA? Lower Containment Ventilation- (VL) System, Upper Containment Ventilation (VU)_ Syste Containment Purge (VP) Syste , Pipe. Tunnel Boost'er Fan (PT) Syste b
._
ANSWER: - 023 (1 00)
- a . -- [ + 1. 0)-
<
~
+w ,r v v w,. w-~.- ,~-<,-v,r ,,,-+,nn,r,;,v m..,w~,... ,<w- n,, cn e r .nn-,, ,.n-,+~~--n u -ns -- - -a,n.u.-- .--~..+,.n-.~.---,-.-
__ _ - - - - - - - - - - __ _ - - _ _ _ _ - - - - - - - - - - _ - - - - - - - - - - - - _ _ _ _ _ _ _ . _ - - . _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ - . _ _ _ _ _ _ _ _ . _ _ _
,
t
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l SENIOR REACTOR OPERATOR '
Page 21 I i
!
REFERENCE: -l 1.-LP- OP MC-CNT-VUL, p. 16, Objectives ;
2. KA 022000A301 ( 4 .1/4'. 3 )
022000A301 ..(KA's)
!
!
QUESTION: 024 (1.00)
WHICH ONE (1) of the following is the reason for adding sodium tetraborate l to the Ice Condenser System? It facilitates converting soluble iodine into insoluble iodine'.
- It scrubs non-condensible gases from the containment atmosphere.- It minimizes the amount of hydrogen generated during a LOC It increasesi the pH of the sump to facilitate iodine remova '
.!
ANSWER: 024 (1.00)
. [+1.0)
-REFERENCE: LP OP-MC-CNT-NF, p. 28, Objective 1C & . KA 0025000G007 025C00G007 ..(KA's)
t
-. , _ _ _ . . . . _ . . - . _ __ _ . _ _. . .._ _ _--__,_ . _ _ _.. _ ..~._.. . _ _. . _
_ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ - _ _ _ _ _ _
SEN!;OR REACTOR OPERA 10R Page 22 [
.I
QUESTION: 025 (1.00)
WHICH ONE (1) of the following is the MAXIMUM hydrogen concentration expected t inside containment assuming the hydrogen recombiners are placed in service and ,
function as designed following a LOCA? - Less than 0.5% !
! Less than 1% _;
! Less than 4% ! Less than 6%
ANSWER: 025 (1.00) [+1.0) ;
REFERENCE: LP OP-MC-CNT-VX, p. 15, Objective . KA 028000K501 (3.4/3.9)
028000K501 ..(KA's)
QUESTION: 026 (1.00) -
-WHICH ONE (1) of the following is the plant _ condition that can result;from
. inadvertent operation of the Containment Air Return _Wans? The ice condenser ' inlet doors may open and' cause containment:
pressure to fall below allowable limit : The fans will _ overpressurize the . ice- condenser aisd prevent the-inlet. doors from opening as designed.-
- It will reposition the' discharge dampers and cause reverse air flows through the ice condenser, d- ItLwill equalize pressure'between lower containment and deadLend-spaces and_ prevent FSAR flow requirements from beingime . .- . - , - - - . - _ - . . - . x. . . -, _. - . - . . . - - - - - ;c , - . . _ -
..,
SENIOR REACTOR OPERATO Page 23 ANSWER:. 026- (1.00) (+1.0)
REFERENCE: LP OP-MC-CNT-VX, p. 22, Objective 1 . KA 028000G010 (3.0/3.2)
028000G010 ..(KA's)
_
QUESTION: 027 (1.00)
WHICH ONE (1) of the following is the GREATEST contributor of hydrogen following a LOCA in which the core is uncovered? Radiolysis of water, Corrosion of stainless steel, Zirconium / water reactio Hydrogen coming out of solution in the NC ANSWER: 027 (1.00) (+1.0)
. REFERENCE: LP OP-MC-TA-AM,-pp. 47-48, Objective 6 . KA 028000K503 (2.9/3.6)
'028000K503 ..(KA's)
l l
.. .
_ - _ _ - -
_ _ .
SENIOR REACTOR OPERATOR Page 24 QUESTION: 028 (1.00)
Given the following conditions:
- A refueling outage has been complete The reactor missile shield has NOT been set in plac WHICH ONE (1) of the following is the reason for ensuring that the Purge Mode Selector Switch is returned to the NORMAL position when aligning the purge system, according to OP/1/A/6450/15, " Containment Purge System", Limits and Precautions? To prevent overpressurization of the upper containmen To ensure that any purge is routed through the cleanup filters, To prevent isolation of the containment purge supply fans, To ensure the system actuates on high containment pressur _ _
ANSWER: 028 (1.00) [+1.0)
@
REFERENCE: LP OP-MC-CNT-VP, p. 17, Objective . OP/1/A/6450/15 " Containment Purge System" KA 029000A103 (3.0/3.3)
029000A103 ..(KA's)
_ . . . . . .. .
. _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ - _
'
SENIOR REACTOR OPERATOR ~ Page 25 QUESTION: 029 (1.00)
Wi!ICH ONE (1) of the following is the reason for the precaution in OP/0/A/6550/02 " Inspection and Storage of RCCA", to NOT operate the 125 ton Overhead Fuel Handling Crane Hoist at anything less than the fastest speed for more than 15 seconds when the selector switch is in the FAST position?. _,
' It will increase the amount of time it takes to complete refueling.
-
I It will cause binding of the hoist cabl It will misposicion the attached load and interfere with t ravel crane movemen It will overheat the hois ,
ANSWER: 029 (1.00) [+1.0]
REFERENCE:
' OP-MC-FH-FC, p. 54, Objective 13,
' KA 034000G010 (2.7/2.9)-
034000G010' ..(KA's)
i
.,
i
-w.--rk4- --w+r,wr,--w=,-,- .--=,---.--,---e--,-.-,v---,,,.-r wr m,.-i..r--+a +----ww-s--n-n=~.--ww-vw---%.,,.a vv,.--.-3,w...e4,.,w-,.m .,w,r ew . , , - , , - w .yr 5,- -- - 1,
._
SENIOR REACTOR OPERATOR Page 26 QUESTION: 030 (1.00)
Given the following :onditions:
- Unit 1 is operating at 100% powe SG "D" wide range level instrument fails LO WHICH ONE (1) of the following is affected by this failure? SG "D" level trip setpoin SG "D" narrow range level instruments, SG "D" level control signa SG loop "A" and "D" three pen chart recorde ~ ANSWER: 030 (1.00) [+1.0)
REFERENCE: LP OP-MC-STM-SG, p. 15, LP OP-MC-CF-IFE, Objective . KA 035010A101 (3.6/3.8)
035010A101 ..(KA's)
.
e
- v
.- .
SENIOR REACTOR OPERATOR Page 27 QUESTION: 031 (1.00)
Given the following conditions:
-
The reactor tripped from 100% powe "B" Reactor trip breaker is OPE "A" Reactor trip breaker is CLOSE Steam Dumps are in the.Tave Mod WHICH ONE (1) of the following demonstrates the status of the Steam Dumps as a result of this transient? Steam dump banks 1 & 2 are armed by C-7B interloc Steam dump banks 3 & 4 are armed by C-7A interloc > Steam dump banks 1 & 2 will modulate to bring Tave to Tnoload, Steam dump banks 3 & 4cwill modulate to bring Tave to Tnoloa ,
ANSWER: 031 (1.00) [+1.0)
r REFERENCE: LP OP-MC-STM-IDE, p. 31, Objective 1 ' KA 041020K417 (3.7/3.9)
041020K417' ..(KA's) t L
QUESTION: 032 (1.00)
WHICH ONE_(1) of the following will-cause-the1 Interface Valve-of-the-Main
. Turbine EH Control System to open causing a turbine _ trip? 3 Fluid Operated Air Pilot (FOAP) Valve.goes close ; Auto Stop Oil (ASO) pressure is at 50 psi r 1: - Mechanical Turbine Overspeed actuatio , Electrical Trip Solenoid 20ET energize ,
e w e's, N re ,- a --en- u,,- ,,v r e ,
,
'i
>
SENIOR REACTOR OPERATOR Page 28 :
'l JANSWER: 032 (1.00)- f [+1.0) !
!
!
-REFERENCE:
- LP OP-MC MT-MT, pp. 14-15, Objective 2 . LP OP-MC-GEN-EHC, pp. 10-14, Drawings EHC 5 & : KA 045000K411 (3.6/3.9) ;
,
I 045000K411 . . (KA's)
i
!
-QUESTION: 033 (1.00) j Given the following conditions:
-
Unit 1-is operating at-100%-powe . '
-
Both Main Feedwater (CF) pump turbines are equally loaded.~
-
A difference of l-inch vacuum is observed between pump :
!
LWHICH-ONE (1) of the following is a possible. reason for the observed i difference? With both pumps equally loaded they are fighting each other for =
~ Control.- ' Flow from the Condenser Circulating Water system . (RC) is unequal j through each FWPT condense The CF Recirculation' Valve closure circuit'has actuated.- t Condensate has accumulated in-the steam supply lines to the CF pump -
turbine !
i
, ANSWER: 033- (1.00) ,
, [+1.0]
l t
'
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l
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! ,
,
t v vW- + v -*m *rvw- T-w'-e=*.- w - ++v r'~n- - ,- -=.w-- e v-'=-e+ '
*+m-'- * * *v -9-*"- ' * = v~h -*-+--*Jd=-~w-
-
'
_ _ _ - _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ __ . _ _ _ _ _ _ _ - _ _ _ _ - _ _ _ _ _ _ _ _ - _ _ _ _ _ _ - _ _ - _ _ _ _ . _ _ _ _ _ - _ _ _ _ _
i, l
SENIOR REACTOR OPERATOR Page 29 !
,
i REFERENCE: l OP/1/A/6250/01,-Condensate and Feedwater System, p. 2,-Limitations and'
Precaution .. LP OP-MC CF-CM, Objective i KA 059000G010 (2.9/2.9)
!
0590000010 ..(KA'a)
i i
QUESTION: 034 (1.00) f Given the following conditions: }
- Unit 1 is in MODE 3 with all plant systems in their normal lineu Auxiliary transformers IATA and 1ATB are NOT in synchronization !
'
when a fault in the protective zone of 1ATA. occur WHICH ONE (1) of the following describes the transfer of power for the 7 KV buses? : An automatic rapid-transfer from 1ATA to 1ATB=will-occur; and, when the fault on 1ATA clears, an automatic rapid transfer back to 1ATA will occu An automatic rapid transfer from 1ATA to 1ATB will occur; i but, when the fault clears, no automatic transfer back to ,
IATA will occur, An automatic slow transfer from 1ATA to 1ATB will" occur;-
and, when the fault on.1ATA clears, an automatic slow transfer back'to 1ATA will occu An automatic slow transfer from'1ATA to 1ATB will occur;-
but, when the fault clears,_no automatic transfer back to 1ATA vill occur.
ANSWER: 034 (1.00) (+1.0)
.
t
?
'- ~ . .- >- ,~., -.., _ ... --._,-..--_-,, - - s - - ,.-----... - - ,,.- - ,..-_.:--, _ ~ m .- -......-.
._ -_ _ _ _ _ _ _ - . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ . . _ _ _ . _ - _ _ _ _ -_ _ _ _ . __ _ - _ _ _ _ _ _ _ _ _ _ _ - _ - _ -_ _ _ _ - _ _ _ . ____ _ _ _ _ _ _ - _ _ _ _
s
!
SENIOR P.EAC.iJa OPERATOR Page 3 l
REFERENCE:
, LP OP-MC-EL-EP, p. 25, Objectives 21 & 2 j '4A 062000A401 (3.3/3.1) ;
r
'
062000A401 ,.(KA's)
L QUEST 1cNs 035 (1.00)
WHICH ONC (1) of the following is a load on 120VAC bus 1EKVD? I
' SSPS Qin201 TJI Train B Train B isolation valves i Safeguards System Test Train A ;
. Train A Containment Air Release valves .
.
ANSWER:- 035 (1.00) , (+1.0)
,
REFERENCE: Drawing MC-1705-01, "125VDC/120VAC Vital Instr. & "ontrol Power System"= LP OP-MC-EL-EPL, Objective 15, KA 062000K201 ;3.3/3.4)
i 062000K201 ..(KA's) :
>
.
f P
t f
' . - _ . . , , . _ _ - , . . . - , . . . . . , , , _ . , _ _ . _ _ . _ , . - , . . . . . . , , . _ . . . . . . _ . , . . , . . _ _ _ _ . . _ _ , . . _ . _ . . . . _ . . . . . - . , . - . _
.
.
__ _ _ _
!
r SENIOR REACTOR OPERATOR Page 31 ;
i
- e 1 QUESTION: 036 (1.00)
-
Given the following conditions: ,
j
-
The reactor has tripped from 100% powe '
- A safety injection has occurre Safety injection is NOT rese The sequencer RESET pushbutton is pushed PRIOR to the sequencer '
completing its cycl WHICH ONE (1) of the following describes how the sequencing event la affected ,
by these conditions?
' It will continue from the spot that the sequencer was rese It will stop and-no further sequencing will take plac ! It will return to the first load group and begin sequencing over ;
agai , It will load shed the 4160V bus, then return-to the spot th sequencer was rese ANSWER: 036 (1.00)
3 [+1.0)
REFERENCE: LP OP-MC-DG EQB, p. 14, Objective _
I 2. -Modified McGuire Exam Bank Question 3 .- KA 064000A307 (3.6/3.7) :
064000A307 . . (KA's)
,
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f f
.
,,~.e 9 -+ w ,%y ,c.-- pwqm . w %y . , - - y ,- p y- e w, , , , .. -., ,,,-a . . . - , ,-w~ ,-=,...-e,,,,.,+4,,,,,-,% -, , ,,.,,, ,..-m, ,w-v.,,e----wg,v--
,
SENIOR REACTOR OPERATOR Page 32 QUESTION: 037 (1.00)
.Given the following conditions:
-
ENA ROOM SUMP HI LEVEL alarm is LI Containment Sump Totalizer was counting, but STOPPE The Liquid Waste system is in it's normal alignmen Initial radiation alarms are norma WHICH ONE (1) of the following is a possible.cause for this condition? The totalizer has failed tripping the ENA sump pump EMF-49L (Waste Liquid Monitor) has reached the TRIP 2 setpoint, [
securing the release, > WL-64A ( RB Sump Pump inside isolation valve) close , The Floor Drain Tank reached the "Hi Level" setpoint and secured th release to prevent overflo !
ANSWER: 037 (1.00) (+1.0)
<
REFERENCE: LP OP-MC-WE-WL, p. 20, Objective . .101 068000A404 (3.8/3.7)
068000A404 ..(KA's)
.
C'
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. . ~, _ . , _ _ , _ , _ , . . - , . - - _ . , _ , . . . ~ , _ _ _ , - _ . , . . _ _ , . _ _ , _ . . , _ . - . _ . , . . . _ - . _ . , _ _ , . _ _ , . .
_
-
-
,, _ - . . _ _ , . . _ , , .
_ _ _ - _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ ____ -___ _ _- ____. _ _ __ _____. _ - _ _ _ - _ ___-__.__ _ _ _ _ _ _ - _ _ _ _ _ _ _ ,.
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SENIOR REACTOR OPERATOR Page 33 -
i
i QUESTION: 038 (1.00)
WHICH ONE (3) of the following will result from a loss of power t i the detector of an area radiation monitor, RP-1A Readout Module? Indication will be at full scal ~ Indication will be at minimum scal ! Indication will be at the TRIP setpoint, Indication will be at the TRIP 2 setpoin ,
ANSWER: 038 (1.00) (+1.0]
REFERENCE: LP OP-MC-WE-EMF, p. 4 . KA 072000A201 ( 2. 'i/ 2 . 9 )
'
072000A201 . . (KA's)
.
QUESTION: 039 (l'. 0 0 ) ,
WHICH ONE (1) of the following conditions will automatically close the. Waste-Gaa Discharge Flow Controller (1WG160) when actuated?
-
,
a .- VCT Unit 1 Purge Flow'high alar Waste Gas Moisture Separator high pressure alar EMF 36 (HH) - Unit Vent Activit i d.- 1 EMF 36 (L) - Unit Vent Ga w-y--w-e ,hpwy p--a g. 3 -wy, -
.p gwm w p%.i .g ,em's, g . pga yp_, _%gg y,. y[ --
, - - - - ---. . _ _ _ - - - -_ _ _ _ . _ ______ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
l SENIOR REACTOR OPERATOR Page 34 ,
-j ANSWER: 039 (1.00) t i [ +1. 0) !
!
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'
REFERENCE: LP OP-MC-WE-EMF, p. 24, Objective l KA 073000K401 (4.0/4.3) ,
073000K401 . . (KA's) -
QUESTION: 040 (1.00) [
WHICH ONE -(1) of the following system pressures will all THREE _ (3) _ Main Fire _ !
pumps be operating? , psig
, psig ,sig ; psig .
. i s
->
ANSWER: 040 (1.00)
a.- (+1.0) *
REFERENCE: LP OP-MC-SS-RFY, p. 20, Ob;iective . KA 086000K402 (3.0/3.4)~ ,
086000K402 . . (KA's) ,
e b
.
-
h
-.h"w'-d , w h e --m w ib e-w,2,-ye. re h-rc .. rweer'cw-a, e g- -w-,re-,.-ymyN -w-. e- rr,sw- em.-wwy-,-,-,wm ,',,ewv,e hp rn,.r.-ww.-' --,.,we, * &bcy,
._
SENIOR REACTOR OPERATOR Pago 35-QUESTION: 041 (1.00)
Gien the following conditions:
- Unit 1 is at 75%.
-
Control rods are in AUT Bank D rods are at 160 stepa and stepping out with NO demand signa WHICH ONE (1) of the following actions are to be performed FIRST per AP/1/A/5500/14, " Rod Control Malfunctions"? Enter EP/1/A/5000/11.1, " Response to Nuclear Power -
Generation /ATWS". Trip the reactor and enter EP/1/A/5000/01, " Reactor Trip and Safety-Injection". Place the CRD bank selctor in MANUA Place the CRD bank selector in the CBD position.
,
- ANSWER: - 041 (1.00) (+1.0]
REFERENCE: - LP OP-MC-RT RCO, p. 27, Objective 1 . KA 000001K106 (4.0/4.2)
000001K106 ..(KA's)
.
' im
. _ . . . . _ _ . _ . . _ . _ . . . . _ _ _ . _ . _ . _ _ _ . . _ _ _ _ . _ _ . . -
- - _ _ _ _ - ~
.
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i' SENIOR REACTOR OPERATOR Page 36
!
QUESTION: 042 (1.00) ,
Given the following conditions: ;
!
-
A reactor startup is in progres !
-
Reactor power is at the point of adding hea Control bank B continues to withdraw when the control switch is <
returned to the neutral positio !
WHICH ONE (1) of the following reactor trips will mitigate the consequences of this event? _
l-i Source Range High Flux tri Power Range Nuclear Instrument High Positive Rate tri Intermediate Range Nuclear Instrument High Flux tri [ Power Range Nuclear Instrument High Flux High Setpoint tri >
l
.
ANSWER: 042 (1.00) , [ + 1. 0 )
'l REFERENCE: LP OP-MC-IC-IPE, p. 13, Objective 1 . KA 000001G004 (2.8/3.8) >
000001G004 ..(KA's)
-QUESTION: 043 (1.00)
WHICH ONE (1) of the following alarms is NOT an immediate symptomLof a dropped control rod? ROD CONTROL NON-URGENT _ FAILURE . RPI AT BOTTOM ROD DROP L
c. -P/R-HI FLUX RATE ALERT
- P/R CHANNEL DEVIATION
Y
.-w, . . w ,e E. m < . - ~E- -r
_ _ _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - - - _ _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ . _ . _ _._ _. _ _ _ _ _ ._ . . _ _ - ..__._ _ - _ _ __ _ _ _ _ _ _ -
!
l
- SENIOR REACTOR OPERATOR Page 37 .
I
!
!
ANSWER: 043 (1.00) [+1.0)
-!
REFERENCE: l LP OP MC IC-IRE, p. 42. Objective 16 . AP/1/A/5500/14 Rod Control Malfunction, Case II . F4 000003G011 (3.6/3.8)
-1 000003G011 ..(KA's)
,
QUESTION: 044 (1.00) -j Given the following conditions:
- Unit 1 is at 80% powe Control rods are in Aut ,
-
A Tave-Tref deviation of 5 degrees F exist f
- Control rods are NOT movin I WHICH ONE (1) of the following immediate actions should be taken? Adjust-Tave to within 1 degree of. Tref by dilution or boration, q Place the rod control in manual and verify control rod operability ~ '
by moving rods in 5 steps, then.out-5 step : Trip the Unit and enter EP/1/A/5000/01, "
Reactor Trip or Safety .
Injection", Place rod control in manual and adjust: turbine load-to match Tave to Tre :
.
ANSWER:. '044 (1.00)
d .' .[+1.0]-
,
F
)
_
"
w
'
= y W e,qyyy9%-3.ge-p+.ag.yyp +p-+ g g p y ng pqw.e,.y9 ye y y_y ,q. g . +,ye,- nym,.y i-pM:-m-qc gg
_ _ - - _ _ _ _ - - . . _ - _ _ - _ - _ . _ _ _ _ __ _ _ ..
t SENIOR REACTOR OPERATOR Page 38
.
REFERENCE:
1. LP OP-MC-IC-IRE, p. 40, Objective 16 .AP/1/A/5500/14, Rod Control Malfunctions, Case ; KA 000005G010 _(3.4/3.6)
000005G010 ..(KA's) ;
i
!
QUESTION: 045 (1.00)
WHICH ONE (1) of the following is a symptom of the failure of a control rod .
bank to move when in AUTOMATIC, per AP/1/A/5500/14, " Rod Control Malfunction"?- ' Unwarranted rod insertion / withdrawal, Rod control-urgent failure alar Power range Channel Deviation alarm.- , One or more rod' position indicators disagree by more than +12 ,
step .
'
ANSWER: 045 (1.00) (+1.0)
REFERENCE: ,
14 LP'OP-MC-IC-IRE, p. 40, Objective 16 . McGuire Exam Bank
~ KA 000005A101 (3.6/3,4)
000005A101 ..(KA's)
.
?
.
L
!
..N- . - - . - - . . - - -.- - - - - .-
.
- . - - -
.
- .- - . -,
.
A 4 e4,+>--ae_ ,A.- 6 A-,14n.- A 4 h- % , loa;w4 nt h& AA ,sa 4.::a
'
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' SENIOR-REACTOR' OPERATOR-
-
- Page-39 ,
,
QUESTION: 046 -(1.00) ,
WHICH-ONE (1) of the following. actions is required per EP/1/A/5000/01, 1" Reactor Trip or Safety Injection" if the turbine. fails to trip;and it-will-NOT trip manually? Continue on in EP-01 " Reactor Trip Safety Injection". Runback the turbine in Speed Control Mod Dispatch an operator to locally trip the. turbine, Manually initiate a main steam isolatio ANSWER: 046 (1.00) [+1.0)
' REFERENCE: LP OP-MC-EP-EP1, p. 11, Objective I . Catawba-1991 exa . KA 000007A107 (4.3/4.3)
000007A107 ..(KA's) ,
QUESTION: 047 (1.00) '
WHICH ONE (1) oof the following .shall be notified per Technical; Specifications, .
within one -(1) hour following a trip of the' Unit where the-NCS-parameters exceeded the safety limit curve? Vice President Nuclear Production NRC Operations Center Director of the-Nuclear _ Safety Review; Board Operating Superintendent
<
. -
__ _ . _ - _ _ _ _ _ _ _ - _ _
-~
-
-SENf0R' REACTOR OPERATOR- -
PageL40
? ANSWER: _047- (1.~ 0 0 )
-: b . (+1.0)
_
REFERENCE: Technical Specifications 2.1.2-and 6.7. .- LP OP-MC-ADM-TS, p. 13, Objective 3 . KA 000007G003 (3.4/3.9)
000007G003 ..(KA's)
_
-QUESTION: 048 (1.00)
WHICH ONE (1) of the following parameters discriminates between a vapor space-
-and non-vapor space LOCA? Pressurizer level Pressurizer pressure
._ PRT pressure RVLIS level ANSWER: 048 (1.00)
f [+1.0)
REFERENCE: LP.OP-MC-EP-EP16, p. 10, Objective 3 . KA -000008A212 (3.4/3.7)
000008A212 ..(KA's)
_
. .
a
,
. _ - _ - _ _ _ _ - _ _ _ - . _ _ . _
SENIOR REACTOR OPERATOR Page 41 QUESTION: 049 (1.00)
Given the following conditions:
-
A LOCA has occurred in Unit RVLIS indicates:
- Upper range level is 86%
- Delta-Pressure reading of 80%.
-
All NCP's are runnin WHICH ONE (1) of the following is the level indication used and the reason for its usage under these conditions?
_ Upper head level because the delta pressure indication is only accurate between 0% and 70% leve Delta pressure level because both areas are filled with a 2 phase mixture of approximately 34% quality, Upper head level because some core exit thermocouples indicate cold leg temperature instead of hot leg temperature in this rang Delta pressure level because all four NCPs are runnin ANSWER: 049 (1.00) [+1.0]
_
REFERENCE: LP OP-MC-IC-ICM, pp. 17-20, Objective 6 . KA 000009A110 ( 4 .1/ 4 .1)
000009A110 ..(KA's)
.
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. _ . . . _- . _ _ _ _ . . , .. _ . _ _ _ . - . _ __. . _ , . _ ... .-- . . . - - .
' SENIOR REACTOR OPERATOR- Page-42'
QUESTION: 050 (1.00)
.s
_Given_the following conditions:
- A natural circulation cooldown is being performed per EP/1/A/5000/ RVLIS is NOT availabl WHICH ONE (1) of the following parameters provides the first indication of a void in the reactor-vessel head during a natural circulation cooldown?--- NCS pressure Incore thermocouple temperature Pressurizer level- NCS hot leg temperature
-. ANSWER: .050- (1.00) , (+1.0) J-REFERENCE: LP OP-MC-EP-EP1, p. 16, Objective 2 . KA 000009A238 (3.9/4.3) j 000009A238 ..(KA's) ]
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SENIOR REACTOR OPERATOR Page 43 QUESTION: 051 (1.00)
Given the following conditions:
-
A large break LOCA has occurre ECCS is operating in Cold Leg Recirculation mod NCS pressure is stable at 200 psi WHICH ONE (1) of the following describes the primary method of decay heat removal? Condensation of reflux boiling in the Steam Generators, Heat is transferred between the NCS and Steam Generators due to natural circulation flow, Heat is transferred between the NCS and Steam Generators due to forced circulation flow, Heat is removed by the ND heat exchanger and injection of water from the containment sump while a water / steam mixture flows out from the brea ANSWER: 051 (1.00) [+1.0]
REFERENCE: LP OP-MC-TA-AM, p. 63, Objective 9 . KA 000011A111 (4.2/4.2)
000011A111 ..(KA's)
.
- . . . . . . . .
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.
- SENIOR REACTOR' OPERATO Page-44 QUESTION: 052 (1.00)
WHICH ONE (1) of-the.followingHis the reason for ensuring the NV pump
. recirculation valves are closed when NCS pressure is less than 1500 psig, per EP/1/A/5000/02 "High Energy Line Break Inside Containment"?- To prevent overpressurizing the recirculation line at maximum'NV '
pump discharge pressur To ensure maximum safety injection flow is directed to core, To prevent overheating-the NV pump during accident condition . To help diagnose the location of the leak by isolating a: potential leakage flowpath.
l l
,
ANSWER: 052 (1.00)
. [+1.0)
REFERENCE:
j .LP OP-MC-EP-EP2, p. 21, Objective 2 . KA 000011K307 (3.5/3.6)
L 000011K307 ..(KA's)
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.- _ _. . , _ - . _ _ . _ . . _ _ . - . . . . ._ ._ _ ,~ . -. . __ _
LSENIOR REACTOR'10PERATOR cPage~45;
.
QUESTION: 053 (1.00)
Given the-following conditions:
- The reactor has tripped from 100% powe NO reactor coolant pumps are runnin Natural _ circulation has been in progress.and stabilize WHICH ONE (1) of the following verfies that natural circulation is still taking place? NC loop Hot Leg temperature is 605 degrees-F and increasin S/G pressure is 900 psig and increasin Core Exit T/C's are 600 degrees F.and increasin NC system subcooling is 10 degrees and increasin ANSWER: 053 (1.00)
- (+1.01 REFERENCE: LP OP-MC-EP-EP1, p. 15, Objective 2 . EP/1/A/5000/1.1, Natural Circulation Cooldown, Fold out-pag . 0000015A121 (4.4/4.5)
000015A121 ..(KA's)
.
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- _ _ _ _ - _ ___ _ ___-_-__ - _ _
SENIOR REACTOR OPERATOR Page 46-QUESTION: 054 (1.00)
WHICH ONE (1) of the following is the MINIMUM NCP stator winding temperature that requires an NCP to be stopped following a loss of M AM flow according to AP/1/A/5500/08, Case II, "NC Pump Motor Malfunction"?
Y degrees degrees degrees degrees ANSWER: 054 (1.00) [+1.0)
REFERENCE: LP OP-MC-PS-NCP, pp. 27 & 35 , Objective 1 . AP/1/A/5500/08, Case II, "NC Pump Motor Malfunction", p. . KA 000015A210 (3.7/3.7) 000026A107 (2.9/3.0)
000015A210 ..(KA's)
.
'
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _________.____________________________________________b
_ - _ - - _ _ _ - _ _ _ - _ _ - _ _ _ _ _ _ . -_.
SENIOR REACTOR OPERATOR Page 47 QUESTION: 055 (1.00)
Given the following conditions:
-
NC PUMP SEAL INJ LO FLOW alarm is LI Pressurizer level is DECREASIN NC PUMP CTRL LEAKAGE LO FLOW alarm is LI REGEN HX LETDOWN HI TEMP alarm is LI WHICH ONE (1) of the following is the FIRST procedure that should be implemented? Loss of Charging Loss of Seal Injection Loss of Letdown Loss of Component Cooling Water ANSWER: 055 (1.00) [+1.0)
REFERENCE: LP OP-MC-PS-NV, p. 59, Objective 10 . AP/1/A/5500/12, Case II, p. . KA 000022G010 (3.5/3.4) 000022G011 (3.3/3.6)
000022G010 ..(KA's)
____ ___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
. SENIOR REACTOR OPERATO Page 48-QUESTION: 056 (1.00).
Given-the following conditions:
-
The reactor has trippe Three (3) rods are NOT fully inserte EP/1/A/5000/1.3 " Reactor Trip" is being performe WHICH ONE (1) of the following is the MINIMUM required-to meet the. emergency _
boration equirements? ppm of boric-acid tota ppm of boric acid total, ppm of boric acid total, ppm of-boric acid tota ANSWER: 056 (1.00) [+1.01 REFERENCE: i LP OP-MC-EP-EP1, p. 21, Objective 4 . KA 000024A205 (3.3/3.9)
000024A205 . . . ( KA ' s )
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M-SENIOR' REACTOR l OPERATO Page 49 QUESTION: 057 (1.00)
Given the following conditions:
-
Unit 1-is at 80% powe .
.
.
.
-
AP/1/A/5500/38, " Emergency Boration" is being_ implemented.-
WHICH ONE (1)- of the following is a positive indication that emergency boration is flowing into the NC system? CONTROL ROD BANK LO-LO alarm is-li Control rods are stepping ou Boric acid pump "A" is runnin Boronometer is decreasin ANSWER: 057 (1.00) [+1.0)
REFERENCE:
1.- LP OP-MC-PS-NV, Objective . AP/1/A/5500/38, Emergency Boration, . KA 000024A201 (3 . 8 /4.1)
000024A201 ..(KA's)
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SENIOR-REACTOR OPERATO Page 50-
.
19UESTION: 058- (1.00);
Given the following conditions:
-
The reactor vessel head is remove Reactor vessel upper-internals are installed in-the-reactor vesse Water level-in the NCS indicates 4 inches during mid-loo operation '
-
ND-1B and ND-2A (NC loop "C" to ND isolation) are ope NCS temperature is 140 degrees BOTH ND pumps are operating while train realignment is in progress.-
-
BOTH ND pumps begin cavitatin WHICH ONE (1) of the following explains why cavitation' occurred in this situation? The ND pumps lost' suction due to air entrainment because level is below the top of the hot legs, The ND pumps-lost suction because an inadequate vent path has created a vacuum on the NC The low NCS level allows the steam generator U tubes.to drain intermittently _ causing a-large amount of noncondensible gas to be entrained in the NC Minimum ND pump flow has heated pump recirculation flow and. caused steam binding of the' pump ANSWER: 058 (1.00)
- [+1.0)
'
~ REFERENCE:
. LP OP-MC-PS-ND, p. 22, Objective 11 . KA 000025K101 (3.9/4.3)
000025K101 . .(KA's).
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.- . - - . --. - -. . . . _ - . . .
SENIOR REACTOR OPERATOR ,
Page 51L 1 QUESTION: 059 ~ (1.00)
Given the following conditions: ,
-
Unit 1 has been shutdown for three -(3) days
-
A total loss of ND_ cooling occur No core cooling ~is immediately re-establishe The following pertinent plant conditions existed prior to theEloss of ND cooling:
NCS Tavg- ... 140 degrees NCS level ... 9" above hot leg (mid-loop).
SFP level ... norma No fuel has been replace WHICH ONE (1) of the following indicates how long it will take the NCS to reach saturation temperature? minutes minutes minutes minutes
,
ANSWER: 059 (1.00) [+1.0]
+
REFERENCE: AP/1/A/5500/19, Enclosure 1, , KA 000025G011 (3.6/3;9) o Generic Letter 88-17 Note: This question reveals if the. candidate is-sufficientlyfsensitive to-
-_the issue of' loss of RHR,_and the very.short time frame available to respond to,sam Industry events have occurred where RHR has been lost at reduced '
' inventory, and.one key issue is the~ operators were often not aware how little time =was available until-saturation was' reached in the_ core. The-question:
'does not require detailed knowledge of the saturation vs time curve due to1the very large time; frame of the' incorrect distractor .000025G011 ..(KA's)
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-
SENIOR REACTOR 10PERATORl I-Page.52
-_ QUESTION: 060 (1.00)'
Given.the following conditions:
-
Unit 1 is at 25% powe _
.
.
-
The controlling pressurizer pressure channel I fails HIG The pressurizer spray valves and PORV-NC34' OPEN Pressure has decreased,below 2170 psig,-PORV-NC34 is OPEN and will NOT. manually reclos Spray valve NC-27 is OPEN and will NOT manually RECLOSE.- -
,
WHICH ONE (1) of the following must be done after selecting a backup control channel per AP/1/A/5500/11, Pressurizer Pressure Anomalies? , Close the PORV block valve, trip the "B"-NC Close the PORV block valve, energize all pressurizer heaters, trip the "A" NC Close the PORV block valve, trip the Reactor, trip the "D" NC Trip the Reactor, initiate S ANSWER: 060 (1.00)
. (+1.01 REFERENCE:
1 LP OP-MC-PS-IPE, pp. 41-42, Objective S , 'AP/1/A/5500/11, pp. 2- . K A215 (3.7/4.0) ,
-000027A215 ..(KA's)=
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-l SENIOR-REACTOR OPERATOR Page.53; jQUESTION: -061 l(1.00)
'
Given the following conditions:
-
'The plant is at 50% powe Auctioneered Tave fails HIG "
,
-
Pressurizer level control is in AUT Assume no operator actio WHICH ONE (1) of the following is the effect on-pressurizer level? Decreases to the point of letdown isolatio Decreases to 25% and stabilize , Increases to 61% and stabilizes, Increases to the point of reactor tri ANSWER: 061 (1.00) (+1.0)
. REFERENCE: LP OP-MC-PS-ILE, , Objective 1 '
. KA 000028A202 (3.4/3.8)
E ;000028A202 ..(KA's) ,
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SENIOR: REACTOR.: OPERATO Page,54
,
l f
QUESTION: 062 (1.00)
WHICH ONE (1) of the following is the reason for ensuring that NCS pressure is
.less than 2335 psig in the immediate actions of EP/1/A/5000/11.1, " Response to
--Nuclear Generation /ATWS"? To prevent the rapid NCS over pressurization transientfexpected-with most ATWS event . To minimize primary to secondary leakage in case of the most limiting ATWS event, a SGTR, until other recovery actions can be take To allow enough borated water-to flow into the NCS-to ensure the addition of negative reactivity to the core, To begin a controlled cooldown.and depressurization, thereby minimizing positive reactivity feedback via a negative MT .
ANSWER: 062 (1.00) [+1.0)
,
,
REFERENCE: s f
1, LP OP-MC-EP-EP11, , Objective 2 . KA 000029K312 (4.4/4.7)
-000029K312 . . (KA's)
.
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.._ _ __ . .__ _ . ~ . ~_._ ___ _ ..__.__._ . . . . - . _ - _ . . . _ _ . . . _ . _ _ . _ .. - . . _ _
l SENIOR 1 REACTOR OPERATOR: Page 55 QUESTION: 063 -(1.00)
Given the following conditions:
-
Unit 1 is in MODE 6, refueling is in progres .
-
The audio count rate signal in containment has stoppe *
-
N-31 Source Range indication is errati WHICH.ONE (1) of the following describes the action to be taken per Technical Specification 3.9.2, " Instrumentation"? The audio count circuit must.b3 verified. operable and shutdown margin verifie Refueling operations and positive reactivity changes must be suspended, Containment building closure must be maintained-until the inoperable source range' channel is returned to servic All operations'that could add negative reactivity-to the-core must be suspended'until the channel is returned to service -
ANSWER:- 063 (1.00) (+1.0)
' REFERENCE: LP OP-MC-FH-FC, Objective 14 . Technical Specification 3.9.2, p. 3/4 9-2.
l : KA 000032G003 (2.6/3.3)
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000032G003 ..(KA's)
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ISENIOR REACTOR OPERATOR =Page,56 QUESTION: 064' (1.00)
'
- Given the following conditions:
- Unit ,Z is in MODE Reactor power is 10 E-08 amps, taking_ critical dat N-35 intermediate range instrument power fuses blow due to-an internal faul WHICH ONE (1) of the following it the appropriate action? Enter EP/1/A/5000/01, " Reactor Trip or Safety' Injection,_" atLSte . Hold power at 10 E-08 amps until repairs are mad Insert rods to lower neutron flux level to a value.within the-source-rang . Place the N-35 Level Trip switch in the BYPASS positio ANSWER: 064 (1.00) (+1.0]
REFERENCE: LP OP-MC-IC-ENB, p. 29, Objective'1 . KA 000033A207 (3.9/4.2)
'000033A207 ..(KA's)
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_ _ _ _ _ _
SENIOR REACTOR OPERA 70R Page 57
. QUESTION: 065- (1.00)
Given the following conditions:
- Unit 1 is in a refueling outag NO fuel movement is in progres A leak has developed which has caused level to drop in the spent fuel poo The SPENT FUEL POOL LEVEL LOW computer alarm has actuate Pool was initially at normal level-and area radiation at 7 mrem /h After 20 minutes the pool level has decreased further.and area radiation is 18 mrem /h Gr p curuk WHICH ONE (1) of the following describes the L usdiate operator response to the current conditions? Begin makeup to the pool from the Boric Acid Tank, h ts before they become uncovered, De-energize the underwater ' ' J Move the fuel transfer cart to the spent fuel side and close the transfer tube valv Notify radiation protection to monitor radiation level ANSWER: 065 (1.00) [+1.0)
REFERENCE: AP/1/A/5500/40, p. . LP OP-MC-FH-FC, p. 67, Objective 15 , 101 000036G010 (3. 7/3. 8 )
000036G010 ..(KA's)
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. . - -_ _ . .
. . .. . . _ . . _ _ ___ . ._ . _ . _ . . . . - - . _ - . . . , , . . ._ .. . . . - ._ , - . . . . .. - _ _
_ _
-
..
'
~ SENIOR REACTOR OPERATOR Page-_58-
.
t
_=-QUESTION: 066
.
(1.00)
'WHICH ONE (1) of the following is NOT a symptom c' a Steam Generator Tube -3
' Leak? .
,
n
' Increase in. frequency of. auto makeup to the:VC ,
.i
' Main feedwater reg' valve position trending ope ;
1 Feedwater flow to S/G "A" decreasin EMF-33 COND AIR EJECT-EXH HI RAD alar .
ANSWER: 066 (1.00) -; (+1.0]
REFERENCE:
1. - LP OP-MC-PS-NC, p. 49, Objective-15 _ _ AP/1/A/5500/10, NC System Leakage Within Capacity of_Both NV-Pumps, Case-1, Steam Generator Tube Leakag .3. KA 000037A206 (4.3/4.5)
000037A206 ..(KA's)
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. _ _ _ _ _ _ . - _ _ _ _ _ _ - - . _ _ . . ~ . _ _ . . . . . , _ ,.. __ ._ .
SENIOR REACTOR OPERATOR 'Page 5 .
' QUESTION: 067 (l'. 0 0 )
Given the following conditions:
-
Unit 1 is at 75% power-
- Steam Generator A-has an identified primary-to secondary leak of 30 gallons per day (calculated 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> ago) .
- Radiation alarms are received on.the Condenser air ejector and Steam Generator sample line,
-
Pressurizer level is 23% and NCS pressure is 1950 psig, both parameters are DECREASING rapidl WHICH ONE (1) of the following is NOT an immediate action that you are required to take? Start additional charging pumps to determine the size of the-leak, Initiate a controlled shutdown per OP/1/A/6100/02, " Controlling '
Procedure for Unit Shutdown." Turn on all available heaters to maintain pressure, Initiate a manual reactor trip and safety injection and enter EP/1/A/5000/01, " Reactor Trip or Safety Injection".
s
'
ANSWER: 067 (1.00) [+1.0]
REFERENCE: LP OP-MC-PS-NC, p. 49, Objective 15 . AP/1/A/5500/10, "NC System Leakage-within. Capacity of Both NV Pumps",
Case . KA 000038G011 (4 2/4.3)
000058G011 ...(KA's)
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.
SENIOR REACTOR-: OPERATOR .Page 60
,
[ QUESTION: 068 (1.00)
'
WHICH ONE (1) of the following symptoms differentiates between a LOCA'andia Main' Steam Line break inside containment?
a.- Increasing containment radiation level Increasing containment sump levels, Increasing containment pressur , Decreasing pressurizer pressur _
'
ANSWER: 068 (1.00) [+1.0) ,
REFERENCE:
- 1. - LP OP-MC-EP-EP2, p. 17, Objective 1 . KA 000040A203 (4.6/4.7)
000040A203 ..(KA's)
QUESTION: 069 (1.00) _
WHICH ONE (1) of the following accidents presents thefGREATEST.potentialifor a Pressurized Thermal Shock (PTS) condition? Steam Line Break
' Excessive Feedwater Event c.- Large LOCA d.- Main Feedline Break- G
, . - .- . .~ .-. . _ _ . - - . - . . . . .,
SENIOR REACTOR-OPERATOR' Page 61
..
' AWSWER:
. :069L (1.00)
- -a.- _ (+1.0)
.
REFERENCE:
l '. LP OP-MC-TA'-PTS, pp. 31-42, Objective.1 . KA 000040K106 (3.7/3.8)-
000040K106 ..(KA's)
QUESTION: 070 (1.00)
Given the.following conditions:
-
Unit 1 is at 70% powe CONDENSER LO VACUUM (PRE TRIP) alarm is LI Condenser vacuum has been decreasing for the past fifteen (15);
minute WHICH ONE (1) of the following is'the condenser vacuum at.which a Reactor / Turbine Trip will FIRST be initiated per AP/1/A/5500/23, " Loss of Condenser Vacuum"? inches H inches Hg
. inches Hg ' inches Hg ANSWER: 070 (1.00)
b , - - [ +1. 0 ]
,
2 g , . - , ~
- -
.- .. - - - - - ..
.
- .
SENIOR REACTOR OPERATOR Page 62 REFERENCE: LP OP-MC-MT-MT, p. 51, Objective 2 ,
2.- AP/1/A/5500/23, " Loss.of Condenser Vacuum", p. . KA 000051A202 (3 . 9 /4 .1)
000051A202 ..(KA's)
QUESTION: 071 (1.00)
WHICH ONE (1) of the following statements indicates why CA-flow rate is procedurally restricted to 100 GPM when recovering a steam generator level if the level has fallen below 9% wide range indication? Minimize thermal stress conditions on steam generator component Minimize NCS cooldown rate and prevent resultant thermal
'
stress on NCS component Ensure NCS inventory demand does not exceed normal charging pump capacit ~ Ensure pressurizer level transient does-not result in prersure transient that would actuate S ANSWER: 071 (1.00) [+1.0)
-REFERENCE: LPLOP-MC-EF-EP13*,'p 21, Objective 6 . KA 000054K102 (3.6/4.2)
000054K102 ..(KA's)
.
+ e -v w m e - #
.. . _ ....-..._ _ _ .___ _ ._ _ _ .. _ _.. . . . _ . _ . - . _ -
. __ ._ _ . .
-SENIOR 1 REACTOR OPERATOR-
.
-
Page 63
.
~
- QUESTIONr 07 (1. '0 0 ) -
-
~
WHICH ONE-(1) of the following_-is'the reason-that cool'down is-limited-while performing a cooldown and depressurization per EP/1/A/5000/09, " Loss of All A Power"? To prevent-the injection of nitrogen from the cold leg-accumulators, To minimize the thermal shock to the NCP pumn seals when cooling is restore To minimize the amount of seal leakage.in.the event of a-seal failure, To prevent the possibility of recriticality from occurring.
ANSWER: .072 (1.00) [+1.0]
REFERENCE:
l'. LP OP-MC-EP-EP09, p. 10, Objective 2 . KA 000055K302 (4.3/4.6)
'
0000SSK302 ..(KA's)
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-; SENIOR REACTOR'OPERATORE
.
'Page 64 QUESTION: 073 (1.00)
-Given the following conditions:
-
A loss of all AC power has occurred. . _ _
-
Steps are-being performed to establish NC-pump seal injection from-1 ETA room per EP/1/A/5000/09, " Loss of All AC Power".-
WHICH ONE (1) of the-following will occur when 1EMXA-4 is switched to its alternate power supply? Standby makeup pump isolation valves (1NV-842AC, 1NV849AC) will be transferred to the SS Control of the pressurizer spray valves (1NC-27, INC29) will be transferred to the Auxiliary Shutdown Pane Letdown isolation valve (NV-1A) will automatically-open, Turbine driven CA pump to S/G "B" isolation valve (CA-54A)1wdll-
-
clos ~ ANSWER: 073 (1.00) [+1.0)
REFERENCE: EP/1/A/5000/09, " Loss of All AC Power", Enclosure 2, . LP OP-MC-EP-EP09, Objective 2 . KA 000055A106 ( 4 .1/4 . 5 ) .
000055A106 ..(KA's) {
,
-
4
SENIOR REACTOR OPERATOR- .Page 65~
QUESTION::07 (1.00):
Given the following conditions: .
-
Unit.1 is at 100% powe ETB experiences a loss of offsite powe .
-
B Train components are in servic ~WHICH ONE (1) of the following is the reason that Unit 2-is-notified to start -;
'
.the 2A RN (Nuclear Service Water) pump? The blackout signal load sheds the 2A pump while the. Unit 1 D/G comes up to spee The blackout signal causes train separation and flow may be lost to the essential header The blackout signal load sheds the 2A pump while its suction switches to the assured sourc .
- The blackout signal causes train separation and flow may be' lost: to the nonessential header ANSWER: 074 (1.00) [+1.0)
,
EREFERENCE: LP_OP-MC-PSS-RN, Objective ,
- .LP OP-MC-EL-EP, p. 4 . AP/1/A/5500/07, Loss of_ Electrical _ Power, Case II, p. 21, KA 000056K302 (4.4/4.7) 000056A107 ( 3 . 2 / 3 .' 2 )
' A107 000056K302 ..(KA's)
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SENIOR REACTOR OPERATOR: Page-66
..
$
QUESTION: 075 (1.00)
.Given the following conditions:
- A Waste Monitor Tank release is in progress.-
-
EMF-49 (LOW-SAMPLE FLOW) has been-in alarm-for 3 minutesLand will-NOT rese Double verification of valve alignment has NOT been' performed.
'
WHICH ONE (1) of the following is the reason for declaring EMF-49 inoperable and suspending the release? To ensure that the radiation detector does not become saturated with radioactive particulates during the low flow condition and .
require replacement, The LOW SAMPLE FLOW alarm should have cleared within 2.5 minutes after initiating the releas To ensure that the radioactive liquid release will be monitored before passing.the discharge isolation valv To ensure that an unmonitored release of EMF-49 calibration fluid'
is not taking plac b ANSWER: 075 (1.00) (+1.0]
REFERENCE: LP OP-MC-WE-RLR, p. 13, Objective . KA 0000059K303 ~ (3.0/3.7)
000059K303 ..(KA's) :
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SENIOR-REACTOR OPERATOR Page 67 !
!
i QUESTION: 076 (1.00) ,
Given the following conditions:
- Unit 1 is in MODE Refueling is in progres The containment evacuation alarm is soundin '
WHICH ONE (1) of the following radiation monitors activates the containment evacuation alarm?
' EMF-16 (Reactor building refueling bridge). EMF-17 (Spent fuel building refueling bridge) . ; EMF-38 (Containment-particulate low range), EMF 40 (Containment iodine monitor).
ANSWER: 076 (1.00) (+1.0]
REFERENCE:
' LP OP-MC WE-EMP, pp. 16 & 28, Objective 3', KA 000061A101 (3.6/3.6)
,
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SENIOR REACTOR OPERATOR Page 68 QUESTION: 077 (1.00)
Given the following conditions:
-
Unit 1 is at 100% powe An unisolable rupture of the Instrument Air (VI) header has occurre WilICil ONE (1) of the following conditions and associated reason will cause the reactor to trip following a total loss of instrument air? The main feed regulating valves will close causing a steam generator low level tri The letdown isolation valves will lose and the pressurizer will fill up causing a pressurizer high level tri The pressurizer spray valves will fail open causing a pressurizer low pressure trip, The auxiliary spray valve will fail open causing a pressurizer low pressure tri ANSWER: 077 (1.00) [+1.0)
-
REFERENCE: EP/1/A/5500/22, p. 3, Objective . KA 000065K308 (3.7/3.9)
000065K308 ..(KA's)
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SENIOR REACTOR OPERATOR Page 69 s
QUESTION: 078 (1.00)
WHICH ONE (1) of the following is the purpese of procedure AP/1/A/5500/17,
,
" Loss of Control Room"? ,
' It describes the procedure for cooling down the NC system from Hot Standby to Cold Shutdown when the control-room is uninhabitable, It describes the steps to be taken to prepare the plant for Hot Shutdown, followed by Cold Shutdown af ter a fire at the Auxiliary ;
Shutdown Panel, It describes the steps required to take the plant from Hot Standby to Cold Shutdown following a fire event that renders the control room and auxiliary shutdown panel unusabl It describes the steps to be taken to achieve and maintain Hot Standby in the event of control room evacuation for reasons other than fire.
.
ANSWER: 078 (1.00) [ + 1. 0)
,
REFERENCE: LP OP-MC-CP-SS, pp. 8-9. Objectives 1A,B,C, , KA 000068G012 (3.8/4.0)
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SENIOR REACTOR OPERATOR Page 70 QUESTION: 079 (1.00)
Given the following conditions:
- The Standby Shutdown Facility (SSF) has been actuated :lue to a security even The SSF diesel generator has been starte WHICH ONE (1) of the following trips is available in the current SSF diesel generator mode of operation? Low lube oil pressure High jacket water temperature Engine overspeed Jacket water low pressure M4SWER: 079 (1.00) [+1.0)
R.EFERENCE: LP OP-MC-CP AD, p. 14, Objective 6 . KA 000068A131 (3.9/4.0)
000068A131 ..(KA's)
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SEMIOR REACTOR OPERATOR Pago 71 ,
i
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QUESTION: 080 (1.00) -1
- i WHICH ONE (1) of the following conditions would VIOLATE Containment Integrity ,
if the plant ascended into MODE 4"? ,
i IVO-1A (Cont Air Release Inside Isol) has its air supply removed and has failed close KF-122 (Fuel Transfer Tube) is fully opened, but can be manually- l closed, KC-429B (Rx Bldg Draain Hdr Inside Isol) has lost its power supply, but is close RN-253A (RB Non ESS Sup Inside Isol) failed its stroke ciming test, but can be closed from the control roo ,
,
ANSWER: 080 (1.00) [+1.0) REFERENCE: Technical Specification 3.6.1.1, p. 3/4 6- . Technical Specification 3.6.1.2, p. 3/4 6-2, LP OP-MC-ADM-TS, p. 9, Objective 2 . KA 000069A201 (3.7/4.3)
000069A201 (KA's)
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SENIOR REACTOR OPERATOR Page 72 QUESTION: 081 (1.00)
Given the following conditions:
-
Unit 1 tripped from 100% powe NCS pressure rapidly dropped to below 1000 psi SI actuated, cnd started injectio Containment pressure rapidly increase Steam generator pressures and levels remained close to normal post trip value Safety injection flow has been reduce Source range nuclear instrumentation energized, and initially showed a decreasing count rat Count rate turned and increased, stabilizing at 2 decades higher than a normal shutdown 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> into the acciden WilICH ONE (1) of the following is the reason for the higher than nornal source range reading? The SI water is cool, increasing the moderating effect and fission count rate over the amount normally expected, As the core void fraction approaches 100%, the fission rate increases due to boron displacement from the core, Core boiling is occurring, resulting in a decrease in boron concentration in the lower part of the core, increasing fission rat Downcomer voiding is occurring, allowing more neutrons to leak out of the cor ANSWER: 081 (1.00) ( + 1. 0)
REFERENCE: LP OP-MC-TA-AM, pp. 45-46, Objective F . KA 000074A207 ( 4 .1/ 4 . 7 )
000074A207 ..(KA's)
-_ . _ _ -_ _ _ __ .
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_ . . _ - . _ . - _ . . . . . _ _ _ . . _ _ _ _ _ _ _ . _ - _ . _ _ _ _ . _ _ _ . _ . _ . _ _ _ _ . _ _ _ . - _ . _
SENIOR REACTOR OPERATOR Page 73 QUESTION: 082 (1.00)
Given the following conditions:
- A LOCA has occurred in Unit The NCP's are runnin RVLIS indicates the upper head and upper plenum are draine WilICil ONE (1) of the following is the status of the coolant that RVLIS is exposed to? Only steam, Steam or a two-phase mixture, c. - Completely covered with water in the plenum area only, Only water.
ANSWER: 082 (1.00) (+1.0)
REFERENCE: LP OP-MC TA-AM, pp. 26-28, Objective l . KA 000074A101 (4.2/4.4)
'000074A101 ..(KA's)
SENIOR REACTOR OPERATOR ' Page 74 QUESTION: 083 (1.00)
Given the following conditions:
-
Unit 1 has been at 100% power for 30 day Chemistry reports that NCS activity is 1.5 microCuries per gram DOSE EQUIVALENT I-13 Isotopic analysis determines the activity is from a crud burs WHICH ONE (1) of the following actions should be taken per AP/1/A/5500/18,
- High Activity in Reactor Coolant"? Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> initiate action to place the Unit in HOT STANDBY with Tave less than 500 degrees F w3. thin 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Place standby cation demineralizer bed in service and maximize letdown, Place NV-127 (Letdown HX outlet 3-way temperature control) in the DEMIN position and maximize letdow Reduce letdown to minimum and establish an NCS pH between 6.5 and 7.5 by chemical injectio ANSWER: 083 (1.00) [+1.0]
-REFERENCE: .AP/1/A/5500/18, "High Activity in Reactor Coolant", p . - l '. Technical Specification 3.4.8, p. 3/4 4-2 ' KA 000076K305 (2.9/3,6)
000076K305 . . (KA's)
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SENIOR _ REACTOR. OPERATOR' Page 75 QUESTION: 084 (1. 0 0 ) -
WHICH ONE (1) of the following positions has direct responsibility for issuance and recall of yellow " HOLD" tags?
a Operations Superintendent Operating Engineer Shift Supervisor Station Manager
$
ANSWER: 084 (1.00) , (+1.0)
REFERENC , Station Directive 3.1.19, p. 4 . KA 194001K102' (3.7/4.1) 1 194001K102 ..(KA's) ;
QUESTION: _085 (1.00) (
WHICH ONE (1) of the following positions-will assume the responsibilities ofl Emergency Coordinator when the Technical Support Center is~ activated?- , Operations Superintendent !
b.-. Shift Supervisor Station Manager Vice President Nuclear Operations
.
ANSWER:' 085 (1.00) (+1.0) ,
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SENIOR REACTOR OPERATOR Page 76-
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REFERENCE: l
! LP OP-MC-EP-EMP,-p. 15, Objective . KA 194001A116 ( 3 .1/4 . 4 )
194001A116 ...(KA's)
!
i QUESTION: 086 (1.00) ,
WHICH ONE (1) of the following is considered a Temporary Modification ,
per Station Directive 4.4.2, " Control of Temporary Modifications"? l Modifications installed ';n equipment that is out of
'
servic Installation of tygon tubing on a pump's drain lin A design change to a syste Gagging a relief or safety valv _
_, _
e ANSWER: 086 (1.00) j (1.0)
REFERENCE: Station Directive 4.2.2, Control of Temporary Modifications, Attachment 6.6, pp. 1- .
' LP OP-MCaADM-SD, Objective 10 . KA 194001A112 (3.1/4.1) McGuire exa A112 ..(KA's)
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SENIOR REACTOR OPERATOR Page 77-QUESTION: 087 (1.00)
Given the following conditions:
-
During the July - September quarter you received a 317 mrem whole body dose while assisting with refueling operation During the current quarter October-December you have received a total of 183 mrem whole body exposur You have an NRC Form 4 on fil WHICH ONE (1) of the following is the MAXIMUM additional exposure you can receive this quarter without exceeding any McGuire Administrative exposure limits? O mrem mrem- mrem , mrem ANSWER:- 087 (1.00)
b.- [+1.0)
' REFERENCE: Radiation Protection Manual,.p. 3 & Exhibit 2.1- . LP OP-MC-RAD-HPM, Objective j EA 194001K103 (2.8/3.4)
'
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SENIOR REACTOR OPERATOR Page 78 QUESTION: 088 (1.00)
WHICH ONE (1) of the following defines the McGuire Low Population Zone (LPZ)? The 2500 foot radius area surrounding the reactor building where whole body dose will not exceed 25 Re The area immediately outside the protected area fence where whole body dose will not exceed 2 mrem /h An area where outside a radiation area where whole body dose will-not exceed .5 mrem /h ' The 5.5 mile radius area surrounding the plant where whole body-dose will not exceed 25 Re .;
L ANSWER: 088 (1.00) [+1.0)
REFERENCE: , LP OP-MC-RAD-HPM, pp. 30-33, Objective 38, KA.194000K105 (3.1/3.4)
194001K105 ..(KA's)
QUESTION: 089 (1.00)
WHICH ONE (1) of the following is a requirement for exiting and final inspection'of a confined space when work is complete? The_last' crew member exiting verifies that all materials have been removed and signs the permit, verifying closure, The work supervisor removes all red tags from the site and returns them to the_ shift superviso c .- The work supervisor closes the space, signs, dates and' initials the-original permit, verifying closur . The-shift supervisor walks down the job site, verifies proper
-
closure and signs the permi ,
l
-. . - , - - . , ,
-,
SENIOR REACTOR OPERATOR Page 79 ANSWER: 089 (1.00) [+1.0)
REFERENCE: Station Directive 2.10.3, Safety Procedure for Working in Confined Spaces, . LP OP-MC-ADM-SD, Objective . KA 194001K114 (3.3/3.6)
194001K114 ..(KA's)
QUESTION: 090 (1.00)
Given the following conditions
-
Unit 1 is in MODE Entry into lower containment must be made to inspect for suspected NC system leakag WHICH ONE (1) of the following determines how " stay time" will be affected if respirators are to be used? It is not affected if ice vests are use The-Low Metabolism chart is used, The Moderate Metabolism chart is use The High Metabolism chart is used.
ANSWER:- 090 (1.00)
- [+1.0)
-.
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,
SENIOR REACTOR OPERATOR Page 80 REFERENCE:
'
. Station Directive 2.10.6, Heat Stress Program, p. . LP OP-MC ADM-SD, Objective 10 . KA 194001K108 (3.5/3.4)
194001K108 ..(KA'a)
.
i QUESTION: 091 (1.00)
WHICH ONE (1) of the following is a duty of a Fire Watch? Reporting hourly status to the Safety and Health Services sectio , Closing a blocked open fire door upon discovery of'a fir Logging area conditions every 15 minute ' Remaining in the area for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after.an actual-fire has been extinguishe P ANSWER: 091 (1.00) (+1.0) .
REFERENCE:
e 1. . Station Directive 2.11.2, Fire Protection and Surveillance', p ',
2. LP OP-MC-ADM-SD, Objective 10 ,
3. KA 194001K116 (3.5/4.2)
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SENIOR REACTOR OPERATOR Page 81 QUESTION: 092 (1.00)
WHICH ONE (1) of the following is NOT a responsibility of an Operations Group when a fire barrier is found to be inoperable? Ensuring that the daily and weekly fire door procedure _is properly complete Logging inoperable fire barriers in the Technical Specification action log book, Writing work requests to repair fire doors.- Determining whether an hourly or continuous fire watch is require ANSWER: 092 (1.00) [+1.0)
REFERENCE:
1 Station Directive 2.11.5, Technical Specification Fire Barriers, pp. 3- . LP OP-MC-ADM-SD, Objective 10 . KA 194001K116 (3.5/4.2)
194001K116 ..(KA's)
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SENIOR REACTOR OPERATOR ' age 82 QUESTION: 093 (1.00)
WHICH ONE (1) of the following is a proper procedure _for gaining access to the Controlled Access Area (CAA) in the control room? The NRC Resident Inspector performing a surveillance requiring multiple entries to the CAA enters through a-NO ENTRY _ gat An on shift instrument technician enters the CAA between the control boards without reactor operator permission, A maintenance worker enters through the CONTROLLED. ACCESS POINT
'
with permission from an off duty SR An on shift electrician enters through a NO ENTRY gate after receiving permission for multiple entries into the CAA and starts a new tas ANSWER: 093 (1.00) (+1.0)
REFERENCE: Station Directive 3.1.1, Control Room Access, p. . LP OP-MC-ADM SD, Objective 10 . KA 194001K105 (3.1/3.4)
194001K105 ..(KA's)
-
-
a
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SENIOR REACTOR OPERATOR Page 83 QUESTION: 094 (1.00)
WHICH ONE (1) of the following is the process for locking out an Operator Aid Computer (OAC) computer point that requires a password? Notify the Control Room SRO for authorization and the password, fill out the lockout logbook then remove the point from service, Notify the Reactor Operator, receive the password from the Control Room SRO, remove the point from service then fill out the lockout logboo Notify the Shift Manager for authorization and password, notify the reactor operator, fill out the lockout logbook then remove the point from servic Notify the Control Room SRO, Notify the Shift Manager for authorization and the password, remove the point from service then fill out the lockout logboo ANSWER: 094 (1.00) (+1.0)
-REFERENCE:
1.- Station Directive 3.1.36, OAC Scan Lockout, p. . LP OP MC ADM-SD, Objective 10 . KA 194001A115 (3.1/3.4)
194001A115 ..(KA's)
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_._ _ _.__ _ _ _ _ __ _ . _ . . - _ _ . . . . . _ _ _ _ . . _ _ .-
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SENIOR REACTOR OPERATOR Page 84
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QUESTION: 095 (1.00)
WHICH ONE (3) of the following describes the required actions to retrieve a red tag stub if the work supervisor responsible for the job is not on site? Another Work Supervisor in that group may authorize retrieval, as long as he has phone approval from the responsible Work Supervisor, The Group Superintendent respcnsible for the work must determine the work is complete and approve tag retrieva The Unit Supervisor must determine the work is complete and approve tag retrieva The Shift Supervisor is the only individual who can authorize tag retrieval in this situatio ANSWER: 095 (1.00) [+1.0)
REFERENCE: Station Directive 3.1.19, Safety-Tags, p. 1 . LP OP MC-ADM-SD, Objective 10 . KA 194001K102 (3.7/4.1)
194001K102' ..(KA's)
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. . _ . - _ . . - ,
-
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J SENIOR REACTOR OPERATOR Page 84 '
QUESTION: 095 (1.00) !
WHICH ONS (1) of the following describes the required actions to retrieve a red tag stub if the work supervisor responsible for the. job !
[ -is not on site? i L
f Another Work Supervisor in that group may authorize retrieval, as long as he has phone approval from the responsible Work
'
Superviso > The Group Superintendent responsible for the work must determine the work is complete and approve tag retrieva The Unit Supervisor must determine the work is complete and approve _ ;
tag retrieva t d The Shift Supervisor is the only individual who can authorize tag retrieval in this situatio ANSWER: 095 (1.00) [ + 1. 0 )
REFERENCE: Station Directive 3.1.19, Safety Tags, p. 17, LP OP-MC-ADM-SD, Objective 10 . KA 194001K102 ( 3 . 7 /4 .1) '
194001K102 ..(KA's)
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SENIOR RFACTOR OPERATOR Page 85 QUESTION: 096 (1.00)
Wii1Cil CNE (1) of the following describes how to verify the position of a manually operated TilROTTLE valve on a syst,9m that is required to be in operation?
a, Move the valve slightly in the closed direction and then return it to its required positio Completely close the valve and then reopen it to the required positio Inspect the last valve . lineup sheet for verification signature and compare recorded valve position with the required positio Observe the position of the valve Stem, position indicator, or flow indication and compare it to the required positio ANSWER: 096 (1.00) [41.0)
REFERENCE: OMP 1-B, Valve and 13reaker Identification, p. . LP OP-MC-ADM-OMP, Objective 9 . KA 194001K101 (3.6/3.7) ~
d 194001K101 ..(KA's) . .
SENIOR REACTOR-OPERATOR Page 86 QUESTION: 097 (1.00)
WHICH ONE (1) of the following_ conditions requires an Removal and Restoration (R&R) to be used? When a-system alignment which is not within the original intent of the system is implemente When n long term system alignment is implemente When a system alignment is implemented that requires removal of_a piece of equipment from service that is within the. design of.the syste When equipment is removed _from service for a_short period of time (within a shift) with control room SRO permission.
ANSWER: 097 (1.00) [ + 1. 0)
REFERENCE: OMP 2 17, Tagout/ Removal and Restoration Procedure, pp. 2 . LP OP-MC-ADM-SD, Objective 10 . KA 194001K102 -(3.7/4.1)
194001K102 ..(KA's)
QUESTION: 098 (1.00)
WHICH ONE (1) of the following describes how bullet steps in the' Emergency
_
Operating Procedures are to be performed?
a. . They must be performed in sequence only when the: steps are immediate action steps, They must all be performed before the next tauk is. started, They must be-performed from memory,_followed by verification using the procedur .They'may be-performed in any sequenc D
- ._ . _ . _ _ -
SENIOR-REACTOR OPERATOR Page 87 ANSWER: 098 (1.00)
'd . [+1.0)
REFERENCE: LP OP-MC-EP-EPF, p. 10, Objective . KA 194001A102 (4 .1/3. 9 )
194001A102 ..(KA's)
>
QUESTION: 099 (1.00)
WHICH ONE (1) of the following describes how initials are transferred to an updated issue of a working copy procedure? The person who initia11ed-the original-procedure must initial the new procedure in the presence of the Unit Manage The control-room SRO is the only person who-may initial the new procedure with approval from the Unit Manage The RO at the controls initials the new procedure after another-operator locally independently verifies the procedure is correct and initials i Any licensed operator may transfer initials to the new procedure with Unit Manager approva ANSWER: 099 (1.00) [+1.0)
REFET :E:
1. LP OP-MC-ADM-OP, p. 15, ObjectiveL10.-
2._-:KA 194001A102 (4 .1/ 3. 9 )
194001A102 ..(KA's)
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_ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ - _ - _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ - _ _ _ _ - _ _ - _ _ _ _ - _ _ _ _ - _ _ _ - - _____-___ _ _ _-________ _ _ _ _
SENIOR REACTOR OPERATOR Page 88 QUESTION: 100 (1.00)
Given the following conditions:
-
Unit 1 is operating at 100% powe Adjustments are to be made to the packing for the S/G CF Co14tainment Isolation Valves (CF-26, 28, 30, 35).
- The valves will be BLOCKED OPEN while work is being performed on each valv WHICH ONE (1) of the following is the status of each valvo while work is being performed? The valves are OPERABLE, but must be stroke timed following t completion of work to verify operability, The valves are INOPERABLE unless a dedicated operator is standing by to remove the valves should a feedwater isolation be require The valves are OPERABLE as long as the accumu.ators remain: >
pressurize i The valves are INOPERABLE until the blocks are REMOVED and the valve is stroke timed to verify operabilit .
ANSWER: 100 (1.00) ~j (+1.0)
REFERENCE: Station Directive 2.8.2, Operability Determination,-Attachment 2, p. 3, -
l step 4 . KA 194001K101 (3.6/3.7)
194001K101 ..(KA's)
+
,
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(********** END OF-EXAMINATION **********)
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, DRAFT COPY pte gyg 9,; .y of N Q r be. H Dy f
.1*ns' }.*sl /f O E sro m U. S. NUCLEAR REGULATORY COMMISSION SITE SPECIFIC EXAMINATION REACTOR OPERATOR LICENSE REGION 2 CANDIDATE'S NAME:
FACILITY: McGuire 1 & 2 REACTOR TYPE: PWR-WEC4 DATE ADMINISTERED: 92/12/07 -
INSTRUCTIONS TO CANDIDATE:
Use the answer sheets provided to document your answers. . Staple this cover-sheet on top of the answer sheet Points for_each-question are indicated in parentheses after the question. The-passing grade requires a final grade of at least 80%. Examination papers will be picked up four (4) . hours af ter-the examination start CANDIDATE'S TEST VALUE SCORE i 100.00 % TOTALS FINAL GRADE All work done on this examination is my ow I have neither given nor received ai Candidate's Signature h
DRAFT COPY-hai t
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REACTOR OPERATOR Page 2-QUESTION: 001 (1.00)
WHICH ONE'(1) of the following conditions will cause a NON-URGENT failure alarm at the power cabinet? Blown Lift Coil Fuse Loss of multiplexer signal Loss of one power supply Failed pulser L-ANSWER: 001 (1.00)
-! (+1.0) .. ;
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REFERENCE: LP OP-MC-IC-IRE, p. 15, Objective ! KA 001000G008 (3.6/3.6)
001000G008 . .(KA's)
QUESTION: 002 (1. 0 0 ) -
-WHICH ONE (1) of the following describes the function of the lift coil-disconnect-switch?
- Allows the master cycler to function without moving.any rod b, Allows retrieval of a dropped or misaligned ro Allows the rods to drop in the eventlof a reactor trip-during-maintenance on the rod * system.-
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d. LAllows a bank of rods to be disconnected from the power cabinet for maintenanc .
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_ _ _ _ _ _ _ _ _ _ _ _ _
REACTOR OPERATOR Page 3 i
ANSWER: 002 (1.00) (+1.0)
REFERENCE:
1. 'sP OP- MC- IC- IRE , p. 26, Objective . KA 001000K409 ( 3 . 9 / 4 .1)
001000K409 ..(KA's)
QUESTION: 003 (1.00)
Given the following conditions:
-
Unit 1 is at 80% powe Control Bank D is at 200 step Power Mismatch is -1 degree Temperature Mismatch is -1 degree Rod Control is in AUT WHICH ONE (1) of the following statements describes the response of the rod control system to these conditions?
a. The control rods step in at 40 steps per minut b. The control rods step out at 40 steps per minut c. The control rods step out at 8 steps per minut d. The control rods step in at 8 steps per minut ANSWER: 003 (1.00) [+1.0)
REFERENCE: LP OP-MC-IC-IRX, p. 23, Objectives 3G, 3H, 3 . KA 001000K402 (3.8/3.8)
001000K402 ..(KA's)
__ __ ._. _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -____ _ _ _ _ _ __ - -
.._ -_.- . _ _ _ _ . . . __ __._. _ _ _ . . _ _ . . _ ,
REACTOR OPERATOR Page 4 QUESTION: 004 (1.00)
Given the following conditions:
-
The reactor is in MODE NCS temperature is 275 degrees Steam Generator pressure is 100 psi Pressurizer level is 95%.
WHICH ONE (1)_of the following must be done before an NC pump can be' started, according to OP/1/A/6150/02A, "
Reactor Coolant Pump-Operation"? Pressurizer vente NC temperature raised tc,285 degrees Steam Generator pressure increased to 150 psi Pressurizer level decreased to 90%.
t ANSWER: 004 (1.00) ' [+1.0)
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REFERENCE:
1. LP OP-MC-PS-NC,-Objective 1 . OP/1/A/6150/02A, Reactor Coolant Pump Operation, p. .. Technical Specification 3.4.1.3, p. 3/4- . KA 002000G010 (3.4/3.9)
002000G010 . .(KA's)
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REACTOR OPERATOR Page 5
.i QUESTION: 005 (1.00)
The-following conditions exists
-
Reactor power is 100%. -
- Annunciator 1AD-9 D/1, "A COLD LEG ACCUMULATOR ABNORMAL LEVEL" is j LI !
-
Cold Leg Accumulator A level has increased from 7325 gallons to:7500 gallons over the last 15 minute ,
- Cold Leg Accumulator fill valves have been verified isolated from the accumulato '
-
There has been NO previously identified leakage into this accumulato WHICH ONE (1) of the following NCS leakage limits has been exceeded per T.S. 3.4.G.2, " Operational Leakage"? The NO PRESSURE BOUNDARY LEAKAGE limi , The 1 gpm UNIDENTIFIED-LEAKAGE limi ' The 1 gpm NCS PRESSURE ISOLATION VALVE LEAKAGE limi The 10 gpm' CONTROLLED LEAKAGE limi ANSWER: 005 (1.00) [ (+1.0)
-REFERENCE:
1. LP OP-MC-PS-NC, p. 40, Objective 1 . Technical Specifications 3.4.6.2, p. 3/4 5-1, 3. KA 002000G011 (3.3/3.9)
002000G011 ..(KA's)
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REACTOR OPERATOR- PageL:61
pg
, LQUESTION: 006 (1.00) a WHICH :ONE -(1) of_the following NCS piping penetrations extends into the
~ coolant s tream? --
9 Prassurizer Spray Line, Pressurizer Surge Line.
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[ NV Normal Charging.
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l- ND Pump Suction.
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i ANSWER: 006 (1.00)
. a '. [+1.0)
. REFERENCE: LP OP-MC-PS-NC, p. 15, Objective . KA 002000K109 ( 4 .1/4 .1) -
002000K109 ..(KA's)
, QUESTION: 007 (1.00)
l
- WHICH ONE (1) of the rollowing is the reason that all the NCP breakers open'on:
underfrequency?
' To protect the %:i a. ti-rotation device _ from damage due to abnormal L_ coastdown, To preuerve the NCP flywheel kinetic energ To. avoid water hammer transients in the NCS. induced-by rap'id-NCP>
.
speed. change, To reduce.the-probability of a stress induced NCP sheared shaft ;
acciden H L
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.CTOR OPERATOR Page 7 ANSWER: 007 (1.00) [+1.01 REFERENCE: LP OP-MC-IC-IPE, p. 14, Objective 1 . KA 003000G007 (3.2/3.3)
003000G007 ..(KA's)
QUESTION: 008 (1.00)
Given the following conditions:
-
Unit 1 is operating at 20% powe Rod control is in AUT A NCP has trippe WHICH ONE (1) of the following describes the effect on the Loop "A".NCS conditions?
t Tave Decreases soop "A" flow reverses 7 hot equals Tcold Tave Decreases Loop "A" flow decreases Tcold is less than other loops Tcold Tave Increases Loop "A" flow re';erses Thot equals the other loops Thot Tave Increases Loop "A" flow decreases Thot is less than other loops Thot ANSWER: 008 (1.00) [+1.0)
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. . _
. __ > _ _ _ . . . _ _ > _. - , _ - . . - _ . - . _ . - . - _ . _ _- . . - . . . . . . _ . . _ . , . _
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REACTOR OPERATOR Page 8 2 REFERENCE: .;
rl . LP OP-MC-PS-NC, p. 25,. Objective ' 2. iKA 003000K301--(3.7/4.0).
003000K301- ..(KA's) ;
-QUESTION: 009 (1.00)
Given the following conditions:
-
NCP 1B #1 seal leakoff temperature is 215 degrees +
-
NCP Seal Return Bypass Header _ Isolation (1NV-92A) is CLOSE k
. WHICH GNE (1) of the following conditions.would PREVENT INV-92A.from being-opened, according to OP/1/A/6150/02A " Reactor Coolant Pump Operation", Limits-and Precautions? NCS pressure is at 400 psig.
, No. 1 seal leakoff valveEis ope a No. 1 seal-leakoff is 1.5 GP Seal injection flow to'each NCP is 7'GP .
' AWSWER: 009 (1.00) [+1.0)
7 REFERENCE:
003000A201 . . -( KA ' s ) - --
.
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' REACTOR OPERATOR Page- 9-QUESTION: 010 (1.00)-
WHICH ONE (1)= of the following is the reason why the Chemical and Volume -
Control System (NV) auxiliary spray should NOT be used if letdown!is isolated?- It is incapable of equalizing pressurizer and NCS boron concentrations, The spray line cannot provide enough flow to control pressurizer pressure, There is no preheating and spray nozzle may be thermally-shocked, It causes excessive vibration in the spray lin ANSWER: 010 (1.00) (+1.0)
REFERENCE: LP OP-MC-PS-NV, p. 52, Objective 9, KA 004000K509 (3.7/4.2)
004000K509 ..(KA's)
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_ _ . . . _ _ _ __ . _ .___ _ _ _ _ _ _ _ _ _ _ . . ~ _ _ _ - . __
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.
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~ REACTOR OPERATOR Page 10
.
. QUESTION: 011 (1.00)
'
- Given the following conditions:
J
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The Volume Control Tank (VCT) is at 42%..
-
Automatic make-up is in progres A leak develops in the reference. leg associated with level controller (NVLT-5760).
-
Assume no operator actio WHICH ONE (1) of the following describes the FIRST system response? NVLT-5761 will begin modulating letdown flow via NC Filter Outleti3- ,
way control valve NV-137A.
- Indicated VCT level will decrease.- Automatic makeup to ths VCT will sto NV pump suction switches to the FWS ' ANSWER: 011 (1.00) [+1.0)
REFERENCE: LP OP-MC-PS-NV, pp. 17-18, .and 25, . Objective 3E and ', System Description MC-1223.04, pg. 3 . KA 004010A211 (3.1/3.1)
004010A211 ..(KA's) ;
. _ _ . _ . - . , , __ - _
_ _ . _ _ _ _ _,
REACTOR OPERATOR Page 11 QUESTION: 012 (1.00)
Given the following conditions:
-
Unit 1 is at 80% powe All control systems are in their normal oper& ting alignmen WHICH ONE (1) of the following leaks could result in a DILUTION of the NCS? Regenerative Heat Exchanger leak Letdown Heat Exchanger leak
- Reactor Coolant Drain Tank Heat Exchanger leak Seal Water Heat Exchanger leak ANSWER: 012 (1.00) [+1.0)
REFERENCE: LP OP-MC-PS-NV, Objective . McGuire Simulator Malfunction NV-24, NCP Seal Water Heat Exchanger Tube KA b4000K118 (2.9/3.2) ;
004000K118 ..(KA's)
QUESTION: 013 (1.00)
WHICH ONE (1) of the following conditions must be met to open ND-2A (NC loop
"C" to ND isolation)? ND-1B (Train B suction from C NC loop) ope NI-185A (Containment sump suction) closed, NI-136B (NI suction from ND) close FW27A (ND suction from Refueling Storage Tank) open.
- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ .
- _ . -~ _
-. . . . . _ . . - . . . . . - . . . . _ . _ . . - - .
_
REACTOR-OPERATOR ' Page 12'
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LANSWER: 013 (1.00) [+1.0]
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' REFERENCE: , LP OP-MC-PS-ND, p. 20, Objective l'
- 2. KA 005000K407 (3.2/3.5)
005000K407 ..(KA's) ,
QUESTION: 014 (1.00)
- Given the following conditions:
- Unit 1 is at 100% powe All control systems are in their normal alignment.-
WHICH ONE (1) of the following is the reason that VCTLoutlet' isolation valves ~
(NV 141, 142) both close on'a_ Safety Injection (Ss) signal? Prevents lower boron concentration water in the=VCT from being1 added to the safety injection flo Prevents the loss of FWST water via-the non-safety portion of the '
NV system in the event of a-pipe ruptur Prevents overpressurizing the-VCTfduring a safety _ injection sequenc Prevents _ exceeding the design negative ~ pressure:for-the-VCTion a-safety injectio ANSWER: 014 (1.00) (+1.0]
.
-= e -, , - ., y, --, - - ~. . ,
A REACTOR OPERATOR Page l'3 REFERENCE:
-
1.-- LP OP-MC- PS -!W, p. 3 .- 006000K108 (3.6/3.9)
006000K108 ..(KA's)
QUESTION: 015 (1.00)
WHICH ONE (1) of the following parameters would require declaring a cold leg; accumulator INOPERABLE?- NI-54A isolation valve is ope ; Borated water-volume is 6500 gallon Boron concentration is 1950 pp Nitrogen cover pressure is 630 psi ANSWER: 015 (1.00)
- [+1.0)
-REFERENCE: LP OP-MC-ECC-CLA, p. 13, Objective 7 ._' Technical Specification 3.5.1, p. 3/4-5- . KA 006000G005 (3.5/4.2)
006000G005 . . -( KA ' s )
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. REACTOR OPERATOR' Page 14
. QUESTION: 016 (1.00) '
'WHICH ONE (1) of the following components discharges to the Pressurizer Relief Tank (PRT) ? Positive displacement pump discharge relief valv NC to ND suction relief valve, Relief valve (NV-156) downstream of letdown pressure control. valve.- VCT relief valv = ANSWER: 016 (1.00)- (+1.0)
REFERENCE: LP OP-MC-PS-NV, p . 31, Objectives 2 & . KA 007000K103 (3.0/3.2) ,
007000K103 ..(KA's)
QUESTION: 017 (1.00)
WHICH ONE (1) of the following would occur on a tube-leak in the-Component-Cooling Water-(KC) Heat Exchanger? _ Automatic KC system makeup-from the Nuclear Service-. Water--(RN))
-
,
would occur, providing the1necessary NPSH to the.KC_ pump ~ KC' system liquid _ inventory-would increase,._thus increasing the KC flow rate to components cooled by the KC syste , KC would leak into the Nuclear-Service Water =(RN) System,.
potentially contaminating the RN syste KC surge tank level would increase, which would cause the vent-valve'to lift due to increasing:KC-system. pressure.
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REACTORL OPERATOR .-Pagef15'
5 ANSWER: 017 (1.00)
c .- . [ + 1. 0 ] .,
1 REFERENCE:
. LP OP-MC-PSS-KC, p. 11,-Objective .- System Description MCSD-1223.23-00, pp. 9-10, & 2 . KA'008000K101 (3.1/3.1)
000000K101- ..(KA's)
QUESTION: 01 (1.00)
Given-the following conditions:
-
Unit 1 is at 100% powe Pressurizer heaters are OF Nornal . pressurizer : spray valves are modulatin Pressurizer'PORV's are close WHICH ONE (1) of.the following NCS pressures is: appropriate'for the above;
--conditions?
' psig psig
,
c.- 2272-psig psig ANSWER: 018 (1.00)
<
. . [ +1. 0)
REFERENCE:=
-- LP.OP-MC-PS-IPE, p. 36,' Objective 4'.
. KA;010000A107 (3.7/3.7)
,
010000A107 ..(KA's)
- . . . . . .=. . - . - - -
.. - .. . .- .~.. _ . . . . . -.. - - . . .
' REACTOR' OPERATOR Page 16 QUESTION: 019 (1.00)
WHICH ONE (1) :of the following is an input to the Low l Temperature -
-
Overpressure Protection circuitry for PORV NC34A?
- Wide range loop "D" pressure instrumen Narrow range Pressurizer pressure instrumen ~ Auctioneered high wide range cold _ leg temperatur Auctioneered high wide range hot leg temperatur ANSWER: 019 (1.00) (+1.0)
. REFERENCE: LP OP-MC-PS-IPE, p. 24, Objective I .. KA 010000K403 ~ (3. 8 /4.1)
010000K403 ..(KA's)
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-
REACTOR OPERATOR Page 17 QUESTION: 020 (1.00)
Given the following conditions:
-
All pressurizer heaters were on prior to actual pressurizer leve dropping to 12%.
-
A safety injection occurred; Safety injection and the sequencer have been RESE Pressurizer level has been restored to 46%.
WHICH ONE (1) of the following describes how the heaters will respond? Heater banks A & B will come on automaticall Heater banks A & B can be manually energize Heater banks C & D will come on automatically, Heater banks C & D can NOT be manually energize .s ANSWER: 020 (1.00) [+1.0]
REFERENCE:
1, LP OP-MC-PS-ILE, p. 11, Objective I . KA 011000K603 (2.9/3.3)
011000K603 ..(KA's)
. . . _ . _ . _ _ _ . . . . . . . _ - _ . .
.-)
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[ REACTOR' OPERATOR Page 18 ]
~
l QUESTION: '021 (1.00)'
_Given:the following conditions:
-
-Reactor power-is at-99%.
-
Pressurizer level-.is at'58%.
-
75 gpm letdown flo Charging line containment outside isolation valve (1NV-244A) has failed CLOSED.-
-
Assume no operator actio .WHICH ONE (1) of'the following statements describes the plant response to.thi accident? Slightly lower pressurizer level due to isolation _of letdown upon-loss of cooling flow and steam-flashing in letdown.lin Slightly higher pressurizer level due-to isolation of letdown with--
continued seal injection: flow to recover level, Decreasing pressurizer level-to 17%, letdown isolates and heaters turn'off leading to low-pressure trip, Decreasing pressurizer level to 17%, letdown isolates.and-pressurizer level slowly increases leading to high level __ trip.
,
ANSWER: 021- (1.00) (+1.0)
'
' REFERENCE:
' LP OP-MC-PS-ILE, p.-10, Objective'1 . -- KA 011000A303 (3.2/3.3)
011000A303 ..(KA's)
,
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.
REACTORLOPERATOR: Pagefl9l QUESTION: 022 -(1.00)
WHICH ONE- (1) of the following statements describes a trip _ directly associated with the P-8 permissive? Undervoltage - NCP Busses, Pressurizer high pressure tri Two loop loss of flow tri Turbine tri ANSWER: 022 (1.00) [+1.0]
REFERENCE: , LP OP-MC-IC-IPE, p. 22, Objective 1 . KA 012000K406 (3.2/3.5)
.-
012000K406 . .- ( KA ' s )
-
--QUESTION: 023 (1.00)
WHICH ONE'(1) of the following describes how the reactor. tri breaker trip-coils are affected:by a MANUAL reactor trip?
.
a. UV coils and shunt coils are all'de-energized, b. UV coils are de-energized, the shunt coils are energize c. Only the UV coils are de-energized,_the-shunt coils are-unaffecte d.- Only the Shunt coils are energized, the IAT coils are unaffecte !
-
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REACTOR OPERATOR Page 20--
. ANSWER: 023 ('1. 0 0 )
b.- (+1.0]-
REFERENCE: LP OP-MC-IC-IPE, p. 13, Objective 1 . KA 012000K603 (3.1/3.5)
012000K603 ..(KA's).
QUESTION: 024 (1.00)
WHICH ONE (1) of the following will result in a Main Steam Isolation? ASSUME Eall control switches are in their normal position for operatio Containment pressure equal to 3.0 psig'on 1/4 detectors, Pressurizer pressure equal to 1840 psig on 3/4 detector "A" Steamline: pressure equal to 575 psig on 2/3 detectors and pressurizer pressure equal to 1970 psi Tave equal to 545 degrees F and reactor trip breakers open, sANSWER: -024 (1.00)
L ( +1. 0]
!-
REFERENCE:
1. OP-MC-ECCS-ISE,Lp. 19, Objective 1 _
2.-KA 013000K403 (3.9/4.4)
013000K403 ..(KA's)
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REACTOR OPERATOR Page 21 QUESTION: 025 (1.00)
WHICH ONE (1) of the following use P-4 as an input to initiate an ESF actuation signal? Feedwater isolatio . Steamline isolatio Auxiliary Feedwater actuation, Containment Spray actuatio _
ANSWER: 025 (1.00) [+1.0)
REFERENCE: LP OP-MC-ECC-ISE, p. 20, Objective 1 . KA 013000A301 (3.7/3.9)
013000A301 ..(KA's)
.
/
_
, _ . - _ ___ __ _ _ _ _ . _ ..__._ _ . , - _ . _ _ , _ . . . _ _
- _ . . . _ _ _ _ _ _ _ . . - - ._ _ .. . .
REACTOR OPERATOR Page'22-QUESTION: 026 (1.00) :
Given the following conditions:-
-
Unit 1 is in MODE It has been determined that BOTH SI trains-automatic actuation logic and actuation relays did NOT meet the-surveillance acceptanc i criteria for the test previously conducted in MODE 5,,but_the -
manual _ initiations passed the surveillance WHICH ONE ~(1) of the following actions should be taken? Stay in MODE 4 and do NOT allow transition to MODE _ Continue with the plant startup, no restraints appl > Enter and comply with Technical Specification 3. Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> verify the actuation relays are in the requtred state for the existing plant conditio ,
-ANSWER: 026 (1.00) (+1.0)
REFERENCE:
1. LP OP-MC-ECC-ISE,fp. 5, Objective 3 ._ Technical Specifications, p. 3/4 3-16, 2 . KA 013000G005 (3.6/4.2)
013000G005 ..(KA's)
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'-REACTOR OPERATOR . Page 23
. 9UESTION: 027 (1.00)
WHICH - ONE - (1) of--the'following actions is used to determine.the position of--
the non-indicating rod upon declaring a single DRPI INOPERABLE--in Bank D per:
Technical Specification 3.1.3.2, " Reactivity Control. System"? Use incore detectors to perform a flux nap of the cor Perform current measurement of coils on'CRDM Use incore system.with a magnetic proximity probe attachment to
'
detect the rod tip positio _
. Monitor and analyze QPTR chang ANSWER: 027 (1.00) [+1. 0)
REFERENCE:
, 1.'LP OP-MC-IC-EDA, Objective . Technical; Specifications 3.1.3.2, p. 3/4 1-1 . KA 014000A206 (2. 6/3. 0)
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014000A206 ..(KA's) j
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-REACTOR-OPERATOR Page 24 QUESTION: .028 -(1.00)
-Given the following conditions:-
-~ Unit 1 la at 100% powe The Digital Rod Position Indicating System (DRPI) has experienced a failure of the "A" Data Cabine WHICH ONE-(1) of the following is the accuracy of a lit rod position LED for these conditions? +10 to -4 steps +4 to -10 steps +10 to -10 steps +4 to -4 steps-j ANSWER: 028- (1.00) - [+1.0) .-
REFERENCE:
i LP OP-MC-IC-EDA, p. 15, Objective S . KA 014000A102 (3.2/3.6)
014000A102 (KA's)
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- _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - . _ _ _ _ _ _ _
REACTOR OPERATOR Page 25 QUESTION: 029 (1.00)
WHICH ONE (1) of the following describes the result of OVERCOMPENSATION of the Intermediate Range Nuclear Instrumentation Detectors? The source range nuclear instruments will automatically energize at a higher power level than normal, Permissive P-6 will not automatically deenergize on a reactor shutdow The Hi Flux at Shutdown alarm will be automatically blocked, Permissive P-10 will not automatically deenergize on a reactor shutdown.
ANSWER: 029 (1.00) (+1.0]
REFERENCE: OP-MC-IC-ENB, pp. 14-15, Objectives 6 . KA 015000A303 (3.9/3.9)
015000A303 ..(KA's)
-- _ - _ _ _ - _ _ _ _ - _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ - _ _ _ - _
-
u REACTOR OPERATOR ,
Page 26:
QUESTION: 030 (1. 0 0 )'
)
LGiven the following conditions:
- Unit 1 is in. MODE 6, refueling is in progres Scaler Timer drawer is in MANUAL mod WHICH ONE (1) of the following will occur.if the nuclear instrumentation Audio Count Rate and Scaler Timer Drawer Reset Pushbutton'is pushed? The display is reset and the gate is armed so the next pulse starts the count, The display, (decades counter or clock time base) are reset.- The instrument is reset and operet;on is stopped until the start ;
pushbutton is depressed in ANY MOD The audible count rate pulses are reset to a discernable rat ANSWER: 030 (1.00) [ + 1. 0 )
REFERENCE: , LP OP-MC-IC-ENB, p. 35, Objective . KA 015000A301 (3.8/3.8)
015000A301 ..(KA's)
QUFSTION: 031 (1.00)
WHICH' ONE - (1) of-the following is NOT an input used by the Train "A" LSubcooling Margin Monitor? Wide Range Loop Pressure ' Phase B contact = Core: Exit Thermocouple Temperatures Wide Range-Hot Leg Temperature
... . - _ _ ~ _ . . .
_. _ . _ . . - - . . . _ . . . _ ._ . . . . _ . _ -_ .. . _ . _ _ _ _ - - _ . _ . . _ . _ _ .
"
.
_REACTO_R OPERATOR Page 27 ;
.-
ANSWER: - -031 (1.00)- ,
=' [+1.0)
-;
REFERENCE:
- LP OP-MC-IC-ICM, p. 25, Objective '. KA 017000K401 (3.4/3.7)
017020K401 ..(KA's)
-QUESTION: 032 (1.00)
WHICH ONE (1)-of.the following Containment Ventilation systems will restart following a LOCA?.- Lower Containment Ventilation (VL). Syste . Upper Containment Ventilation (VU) System.: o; Containment Purge (VP) Syste ' Pipe. Tunnel Booster Fan (PT) Syste ANSWER: 032- (1.00)
~ . [+1. 0]
~ REFERENCE:
..
1.-LP- OP-MC-CNT-VUL, p. 16,_ Objectives 1 A301 (4 .1/4. 3 )
'
- 2. KA
-
-022000A301 ..(KA's)
.
.
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-, ,- .- , - . . _ . . - - - . . . - - - .-..- . .- .- . -. . . _ . - . -
REACTORLOPERATOR i Page-28-QUESTION' '033 (1.00)
'WHICH ONE (1) of-the following is the automatic action'that occurs as'a result' -
of the indicated alarms associated with the Glycol Expansion Tank?' '
.
a. -High level, trips the glycol pump Low-Low level, closes containment isolation valves (1NF-228A,-1NF-
'
233B, INF-234A). Hi-Hi level, secures makeup to the Ice Condenser Syste Low level, initiates automatic makeup from the Glycol' Mixing and Storage Tank.
,
ANSWER: 033 -(1. 0 0 ) (+3.0) ,
1-REFERENCE: LP OP-MC-CNT-NF, p. 21, Objective 6.
-
2. KA 025000G008 (3. 8/3. 8)-
.
025000G008 ..(KA's) _
QUESTION:=034 (1.00)
.
WHICH ONE (1) of the following is the plant condition that can result from
' inadvertent operation of the Containment Air Return Fans?-
- The ice condenser inlet doors may open.and cause containment-
~
. pressure to fall below. allowable limits, The fans will overpressurize the ice condenser.and_ prevent.-the:
inlet doors from opening as designe c. .It will reposition the discharge dampers and cause reverse air flow'
- through1the ice condenser, It will equalize pressure between lower containment and dead'end spaces and prevent FSAR flow-requirements from being met.
,
, #. 4 ,, _.dee,-, --. _ , y ,m,.'., ,. ,. :,, , ,, y 7- r, y
_
r
~ REACTOR ~ OPERATOR-
-
Page 29-ANSWER: 034 (1.' 0 0 )
a '. - -[+1.0)
REFERENCE: LP OP-MC-CNT-VX, p. 22, Objective 1 ~ KA 028000G010 (3.0/3.2)
028000G010 ..(KA's) ,
- QUESTION
- 035 (1.00)
a Given the following conditions:
-
A refueling outage has been complete The reactor missile shield has NOT been set in plac WHICH ONE _(1) of the following is the-reason for ensuring that the' Purge Mode Selector Switch is returned to the NORMAL position when_ aligning the purge system, according to OP/1/A/6450/15, " Containment Purge. System", Limits:and!
Precautions? To prevent overpressurization of-the upper; containment'.= To ensure that any purge is routed through the eleanup filters,
' To prevent _ isolation of the containment purge supply-fan To ensure the system actuates on high containment pressur .
TANSWER: _035 (1.00) [+1.0}
REFERENCE:
- LP OP-MC-CNT-VP, p.117, Objective . 'OP/1/A/6450/15 _" Containment ~ Purge System"'
- KA'029000A103
-
(3.0/3.3)
029000A103 ..(KA's) -
-
. . . -_ _ . . _ - _
- - REACTOR- OPERATOR Page 30)
LQUESTION: 036- (1.00)-
Given_the-following conditions:
-
Reactor is in MODE 6
-
-The following alarms are LIT:
INCORE INST-ROOM SUMP HI LEVEL EMF-16 CONTAINMENT REFUELING BRIDGE SPENT FUEL POOL LEVEL LOW-WHICH ONE (1) of the following procedures should be implemented? AP/1/A/5500/25 " Spent l Fuel-Damage" AP/1/A/5500/40 " Loss of Refueling Canal Level" AP/1/A/5500/19 " Loss of-ND or ND System Leakage" AP/1/A/5500/24 " Loss of Containment Integrity"
.
. ANSWER: 036 -(1.00) [ +1. 01 REFERENCE: LP-OP-MC-FH-FC, Objective 1 . 'AP/1/A/5500/40, " Loss of Refueling Canal Level"
' 3 ^. KA 034000G015 '(3.3/3.7)
034000G015 ..(KA's) ,
,
e
.
h REACTOR -_ OPERATOR ; LPage 31-
-QUESTION:.037 _( 1. 0 0 ) -
Given the-following conditions:
-
-Unit 1 is operating at 100% powe SG "D" wide range level instrument fails LO GIICH ONE (1) of the following is affected by this failure? SG "D" level trip setpoin SG "D" narrow range level instrument . - SG "D" level control signa SG loop "A" and "D"-three pen chart recorde ANSWER: 037 (1.00) (+1.0)
REFERENCE: LP OP-MC-STM-SG, p. 15, LP OP-MC-CF-IFE, Objective . KA 035010A101 (3.6/3.8)
035010A101 ..(KA's)
_ - - _ - .
, .- . -. . . . _ ~ . . . - -
- ;
,
k
.REACTORJOPERATOR . Page'32 QUESTION: 038 (1.00)
Given the following conditions:
!
- The reactor tripped from 100% power, ',
- "B" Reactor trip breaker is OPE "A" Reactor trip breaker is CLOSE Steam Dumps are in the Tave Mod WHICH ONE (1) of the following demonstrates the status of the Steam Dumps as-a result of this transient? Steam dump banks 1 & 2 are armed by C-7B interloc Steam dump banks 3 & 4 are armed by C-7A interlock, Stean dump banks 1 & 2 will modulate to bring Tave to Tnoloa Steam dump-banks 3 & 4 will modulate to bring Tave to Tnoloa .
ANSWER: 038 (1.00) [ +1. 0 )
REFERENCE:
1 LP OP-MC-STM-IDE, p. 31, Objective 1 . KA 041020K417 (3.7/3.9).
041020K417 ..(KA's)
QUESTION: 039 (1.00)
-WHICH ONE (1) of the following are affected when the Turbine EHC Overspeed-
,
Protection Controller (OPC)1 solenoid-valves energize at1103%-turbine speed?: Reheat Stop and Throttle Valves Reheat Stop and Governor-Valves . Intercept and Throttle Valves d.: Governor and Intercept Valves
,
- , . 5. . -- ,
. _
, . - . . . . . . . . .- . . . . . . . . - ~ . - _- - . - . .. - -. -
LREACTOR OPERATOR .PageJ33 ANSWER: 039 (1.00)
L (+1.0]- l REFERENCE: , LP OP-MC-MT-MT, p. 32, Objective 12 '
LP OP-MC-GEN-EHC, p. 14, Objective 1 ' . KA 045000A401 (3.1/2.9)
045000A401- . . (KA's) /0
. QUESTION: 040 (1.00)
WHICH ONE (1) of the following will trip a Main Feedwater (CF) pump?. FDWPT suction pressure is 215 psi > FDWPT oil pressure is 15 psi _
, FWDPT discharge: pressure is 1235 psi t
, Doghouse water level ~is 10 inches..
.
' ANSWER: 040 (1.00) (+1.0]
REFERENCE:
- 1 ^. LP.OP-MC-CF-CF,.p. 28,. Objective : KA 059000K416 (3.1/3.2) .
059000K416 . . (KA's)
a p =--u r -a v - n ., , , .- , N~
__ _ _______________-____________-____
REACTOR OPERATOR Page 34 I QUESTION: 041 (1.00)
WilICH ONE (1) of the following is the power supply for the Unit 1 CA pump motor 1B? TB ELXB ITD ETB
_
ANSWER: 041 (1.00) [+1.0)
REFERENCE: LP OP-MC-CP-CA, p. 30, Objective . KA 0610001 2 (3.7/3.7)
061000K202 ..(KA's)
QUESTION: 042 (1.00)
Giver. the f ollowing conditions:
-
Tne TD CA pump control switch is in the LOCAI positio The START /STOP switch is in the STOP positio An autostart signal has started the TD CA pum whirl ONE (1) of the following describes how the turbine speed is being controlled AND the location from which it is being controlled? By manual control knob at the local control pane By potentiometer at the local control panel By manual control knob at the governor, By potentiometer at the governo _ - -- -__---_ - -_ _ __
_ _ _ _ _ _ _ - - _ _ ___ _ _ _ - _ - _ _
REACTOR OPERATOR Page 35 [
I
.
ANSWER: 042 (1.00) I (+1.0) ;
!
,
REFERENCE: LP OP-MC-CP-CA, pp. 17 18, Objective 1 . KA 061000G009 (3.8/3.9) [
061000G009 ..(KA's) f J
QUESTION: 043 (1.00)
-Given the following conditions:
- Unit 1 is in MODE 3 with all plant systems in their normal. lineup.-
- Auxiliary transformers 1ATA and 1ATB- are HOT in synchronization when a fault in the protective zone of 1ATA occur WHICH ONE (1) of the following describes the transfer of power lforLthe 7 KV-buses?
r An automatic rapid transfer from 1ATA to 1ATB will-occur;-
and, when the fault on 1ATA clears, an automatic rapid transfer back to 1ATA will occu An automatic rapid transfer from 1ATA to 1ATB will occur; but, when the fault clears, no automatic transfer back to 1ATA will occu An automatic slow transfer from 1ATA to-1ATB will-occur;_ '
and, when the fault on 1ATA clears, an automatic slow transfer back to 1ATA will occu An automatic slow transfer'from 1ATA to-1ATB will occur; .'
but, when the: fault clears,-no-automatic transler back to
'
1ATA will occu ,
LANSWER: 043 (\.00) (+1.0) ,
.
I
.1 m, y - +o .+ . ..,m,,..,w, m,,c,m, s., , , , , ,
- - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
__ .
!
!
. l REACTOR OPERATOR Page 36 ,
I REFERENCE: j e
'
. LP OP MC-EL-EP, p. 25, Objectives 21 & 2 . KA 062000A401 (3.3/3.1) [
t
!
062000A401 ..(KA's) ,
i I
,
QUESTION: 044 (1.00) j
!
Given the following conditions:
- Unit i startup is in progress.
.
- The turbine is being synchronized to the-grid por OP/1/A/6300/01, ;
" Turbine Generator Operation". _
_
-
The Synchroscope has been adjusted to move slowly in the-FAST directio i-WHICH ONE (1) of the following describes the two parameters monitored'by the 't
-
synchroscope? - --
_ _
. Frequency and phase difference l Frequency and current difference : Current and voltage differences, Current and phase difference .
ANSWER: 044 (1.00)- [+1.0)
REFERENCE:
1. LP OP-MC-EL-ETR, p. 40, Objectives 9 & 1 . KA_062000A403 (2.8/2.9)
2 06200.0A403- _..(KA's)
,
.- .. . - _ . - . _...;_ , _, ,--.-._: . ,_ __. .. uc2_; 2 -. _ _ . . - . , _ .u.- . - . . .
REACTOR OPERATOR Page 37 1
- I
,
QUESTION: 045 (1.00) l
,
Given the following conditions: [i
- The reactor has tripped from 100t powe A safety injection has occurre ,
-
Safety injection is NOT rese The sequencer RESET pushbutton is pushed PRIOR to the sequencer completing its cycl WHICH ONE (1) of the following describes how the sequencing event 11s affected by these conditions?
' It will continue from the spot that the sequencer Was rese It will stop and no further sequencing will take place, It will return to the first load group and begin sequencing over agai It will load shed the 4160V bus, then return to the spot the sequencer was rese ,
L ANSWER: 045 (1.00) (+1.0) ,
REFERENCE: j LP OP-MC-DG-EQB, p. 14, Objective . Modified McGuire Exam Bank Question-3, KA 064000A307 (3.6/3.7)
064000A307 ..(KA's)
.
i
REACTOR OPERATOR Page 38-QUESTION: 046 (1.00)
Given the following conditions:
-
ENA ROOM SUMP HI LEVEL alarm is LI Containment Sump Totalizer was counting, but STOPPE The Liquid Waste system is in it's normal alignmen Initial radiation alarms are norma WHICH ONE (1) of the following is a possible cause for this condition? The totalizer has failed tripping the ENA sump pump EMF-49L (Waste Liquid Monitor) has reached the TRIP 2 setpoint, securing the releas WL-64A ( RB Sump Pump inside isolation valve) close The Floor Drain Tank reached the "Hi Level" setpoint and secured'the release to prevent overflo ANSWER: 046 (1.00) (+1.0)
REFERENCE: LP OP-MC-WE-WL, p. 20, Objective . KA 068000A404- (3.8/3.7)
068000A404 ..(KA's)
1
, _ . - ,. _ , _ . . . , _ . _ , _ _ . . . . - . . . _ _ , . _ _ . _ - - _ , . . . . . _ _ _ - . . ,
.
REACTOR OPERATOR .Page 39'
QUESTION: 047 (1.00)
WHICH ONE (1) of the following components is the largest source of radioactive gas sent to the Waste Gas System (WG) during normal, full-load operations? Recycle Holdup Tanks Volume Control Tank Waste Gas Decay Tanks Reactor Coolant Drain Tank ANSWER: 047 (1.00) [+1,0)
REFERENCE: LP OP-MC-WE-WG, pp. 7-9, Objective 2, KA 071000A405 (2. 6/2. 6)
071000A405 ..(KA's)
QUESTION: 048 (1.00)
WHICH ONE (1) of the'following will. result'from a-loss of power to the detector.of an area radiation monitor, RP-1A Readout Module? Indication will be at full scal Indication will be at minimum scale, Indication'will-be at the TRIP-setpoin Indication will be at the TRIP 2 setpoint, n
i
REACTOR OPERATOR Page 40-ANSWER: 048 (1.00) [+1.0)
REFERENCE: LP OP-MC WE EMF, p. 4 . KA 072000A201 (2.7/2.9)
072000A201 ..(KA's)
_
QUESTION: 049 (1.00)
WHICH ONE (1) of the following conditions will automatically close--the Waste-Gas Discharge Flow Controller (1WG160) when actuated?
- VCT Unit 1 Purge Flow high-alar Waste Gas Moisture Separator high pressure alar EMF 36 (HH) - Unit Vent Activit EMF 36 (L) - Unit Vent Ga ANSWER: 049 (1.00) [+1.0)
REFERENCE: LP OP-MC-WE-EMF, p. 24, Objective ' .101 073000K401 (4.0/4.3)
073000K401 ..(KA's)
,
. _ . . . . . . .
- -.-.-. . . . - .- . - _ - . . - _ . . . _ . _ _ . - _ _ . - . . . . _ - - - - . - . . .
L
,
REACTOR OPERATOR Page 41
i
,
QUESTION: 050 (1.00) .
WiiIC11 ONE (1) .of the following is the MINIMUM Instrument Air (VI) pressure-
-
that will allow the VI to Station Air (VS) cross-over valve - (1VI 820) to REOPEN after it has closed due to low system pressure? ) psig psig ; psig
.
. psig l t
t ANSWER: 050 (1.00) * (+1.0) .i-REFERENCE: ; LP OP-MC-SS-VI, p. 25, KA 078000K402 (3.2/3.5)
.i 078000K402 ..(KA's)' l
,
QUESTION:.051 (1.00) Ji WHICH ONE (1). of the following system pressures will all TliREE -(3) Main Fire pumps be. operating?- psig
, psig
-' psig d- 100 psig i
- . ~ . . . _ ,. . . _ - , , . - . ~ _ . , . . . , . . , .s_, ._ , , , , , , , .. _ ... ,, , _ . . , _ . . . . . . . . . , ,, , , . . , ,, 4 ., . , _ _
_ .
.
.
REACTOR OPERATOR Page 42 ANSWER: 051 (1.00) (+1.0)
REFERENCE: LP OP-MC-SS-RFY, p. 20, Objective . KA 086000K402 (3.0/3.4)
086000K402 ..(KA's)
_
QUESTION: 052 (1.00)
'Given the following conditions:
-
Unit 1 is at 75%.
-
Control rods are in AUT .
- Bank D rods are at 160 steps and stepping out with NO demand signa WHICH ONE (1) of the following actions are to be performed'FIRST per AP/1/A/5500/14, " Rod Control. Malfunctions"? Enter EP/1/A/5000/11.1, " Response to Nuclear Power
-
Generation /ATWS". Trip _the reactor and enter EP/1/A/5000/01, " Reactor Trip'and Safet Injection".
_ Place the CRD bank selctor in MANUAL.- - - Place the CRD bank selector in the CBD positio _
ANSWER: 052 (1.00)- ( +1. 0 )
'
'
~
ma inums -
'd
. .._.. _ _ ._ . . - . . . _ _ _ _ __ ._._ _ . .. _ . . _ _ _ _ m. ~~.~ _ . _ _ . _ _ _ _ .m__.._ _ ... _
l REACTOR OPERATOR Page 43 REFERENCE: l l LP OP-MC-RT-RCO, p. 27, Objective 1 . KA 000001K106 (4.0/4.2)
'
000001K106 . . (KA's)
i QUESTION: 053 (1.00)
WHICH ONE (1) of the following alarms is NOT an immediate symptom of a dropped control rod? ,
, ROD CONTROL NON URGENT FAILURE RPI AT BOTTOM ROD DROP , P/R HI FLUX RATE ALERT P/R CHANNEL DEVIATION ANSWER: 053 (1.00)
v [+1.0) i
!
-REFERENCE: , LP OP-MC-IC-IRE, p. 42, Objective 16 . AP/1/A/5500/14 Rod Control Malfunction, Case II . KA 000003G011 ( 3 . 6 / 3 '. 8 )
000003G011 . . (KA's)
.
._
- ,-.~..h.....,y-
'
-,.--,,. .-,%.- , ..,m,,,.,,, , - , . ~ . , , , , . , . . , . , -, , , h . .. w. .
,m .._h .-,
. _ _ _ _ _ _ _ . _ _ . - _ _ .
,
REACTOR OPERATOR Page 44 QUESTION: 054 (1.00)
Given the following conditions:
-
Unit 1 is at 80% powe Control rods are in Aut A Tave-Tref deviation of 5 degrees F exiat Control rods are NOT movin WHICH ONE (1) of the following immediate actions should be taken? Adjust Tave to within 1 degree of Tref by dilution or boratio _ Place the rod control in manual and verify control rod operability by moving rods in 5 steps, then out 5 step Trip the Unit and enter EP/1/A/5000/01, " Reactor Trip or Safety Injection".
s Place rod control in manual and adjust turbine load to match Tave to Tre ANSWER: 054 (1.00) {+1.0)
REFERENCE:
_ LP OP-MC-IC-IRE, p. 4 0, Objective 16 . AP/1/A/5500/14, Rod Control Malfunctions, Case . KA 000005G010 (3.4/3.6)
000005G010 ..(KA's)
r
- .
. REACTOR OPERATOR Page 45-
!
'!
,
QUESTION: 055 (1.00)
WHICH ONE (1) of the following_ parameters discriminates between a-vapor space and non-vapor space LOCA? Pressurizer level
' Pressurizer pressure PRT pressure
< RVLIS level ANSWER: 055 (1.00) [+1.0]
REFERENCE: LP OP-MC-EP-EP16, p. 10, Objective 3 . KA 000008A212 (3.4/3.7)
000008A212 . . (KA's)
. _ .
-
- mp 'r . 'imew -rie 4 w m ?W t-4 y s'4wi . e- MU-Mi*tFT *$7 T4g,
. _ . _ _ _ . . = _ _ . .. _ . . _ _ . _ __ ._ . . . . . _ . . _ __ _ . - _ . .
,
I
>
REACTOR OPERATOR Page 46 i L
!
>
l QUESTION: 056 (1.00) l Given the following conditions:
-
A LOCA has occurred in Unit RVLIS indicates:
- Upper _ range level is 86%
- Delta + Pressure reading of 80%.
- All NCP's are runnin l WHICH ONE (1) of the following is the level indication used and the reason for its usage under these conditions?- Upper head level because the delta pressure indication is.only -l accurate between-0% and 70% leve Delta pressure level-because both areas are filled with a12 phase mixture of approximately 34% qualit c .- Upper 1 head level because some core _ exit _thermocouples indicate cold -
leg temperature instead of_ hot leg temperature in this. range,
' Delta pressure level because all four NCPs.are runnin i ANSWER: 056 (1.00) * [+1.0) i
,
1 REFERENCE: LP OP-MC-IC-ICM, pp. 17-20, Objective 6 . LKA 000009A110 (4.1/4.1)
000009A110 . . (KA's)
s
,;c..s.- = M, _-.r...,',.vwe- ,ew,,,E--.'w., .*1-c-ee,-r-,-.- . - -
.,.,y - ., - y . -, -,- ,# w , .r - r i w -- e -
we e
.
t REACTOR OPERATOR Page 47 :
i r
QUESTION: 057 '(1.00)
Given the following conditions ;
.
-
A natural circulation cooldown is being performed per :'
EP/1/A/5000/ RVLIS is-NOT available, ,
WHICH ONE (1) of the following parameters provides the first' indication of a-void in the reactor vessel head during a natural circulation cooldown? NCS pressure Incore thermocouple temperature Pressurizer level NCS hot leg temperature ANSWER: 057 (1.00) (+1.0)
REFERENCE: LP OP-MC-EP-EP1, p. 16, Objective 2 . KA 000009A238 (3.9/4.3)'
!
000009A238 . . (KA's) l
-
l
l:
i ..
- -
'
, ....,..._._.4,,.,_.-...,_,,..
-
,, m_ , . . . . . . , . - , .,,,...,,......s, _ . . , - . . , , . -;,..
.
-
_ , . . , -~
. - . - . . _ . . - - - - . _ . . . . - - - - - . . . - - . - . . - - - _ - -
_
. - .
t REACTOR OPERATOR Page 48 ;
i
!
!
QUESTION: 058 (1.00)
i'
Given the following conditions:
- A large break LOCA has occurre ECCS is operating in Cold Leg Recirculation mod NCS pressure is stable at 200 psi L WHICli ONE (1) of the following describes the primary method of decay heat removal? Condensation of reflux boiling in the Steam Generators, Heat is transferred:between the NCS and Steam Generators due 'I to natural circulation flow, Ileat is transferred between the NCS and Steam Generators due to forced circulation flo Heat-is removed-by the ND heat exchanger and-injection of. water from the containment sump while a water / steam mixture flows out from the brea ANSWER: 058 (1.00) [+1.0)
REFERENCE: LP OP-MC-TA-AM, p. 63, Objective-9 . KA 000011A111 (4.2/4.2)
000011A111 ..(KA's)-
,
,
a., - _ , , , , _ . . , . , _ __ - . . _ , , . , . . - . - . . . , _ _ , _ _ _ , _ . _ . . _____.u._,.,-.-,-,._...-_-u-
. _ . . _ _ _ . ~ . _ _ _ . . _ . _ . . _ _ . . _ _ _ . _ . _ _ _ . . _ . _ . _ . _ . -
- _ . _ _ . _ _ . . . _ - _ _ . . t REACTOR OPERATOR Page 49
!
l QUESTION: 059 (1.00)
WHICH ONE (1) of the following is the reason for ensuring the NV pump l recirculation valves are closed when NCS pressure is less than 1500 psig, per !
EP/1/A/5000/02 "High Energy Line Break Inside Containment"? i
, To prevent overpressurizing the recirculation line at maximum NV !
pump discharge pressur l To ensure maximum safety injection flow is directed to cor ! To prevent overheating the NV pump during accident condition ! To help diagnose the location of the leak by isolating a potential ;
'
leakage flowpat .
ANSWER: 059 (1.00) -; [+1.0)
.;
REFERENCE: LP OP-MC-EP-EP2, p. 21, Objective 2C.- [ KA 000011K307 (3.5/3.6) i
.
000011K307 .,(KA's)
.
d
,
f
'
. - . . . , . . . . , . . J.....ye,.--,,,,.._...;.,-,,-m_-_,m.,,m_4.,,-,--.,,,_c;- ...,y..L,m,,.,m _, . _ .. ...?..- . . : . . , i _. . s . .
,
REACTOR OPERATOR Page 50
~ QUESTION: 060 (1.00)
-Given the following conditions:
- The reactor has tripped from 100% powe NO reactor coolant pumps are runnin Natural circulation has been in progress and stabilize WHICH ONE (1) of the following verfles that natural circulation is still-taking place? NC loop Hot Leg temperature is 605 degrees F and increasin S/G pressure is 900 psig and increasin Core Exit T/C's are 600 degrees F and increasing, NC system subcooling is 10 degrees and increasin ANSWER: 060 (1.00) [+1.0)
REFERENCE:
1, LP OP MC-EP EP1, p. 15, Objective 2 . EP/1/A/5000/1.1, Natural Circulation Cooldown, Fold out pag . 0000015A121 (4.4/4.5)
000015A121 ..(KA's) -;
.
.
b b
?
_
B
'-
. . . - - . . - ~ . . , . . _ . , _ . . . _ - , . _ . . _ . . _ . , . . . . _ . . . - ~ _ - - . _ . _ . _ . _ _ . - . . , _ _ _ _ - - _ . _ . _ . _ _ . . ~ . ~ . _ . . _ . _ . ~
REACTOR OPERATOR Page 51 QUESTION: 061 (1.00)
WHICH ONE (1) of the following is the MINIMUM NCP stator winding temperature that requires an NCP to be stopped following a loss of KC flow according to AP/1/A/5500/08, Case II, "NC Pump Motor Malfunction'? degrees degrees degrees degrees ANSWER: 061 (1.00) (+1.0)
REFERENCE: LP OP-MC-PS-NCP, pp. 27 & 35 , Objective 1 . AP/1/A/5500/08, Case II, "NC Pump Motor Malfunction", p. . KA 000015A210 (3.7/3.7) 000026A107 (2.9/3.0)
000015A210 ..(KA's)
-
-- - --
_- ..
.-.
REACTOR OPERATOR Page 52 QUESTION: 062 (1.00)
Given the following conditions:
-
NC PUMP SEAL INJ LO FLOW alarm is LI Pressurizer level is DECREASIN NC PUMP CTRL LEAKAGE LO FLOW alarm is LI REGEN HX LETDOWN HI TEMP alarm is LI WHICH ONE (1) of the following is the FIRST procedure that should be implemented?
' Loss of Charging
' Loss of Seal Injection Loss of Letdown
> Loss of Component Cooling Wate ,
ANSWER: 062 (1.00) , [ + 1. 0)
REFERENCE: LP OP-MC-PS NV, p. 59, Objective 10 .- AP/1/A/5500/12,- Case II, . KA 000022G010 (3.5/3.4) 000022G011 _ _(3,3/3.6)
000022G010 . . (KA's)
.
i r m s-~ n n, r ,e-,~, n-sv,,ew-~ sm,, ,wv- vv..-+v-<,e r - > < - - n A~ 5 ,- du ,-,,,>--ane. +w , - ~ - - - - - - -. Sw- -w--o- --- ~ ------n-. , -rs
_ _ _ _ _ _ _ _ _ _ ___ _ _
. . . . .
REACTOR OPERATOR Page 53 QUESTION: 063 (1.00)
Given the following conditions:
-
The reactor has trippe Three (3) rods are NOT fully inserte EP/1/A/5000/1.3 " Reactor Trip" is being performed, hHICH ONE (1) of the following is the MINIMUM required to meet the emergency boration requirements? ppm of boric acid tota I ppm of boric acid tota ppm of boric acid tota ppm of boric acid tota ANSWER: 063 (1.00) [+1.0)
REFERENCE: LP OP-MC-EP-EP1, p. 21, Objective 4 . KA 000024A205 (3.3/3.9)
000024A205 ..(KA's)
i
, - . .
REACTOR OPERATOR Page 54 QUESTION: 064 (1.00)
Given the following conditie s:
-
Unit 1 is at 80% powe AP/1/A/5500/38, " Emergency Boration" is being implemente WilICH ONE (1) of the following is a positive indication that emergency boration is flowing into the NC system? CONTROL ROD BANK LO-LO alarm is li Control rods are stepping ou Boric acid pump "A" is running, Boronometer is decreasin ANSWER: 064 (1.00) [ 41. 0 )
REFERENCE: LP OP-WC-PS-NV, Objective . AP/1/A/5500/38, Emergency Boration, . KA 000024A201 (3.8/4.1)
000024A201 ..(KA's)
. . .
_ _ _ _ _ _ _ ._ _ _ _ _ _ _ _ _ _ - __ - _ _ _ _ _ _ _ _ __ _ _ . _ _ __ _ _ _ _ _ __ _ _ __ _ _ . _ _ . ___ _ _
-
r
- REACTOR OPERATOR Page 55 I
- l QUESTION: 065 (1.00)
Given the following conditions:
!
-
The reactor vessel head is remove Reactor vessel upper internals are installed in-the reactor. vesse Water level in the NCS indicates 4 inches during mid-loop operation ND-1B and ND-2A (NC loop "C" to ND isolation) are ope NCS temperature is 140 degrees ,
- BOTH ND pumps are operating while train realignment is in progres BOTH ND pumps begin cavitatin ,
WHICH ONE (1) of the following explains why cavitation occurred in this situation?
- The ND pumps lost suction due to air entrainment because level is below the top of the hot leg The ND pumps lost suction because an inadequate vent path:has created a vacuum on the NC The low NCS level allows the steam generator U tubes to drain intermittently causing a large amount of noncondensible-gas to be-entrained in the NC Minimum ND pump flow has' heated pump recirculation flow and caused i steam binding of the pumps, j ANSWER: 065 (1.00) (+1.0]
i REFERENCE: LP OP-MC-PS-ND, p. 22, Objective 11 .- KA 000025K1011(3.9/4.3)
000025K101 . . (KA's)-
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REACTOR OPERATOR Page 56
.
QUESTION: 066 (1.00)
-Given the following conditions
- Unit 1 is at 25% powe The controlling pressurizer pressure channel I fails HIGH.-
-
The pressurizer spray valves and PORV-NC34 OPEN Pressure has decreased below 2170 psig, PORV-NC34 is OPEN and will-NOT manually reclos Spray valve NC-27 is OPEN and will NOT manually RECLOS WHICH ONE (1)-of the following must be done after selecting a backup control channel per AP/1/A/5500/11, Pressurizer Pressure Anomalies? Close the PORV block valve, trip the "B" NC Close the PORV block valve, energize all pressurizer-heaters, trip the "A" NC Close the PORV block valve, trip the Reactor, trip-the "D" HC Trip the Reactor, initiate S ANSWER: 066 (1.00) [+1.01 REFERENCE: LP OP-MC-PS-IPE, pp. 41-42, Objective S . AP/1/A/5500/11, pp. 2-3, KA 000027A215 (3.7/4.0)
,
000027A215 ..(KA's)
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. . . . . . ,
REACTOR OPERATOR- Page 57 QUESTION 067 (1.00)
'Given the following conditions:
- The plant is at 50% powe Auctioneered Tave fails HIG Pressurizer level control is in AUT Assume no oparator actio WHICH ONE (1) of the following is the effect on pressurizer level? Decreases to the point of letdown isolatio _ Decreases to 25% and stabilize Increases to 61% and stabilizes, Increases to the point'of reactor tri ANSWER: 067 (1.00) (+1.0]
REFERENCE: LP OP-MC-PS-ILE, p. 8, Objective 1 . KA 000028A202 (3.4/3.8)- _
000028A202
- -
..(KA's)
,
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. _ _ _ . _ _ _ _ . . _ _ _ _ _ _ . _ _ _ . _ . _ _ _ _ _ . _ _ _ _ _ _ _ _ _ . . _ _ .
_ _ _ _ - _ _ _ _ _ - __ _ _ _ _ _ _ _______ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .
!
REACTOR OPERATOR Page 58- '
. QUESTION: 068 (1.00) ;
WHICH ONE (1) of the following is the reason for ensuring that NCS pressure is- {
less than 2335 psig in the immediate actions of EP/1/A/5000/11.1, " Response to i Nuclear Generation /ATWS"? ! To prevent the rapid NCS over pressurization transient expecte *
with most ATWS event To minimize primary to secondary leakage in case of the most limiting ATWS event, a SGTR, until other recovery actions can be take To allow.enough borated water to flow into the NCS to ensure the ,
addition of negative reactivity to the cor ; To begin a controlled cooldown and depressurization, thereby minimizing positive reactivity feedback via a negative MT ANSWER: 068 (1.00) [+1.0) ,
REFERENCE: LP OP-MC-EP-EP11, , Objective 2 . KA 000029K312 (4.4/4.7) _ _ K312 . . (KA's)
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REACTOR OPERATOR Page 59 l
QUESTION: 069 (1.00) l l
'
WHICH ONE (1) of the following actions is the FIRST required by j EP/1/A/5000/11.1, " Response to Nuclear Power Generation /ATWS," if the turbine .
will NOT trip or manually runback? 'frip the generator output breakers, Close the MSIV's and bypasse ,
, Trip turbine from main turbine front standar Stop both DEH pump ANSWER: 069 (1.00)
- [+1.0)
REFERENCE: ;
l '. LP.OP-MC-EP-EP11, Objective 2 . LP OP-MC-EP-EPF, pp. 17-18, Objective . EP/1/A/5000/11.1, " Response to Nuclear Power Generation /ATWS", p. . KA 000029G010 ( 4.5/4.5) .
000029G010 ..(KA's)
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REACTOR OPERATOR Page 60-QUESTION: 070 (1.00)
Given the following conditions:
-
Unit 2 is in MODE Reactor power is 10 E-08 amps, taking critical dat N-35 intermediate range instrument power fuses blow due to an internal faul l WHICH ONE (1) of the following is the appropriate action? Enter EP/1/A/5000/01, " Reactor Trip or Safety Injection," at Step Hold power at 10 E-08 amps until repairs are made, 7 Insert rods to lower neutron flux level-to a value within the source rang Place the N-35 Level Trip switch in the BYPASS positio .
ANSWER: 070 (1.00) ; (+1.0)
r t
REFERENCE: LP OP-MC IC-ENB, p. 29, Objective 1 . KA 000033A207 (3.9/4.2)
000033A207 ..(KA's)
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_
REACTOR OPERATOR Page 61 QUESTIONt'071 (1.00)
WilICH ONE (1) of the following is NOT a symptom of a Steam Generator Tube Leak? Increase in frequency of auto makeup to the VC Main feedwater reg valve position trending ope Feedwater flow to S/G "A" decreasing.
' EMF-33 COND AIR EJECT EXil HI RAD alar ANSWER: 071 (1.00) [41.0)
REFERENCE:. LP OP-MC-PS-NC, p. 49, Objective IS . AP/1/A/5500/10, NC System Leakage Within Capacity of Both NV Pumps, Cas , Steam Generator Tube. Leakag . KA 000037A206 (4.3/4.5)
000037A206 ..(KA's)
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_ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ - _ _ _ .
I REACTOR OPERATOR Page 62 QUESTION: 072 (1.00)
Given the following conditions:
Unit 1 is at 75% power
- Steam Generator A has an identified primary to secondary leak
- of 30 gallons per day (calculated 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> ago).
- Radiation alarms are received on the Condenser air ejector and Steam Generator sample lin Pressurizer level is 23% and NCS pressure is 1950 psig, both parameters are DECREASING rapidl WHICH ONE (1) of the following is NOT an immediate action that you are -
requireo to take? Start additional charging pumps to determine the size of the ,
lea \ Initiate a controlled shutdown per OP/1/A/6100/02, " Controlling Procedure for Unit Shutdown." Turn on all available heaters to maintain pressur Initiate a manual reactor trip and safety injection and enter EP/1/A/5000/01, " Reactor Trip or Safety Injection".
,
ANSWER: 072 (1.00) -
(+1.0)
- REFERENCE: LP OP-MC-PS-NC, p. 49, Objective 15 . AP/1/A/5500/10, "NC Syst'm Leakage within Capacity of Both NV Pumps",
Case I.
9 KA 000038G011 (4.2/4.3)
000038G011 ..(KA's)
. . . .
REACTOR OPERATOR Page 63 QUESTION: 073 (1.00)
WHICH ONE (1) of the following symptoms differentiates between a LOCA and a Main Steam Line break inside containment? Increasing containment radiation levels, Increasing containment sump level Increasing containment pressure, Decreasing pressurizer pressur ,
ANSWER: 073 (1.00) [+1.0]
REFERENCE: LP OP-MC-EP-EP2, p. 17, Objective 1 . KA 000040A203 (4.6/4.7)
000040A203 ..(KA's)
.
(1.00)
-
QUESTION: 0 14 WHICH ONE (1) of the following accidents presents the GREATEST potential for a Pressurized Thermal Shock (PTS) condition? Steam Line Break Excessive Feedwater Event Large LOCA Main Feedline Break l
l
_
. -. .. .- ..-. .~_ . _ . -- . .- - .-
- REACTOR' OPERATOR .Page464
.
-
,
'
.
ANSWERt- 074 (1.00) [+ 1. 0)
- REFERENCE: LP OP-MC-TA-PTS, pp. 31-42, Objective 1 < KA 000040K106 (3. 7/3. 8 )
000040K106 ..(KA's)
QUESTION: 075 (1.00)
Given the following conditions:
-
Unit 1 is at 70% powe CONDENSER LO VACUUM (PRE-TRIP) alarm is LI Condenser vacuum has been decreasing for the past. fifteen (15)
minute WHICH ONE (1) of the following is the condenser' vacuum at which a Reactor / Turbine Trip will FIRST be initiated per AP/1/A/5500/23,;" Loss '
of Condenser Vacuum"? inches Hg inches Hg inches Hg inches Hg (1.00)
'
ANSWER: 075_ [+1.01
,
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. . _ , . . _ . - -
. - - . - . . -_-- --- . . - _ - - - . . - . - . . - -- . ~
,
REACTOR OPERATOR ' Paget- 65'
REFERENCE:-
11.- LP OP-MC-MT-MT, p. 51,-OM ective 2 . AP/1/A/5500/23, " Loss of Condenser Vacuum", .
1 KA 000051A202 ( 3 . 9 /4.1)
=000051A202 ..(KA's) ,
QUESTION: 076- (1.00)
WHICH ONE (1)'of the following statements indicates why CA flow rate-is procedurally restricted to 100 GPM when recovering a steam generator
- level if the level has fallen below 9% wide range indication? Minimize thermal' stress conditions on steam generator-components, Minimize NCS cooldown rate and prevent resultant therma stress on NCS_ components, Ensure NCS inventory demand does not exceed normal charging-pump capacit Ensure pressurizer level transient does not result in pressure transient that would actuate S ANSWER: 076 (1.00)
z [+1.0}.
. REFERENCE: y LP-OP-MC-EP-EP13, p. 21, Objective 6 .- KA 000054K102 (3.6/4.2)
-000054K102- ..(KA's)
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.-REACTOR OPERATOR _
_
Pag'e 66:
QUESTION: 077- (1. 00)
WHICH ONE (1) of-the_following is the reason that cooldown is limited while:
. performing a cooldown and depressurization per EP/1/A/5000/09, " Loss of'All-AC; Power"? To prevent the injection of nitrogen from the.-cold leg accumulators.- To minimize'the thermal shock to the NCP pump seals when cooling.is restored, To-minimize the amount of seal leakage in the event of a seal failure, To prevent the possibility of recriticality from occurrin ANSWER: 077 (1.00) [+1.0)
REFERENCE: LP OP-MC-EP-EP09, p. 10, Objective 2 ,. KA 000055K302' (4.3/4.6) -
000055K302 ..(KA's)
I
. - _ - -
'
REACTOR OPERATO Page 67~
,
QUESTION: 078 (1.00)
'Given the following conditions:
-
A loss of all AC power has occurre .. ..
-
Steps are being performed to establish NC pump seal injection from 1 ETA room per EP/1/A/5000/09, " Loss of-All~AC-Power".
WHICH ONE (1) of the following will occur when 1EMXA-4 is switched to.its alternate power supply? Standby makeup pump isolation valves (1NV-842AC,.1NV849AC) will'be l transferred to the SSF.
' Control of the pressurizer spray valves (1NC-27, INC29) will be-transferred to the Auxiliary Shutdown Pane Letdown isolation valve (NV-1A) will automatically ope ' Turbine driven CA pump to S/G "B" isolation valve (CA-54A) will clos .
ANSWER: 078 (1.00) [+1. 0)
REFERENCE: EP/1/A/5000/09, " Loss of All AC Power",= Enclosure 2, p. ' 2 '. .LP OP-MC-EP-EPC9, Objective 2 . KA 000055A106 ( 4 .1/4 . 5 )
000055A106 ..(KA's)
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~ REACTOR OPERATOR LPage:68
.
c
- QUESTION: 079. (1.00) ,
'
'Given the-following conditions: -
-
Unit 1 is at 100% powe ETB experiences a loss of offsite powe B Train components are in servic WHICH ONE (1) of the following is the reason that Unit 2 is notified to start the 2A RN (Nuclear. Service Water) pump? The blackout signal load sheds the 2A pump while the Unit _1 D/G comes up-to speed.
, The blackout signal causes train separation andLflow may-be lost'to the essential headers, The blackout signal load sheds the 2A pump while its suction Lwitches to the assured sourc The blackout signal causes train separation and_ flow may-be lost to-the nonessential header ANSWF3: 079 (1.00) [ + 1' . 0 ]
'
REFERENCE:
~ AP/1/A/5500/07, Loss of Electrical _ Power, Case II, p. 2 . . .KA 000056K302 (4.4/4.7) 000056A107 (3.2/3.2).
J 000056A107 000056K302 ..(KA's)
. . .-
. ..
- - - . . .- -- - - - ~- . . - . . . - . - . ... _ . - . - - .
REACTORLOPERATOR Page 69
.,
QUESTION: 080 (1.00)
Given.the following conditions:
-
A Waste Monitor Tank. release is in progres EMF-49. (LOW SAMPLE FLOW) has been in alarm for 3 minutee and will NOT rese Double verification of. valve alignment has NOT been performe WHICH ONE (1) of the following is the reason for declaring EMF-49 inoperable
.and suspending the release? To ensure that the radiation detector does not become saturated-with radioactive particulates during the low flow condition and'
require replacement.
, The LOW SAMPLE FLOW alarm should have cleared within 2.5 minutes after initiating the release, To ensure that the radioactive liquid release will be monitored before passing the discharge isolation valve.
, To ensure that'an unmonitored release of EMF-49 calibration-fluid-is not taking place.
E ANSWER: 080 (1.00) [+1.0]
REFERENCE: LP OP-MC-WE-RLR, p. 13, Objective . KA 0000059K303 (3.0/3.7)
000059K303- ..(KA's)
.
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REACTOR OPERATOR Page 70 QUESTION: 081 (1.00)
Given the following conditions:
-
Unit 1 is in MODE Refueling is in progres The containment evacuation alarm is soundin WHICH ONE ( '. ) of the following radiation monitors activates the containment evacuation alarm? EMF-16 (Reactor building refueling bridge), EMF-17 (Spent fuel building refueling bridge). EMF-38 (Containment particulate low range). EMF-40 (Containment iodine monitor).
ANSWER: 081 (1.00) [+1.0]
REFERENCE: LP OP-MC-WE-EMF, pp. 16 & 28, Objective . KA 000061A101 (3.6/3.6) ;
000061A101 ..(KA's)
a
-REACTOR OPERATOR Page 71
.
QUESTION: 082 (1.00)
Given the following conditions:
-
Unit 1-is-at.100% powe An unisolable rupture of the Instrument Air -(VI)- header has occurre WHICH ONE (1) of the following conditions and associated reason'will cause the-reactor to trip following a total loss of instrument air? The main feed regulating valves will close causing a steam-generator low level tri The letdown isolation valves will close and the pressurizer will fill up causing a pressurizer high level tri The pressurizer spray valves will fail open causing a pressurizer-low pressure tri 'd , The auxiliary spray valve will fail open causing a pressurizer low pressure tri ANSWER: 082 (1.00). [+1.0)
REFERENCE: EP/1/A/5500/22, p. 3, Objective . KA 000065K308 (3.7/3.9)
000065K308 ..(KA's)
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-
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_
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, .
. _-
.
- _ _ _ _ _ _ _
REACTOR OPERATOR Page 72 t
QUESTION: 083 (1.00)
WHICH ONE (1) of the following is the purpose of procedure AP/1/A/5500/17,
" Loss of Control Room"? It describes the procedure for cooling down the NC system from Hot Standby to Cold Shutdown when the control room is uninhabitable, It describes the steps to be taken to prepare the plant for Hot shutdown, followed by Cold Shutdown after a fire at the Auxiliary Shutdown Pane It describes the steps required to take the plant from Hot Standby -
to Cold Shutdown following a fire event that renders the control room and auxiliary shutdown panel unusable, It describes the steps to be taken to achieve and maintain Hot Standby in the event of control room evacuation for reasons other than fir ANSWER: 083 (1.00) (+1.0)
REFERENCE:
~ LP OP-MC-CP-SS, pp. 8-9. Objectives 1A,B,C, . KA 000068G012 (3.8/4.0) ~
% 000068G012 ..(KA's)
4
. _ . _ _ _
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REACTOR OPERATOR . Page.73' ;
..
QUESTION: 084 (1.00)
Given the following conditions:
--
The -Standby Shutdown Facility (SSF) has 'been actuated due to a security event.-
-
The SSF diesel generator has been starte WHICH ONE'(1) of the following trips is available in the. current SSF-diesel generator mode of operation? Low lube oil pressure High jacket water temperature Engine overspeed Jacket water low pressure _
ANSWER: 084 (1.00) [+1.0) ,
REFERENCE: LP OP-MC-CP-AD, p. 14, Obj ective 6 . -KA 000068A131 (3.9/4.0)
.
000068A131 ..(KA's)
J .
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.
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REACTOR OPERATOR- :Page 74: "
'
' QUESTION: 085_ -(1.00)
WHICH ONE (1)'of-the-following conditions would VIOLATE Containment Integrity-if the plant ascended into_ MODE 4"?.
' IVQ-1A (Cont Air Release Inside Isol) has its air supply removed and has failed close . KF-122 (Fuel Transfer Tube) .is fully opened, but can be. manually close KC-429B (Rx Bldg Draain Hdr Inside Isol) has-lost its-power supply, _
but is closed . RN-253A (RB Non ESS Sup Inside Isol) failed its stroke timing test, but can be closed from the-control room.
>
ANSWER: 085 (1.00) [41.0)
.
REFERENCE:- . Technical Specification-3.6.1.1, p. 3/4 6- . Technical Specification 3.6.1.2, p. 3/4 6- . LP_OP-MC-ADM-TS, p . _ 9, Objective-2 . KA_000069A201: (3.7/4.3')
000069A201 ..(KA's)
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. - _ - . . . _
Page'75
'
REACTOR OPERATOR -
QUESTION: 086 (1.00)
Given the following conditions:
-
Unit 1 tripped from 100% powe NCS pressure rapidly dropped to below 1000 psi SI actuated, and started injectio Containment pressure rapidly increase Steam generator pressures and levels remained close to-normal-post trip value Safety injection flow has been reduce Source range nuclear instrumentation' energized, and initially showed a decreasing count rat Count rate turned and increased, stabilizing at 2 decades higher than a normal shutdown 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> into the acciden WHICH ONE (1) of the following is the reason for the higher than normal source range reading?
' The SI water is cool, increasing the moderating effect and fission count rate over the amount normally expecte As the core void fraction approaches 100%, the fission rat increases due to boron displacement from the cor Core boiling is occurring, resulting in a decrease in boro concentration in the lower part of the core, increasing fission rat Downcomer voiding is occurring, allowing more neutrons to_ leak out-of the core.
ANSWER: 086 -(1.00)
'd.- (+1.0]
REFERENCE:
000074A207 ..(KA's)-
. -. . , . - .
i REACTOR OPERATOR . Page_76
-
-QUESTION: 087 (1.00)
Given the:following conditions:-
-
A LOCA has occurred.in Unit The NCP's are runnin RVLIS indicates the upper head and upper plenum'are draine WHICH ONE (1) of the following is the status of the coolant'that RVLIS-is; exposed to? Only stea Steam or a two-phase mixture, Completely covered with water in the plenum area onl Only wate ANSWER: 087 (1.00) [+1.0)
REFERENCE: LP OP-MC-TA-AM, pp. 26-28, Objective 1 . KA 000074A101 (4.2/4.4)
000074A101 ..(KA's)
QUESTION: 088- (1.00)
WHICH ONE (1) of the-following positions has direct responsibility (for issuance and recall of. yellow " HOLD" tags?. '
, Operations Superintendent Operating. Engineer Shif t: Supervisor
' _ Station Manager
,
..
y
.,. .. . .
_
- . . . -. ... - -. . . - . .- . - . . .
. REACTOR ~ OPERATOR . Page 77c
,
ANSWER: 088 (1.00) (+1.0]
-REFERENCE:
l'. Station Directive 3.1.19, p. 42, KA 194001K102 (3.7/4.1)
294001K102 ..(KA's)
QUESTION: 039 (1.00)
.WHICH ONE (1) of the following positions will' assume the-recponsibilities.of
. Emergency Coordinator when the Technical Support Center-is activated? Operations Superintendent Shitt Supervisor Station Manager Vice President Nuclear Operations
,
ANSWER: 089 (1.00)
"
- [+1.0)
REFERENCE:-
- LP OP-MC-EP-EMP, p. 15, Objective ~
' KA 194001A116 (3 .1/4. 4 )
194001A116 ..(KA's)
.
N'
p +
. .- - . - - - , . - - . . ~ - . . - - - . - - . ..
i REACTOR OPERATO Page'_78 ,
QUESTION: 090 (1.00)
WHICH ONE (1) of the following is the MAXIMUM notification and accountability
-_ time requirement per the Emergency Plan for a-General Emergency?-
~
,
a, The state and counties must be notified within 15 minutes; individuals on site must be accounted for within 15 minutes, The state and counties must be notified within 30 minutes;-
individuals on site must be accounted for within 30 minutes, The state and counties,must be notified within 30 minutes; individuals on site must be accounted for within'15 minute The state and counties must be notified within 15 minutes; individuals on site must be accounted for within 30 minute ANSWER: 090 (1. 0 0 ) _ [1.0]
REFERENCE: LP OP-MC-EP-EMP, p. 23, Objective 1 . Station Directive 3.8.1, Site Assembly / Accountability,= . KA 194001A116 ( 3 .1/ 4 . 4 ) Facility Bank Question EPEMP009 (modified)
194001A116 ..(KA's)-
- QUESTION: -091 (1.00) ,
WHICH ONE (1) of the-following is a duty of a Fire Watch? Reporting hourly status to the Safety and Health Services section.- Closing a blocked open fire door upon discovery of a fire, Logging area conditions every 15 minutes, Remaining in the area for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after an actual-fire-has been extinguishe .- ,
. - - - - . . ..- - - . - - . - _-
.-
REACTOR OPERATOR Page 79 ANSWER: 091 (1.00) (+1.0)
REFERENCE: Station Directive 2.11.2, Fire Protection and Surveillance, pp. 3- . LP OP-MC-ADM-SD, Objective 10F, KA 194001K116 (3.5/4.2)
194001K116 .(KA's)
_
QUESTION: 092 (1.00)
WHICH ONE (1) of the following is NOT a responsibility of an Operations Group when a fire barrier is found to be inoperable? Ensuring that the daily and weekly fire door procedure is properly complete Logging inoperable fire barriers in the Technical Specification action log boo Writing work requests to repair fire doors, Determining whether an hourly or continuous fire watch is require _
ANSWER: 092 (1.00) (+1.0)
REFERENCE: Station Directive 2.11.5, Technical Specification Fire Barriers, pp. 3- . LP OP-MC-ADM-SD, Objective 10 . KA 194001K116 (3.5/4.2)
194001K116 ..(KA's)
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'RE'CTOR-OPERATOR A Page 80 l
QUESTION: 093 (1.00)
WHICH ONE (1) of the following individuals may be issued the High Radiation
- Master Key _(#12) from the Shift Support Technician? The IAE technician performing routine surveillance The Reator Operator at,the controls (OAC). j The Operator assigned to Auxiliary Building rounds, The Shift Operations Manager.
LANSWER: 093 (1.00) [+1.0)
REFERENCE: OMP 2-16, Key Control, . IUk 194001K105 ( 3.1/3. 4 )
194001K105 ..(KA's)
l QUESTION: 094 (1.00)
-WHICH ONE (1) of the'following is a requirement when using a HUMAN RED TAG-as-
.a control for a pump breaker?
a .- The Human Red Tag may transfer responsibility to another qualified-individual as long as-the~ individual agrees to the responsibilit The Human Red 1 Tag:shall verify the safe condition of a_ pump-that ha been isolated for-seal. replacement prior-to allowing any. maintenance to be performe The Human Red Tag shall-have-no other responsibilities'while acting;
.in this capacit The Human Red Tag must perform the independent verification when.the-component is-returned to servic .
REACTOR OPERATOR Page 81 ANSWER: 094 (1.00) [+1.0)
REFERENCE: Station Directive 3.1.19, Safety Tags, pp. 26-2 . LP OP-MC-ADM-SD, Objective 10 . KA 194001K102 (3.7/4.1)
194001K102 ..(KA's)
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QUESTION: 095 (1.00)
WHICH ONE (1) of the following describes how to verify the position of a manually operated THROTTLE valve'on a system that is required to be in operation? Move the valve slightly in the closed direction and then return it to its required positio Completely close the valve and then reopen it to the required positio Inspect the last valve lineup sheet for verification signature and compare recorded valve position with the required positio Observe the position of the valve stem, position indicator, or flow
-
indication and compare it to the required positio ANSWER: 095 (1.00) [+1.0]
REFERENCE: OMP 1-8, Valve and Breaker Identification, p. . LP OP-MC-ADM-OMP, Objective 9 . KA 194001K101 (3.6/3.7)
194001K101 ..(KA's)
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REACTOR OPERATOR Page 82 QUESTION: 096 (1.00)
WHICH ONE (1) of the following types of radiation is measured by a self reading pocket dosimeter (SRPD) ? Alpha Beta Gamma Neutron
___
ANSWER: 096 (1.00) [+1.0]
REFERENCE: LP OP-MC-RAD-FRP, p. 54, Objective 2 . KA 194001K103 (2.8/3.4)
'. J 4 001K103 ..(KA's)
(1.00)
~
QUESTION: 097 WHICH ONE (1) of the following describes the PREFERRED method of contamination frisking for personnel that are exiting the RCA? Use a PCM monitor and Small Article Monitor (SAM). Perform a 40 second hand and foot frisk and then use a PCM monitor, Perform a three minute whole body frisk and then a 40 second hand and foot fris Perform a 40 second whole body frisk and then use a SAM monitor.
- -- _ _ - _ - _ - - _ - _ _ _ _ _ _ _ _ _ - _ - _ _ _ _ _ _ . - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -
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REACTOR OPERATOR Page 83 ANSWER: 097 (1.00) [+1.0)
l REFERENCE: LP OP-MC-RAD-HPM, Objective 3 . RP Manual Section 2.3, Exhibit 2.3-2, Frisking Policy, . KA 194001K103 (2.8/3.4)
194001K103 ..(KA's)
QUESTION: 098 (1.00)
Given the following conditions:
-
The RO is in the control room performing a surveillance procedur A local operator calls and informs the RO that he has completed a step as requeste WHICH ONE (1) of the following describes the process to complete procedural step sign-off? The local operator initials the step on a working cop The RO initials the step as if he completed i The RO puts the local operator's initials first, then tF, RO initials with the notation VIA PHON .* The RO initials first, then the local operator 4.4tials upon return to the control room.
ANSWER: 098 (1.00) [+1.0)
REACTOR. OPERATOR Page 84J REFERENCE:
' 1. _ LP OP-MC-ADM-OP,'p. 12, Objective .- KA 294001A102 ( 4 .1/ 3 . 9 ) -
194001A102- ..(KA's)-
-QUESTION: 099 (1.00)
WHICH ONE (1) of the following is the responsibility of Operations personnel'
when emptying the Waste Oil Storage Tank (WOST) in accordance with Station Directive 2.4.3, " Hazardous Waste Management Program"? Sign the bill of lading and give it-to the driver as authorization for offsite shippin Sampling the WOST prior to shipping the waste oil offsite, Notify the Waste Disposal Company to arrange for a tanker: truck, Accompany the tank truck into the protected area to receive the waste oi ANSWER: 099 (1.00)- (+1.0] q
--REFERENCE: Station Directive 2.4.3,-p. 9, Objective 10 L KA 194001A112 (3.1/4.1)
'194001A112- ..(KA's)
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. REACTOR OPERATOR Page 85 QUESTION: 100 (1.00)
WHICH ONE (1) of the following identifies an out-of-service. point on the Operator Aid Computer (OAC)? A computer point identification number that is FLASHING.- A computer point identification number that is RE An asterisk (*) following the computer point identification number.' An "X" following the computer point identification number .
_
ANSWER: 100 (1.00) [+1.0)
REFERENCE: McGuire Simulator KA 194001A115 (3.1/3.4)
194001A115 ..(KA's)
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(********** END OF EXAMINATION **********)
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/L'( e C u o e ') ;7 . ] o 7 8]a.1/e~ kegun/ Enna PRINT NAME PROG, ID: OP.MC LRQ SIGNATURE NRCMU SSE 05(SRO)
SSN Prepared by:3 SitIFT DATE REVIEW / INITIAL f
Ql 6 i
L bD (
LICENSED REQUAL ANNUAL EXAMINATION SUBJ ECT: NRCMU-SSE-05(SRO)
Total Points: 15.00 Total Questions: 15
- INSTRUCTIONS *** Use NO 2 PENCIL onl . Fill in the appropriate information on the TEST COVER SHEE . Ask the test monitor instructor about any questions which are not clear to_you, Circle the correct answer on each question'of this exam,- When finished with exam, read the "non-compromise statement" an sign the TEST COVER SilEE NON-COMPROMISE STATEMENT:
"My Signature on this form is my declaration that the responses given on the attached test or exam are entirely my ow It further declares that I am aware that I am subject to termination from the training program immediately and in addition, will be subject -
to further disciplinary action up to and including discharge from the company for cheating and/or compromising on exams / tests / quizzes."
___ _
.-_ .. ,
1 FEEDWATER SYSTEMS CFCFR06 1 Pt(s) Civen the following conditions:
Unit 1 is at 35% turbine load NO power changes have been made in the last hour-Turbine Impulse Pressure Channel 1 (ISMPS$213) fails HICH Which of the following describes the AMSAC system response? AMSAC' remains blocked because turbine load is'less than 40% on Turbine Impulse Channel I _ AMSAC will unblock, but can be blocked by depressing the
~
-block pushbutto AMSAC will unblock and cannot be blocked.since Turbine-Impulse Channel 1 is greater than 40% nMSAC remains blocked since Turbine Impulse Channel I-does not input AMSA ANSWER: A MISCINFO:
REFERENCES: OP/1/A/6100/10B 3-26-91 LESSON: OP MC CF-CF TASK: MO 2313 OBJECTIVES: LPRO OBJ: 16' TIME: 3 MINUTES LPS0 OBJ: 16-KA059000 K3.02 3.6/ REV. DATE: 102/24/92
4' $ g d '
2 STM GEN LEVEL CONTROL CFIFER06 1 Pt(s) Unit 1 is at 75% RTP with Control Rods in manual'. 'The'"S/G B Lo Lo Level' Alert" annunciator alarm is received (1AD4-F2) .
The operator finds "B" S/G 1evel Channel'III at 01. All other indications were norma This-failure will: Result in an AMSAC Actuation Not reposition "B" S/G feed reg. valves Cause "B".S/G feed reg. valve to open Cause "B" S/G feed reg. valve to close ANSWER: B
- MISCINFO:
REFERENCES: OP/1/A/6100/10E .04/02/91
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LESSON: OP-MC-CF-IFE TASK: MO-6308 OBJECTIVES : LPRO OBJ : 10 _ TIME: 3_ MINUTES LPS0 OBJ: 10 KA059000 A2.11 3.0/ REV. DATE: 11/10/92
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3 STM GEN LEVEL CONTROL CFIFER08 1 Pt(s) With Unit 1 at 50% RTP, Channel 42 of Nuclear Instrumentation fails to 120%. If the S/G 1evel program _ select switch-is in the " Normal" position, which of- the following describes the effect this failure will have on the S/G 1evel control-system? The feedwater regulating valves on "A" and "D" S/G will open.to increase the levels to 66% since NI Channel 42 i now the controlling channel for these S/G's- The feedwater regulating valves will remain in the same position for all S/G' Trip program-for "A and_"D" S/G's will increase All feedwater regulating valves will open to feed all S/G 1evels to 66%. Since the programmed level is a "High Select" circuit, Channel 42 will be controlling The feedwater regulating valves on "B" and "C" S/C will open to_ increase the levels to 66% since NI Channel 42 is now the controlling channel for these S/G's-ANSWER: D MISCINFO:
REFERENCES: AP/2/A/5500/16 l
LESSON: OP-MC-CF-IFE TASK: MO-731 MO 630 .
OBJECTIVES: LPRO OBJ: 10 TIME: 3 MINUTES-LPSO OBJ: 10 - --
KA035000 G.15 3.6/ REV. DATE: 11/10/92
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4 HAIN CENERATOR 6 EXCITER I GENHCR02
- _ . _
i 1 Pt(s) Du) to a problem with the air s'.ue seal oil pump relief valve leaking, full air side seal oil presst.rt cannot be maintaine (It car, however maintain approximately 60 psig_
to the seals.) The decision is made to continue operation with a reduced generator hydrogen pressure of 45 psig. The
,
'
generator has a 0.9 lagging power factor. Select one of ;
the following: Limit power to approximately 1200 MW [
? Limit power to approximately 1140 MW , Limit power to approximately 980 MW Limit power to approxiwately 67u MW i
ANSWER: C '
MISC 1NFO:
REFERENCES : OP/1/B/6300/04 OP/1/A/6100/22 Enclosure 4.3, Curve .
LESS OP.MC+0EN MG TASK: MO 3321 OBJ EC1. /ES : LPRO OBJ: 11 TIME: 4 MINUTES LPSO OBJ: 11 KA045010 K4.25 2.8/ REV. DATE: _09/01/92 *
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$ CENERIC QUESTIONS SSE00R095 1 Pt(s) Given the following conditions: Reactor power is 1001 Pressurizer spray control is in AUTO Pressurizer spray valves open Which of the following is the response cf the PORV's and spray valves if pressurir.or master controller setpoint is inadvertently changed to 2370 psig? (Assume a step change in the setpoint and that pressurizer pressure control remains in automatic.) _
The automatic responses of the PORV's and spray valves OVER THE NEXT HOUR will be: PORV NC 34 will cycle opened and closed, spray valves wil1 remain opea PORV's NC 32 and NC 36 will cycle opene!. and closed, spray valvos will close PORV's NC 32, 34 and 36 will remain closed, spray valves will cycle opened and closed P0kV's NC 32, 34, and 36 will remain closed, spray valves _
will close ANSWER: B HISCINFO:
REFERENCES: OP.HC PS 1PE LESSON: OP MC PS-IPE TASK: MO 6303 OBJECTIVES : LPRO OBJ: 3 TIME: 3 h1NUTES LPSO OBJ: 3 KA010000 A1.07-3.7/ REV. DATE: 11/13/92
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6 GENERIC QUESTIONS SSE00R112 1 Pt(s) Given the following information: The Unit is in Mode 3 The Steam Dump Mode Selector is in the " Steam Pressure" position The valve positioner for Atmospheric Dump #1 (SV 30)'
fails "0 PEN" Which of the following will halt the resultant cooldown? S/0 Pressures decreasing to 770 psig NC System T ave decreasing to $50 degrees F Placing the Steam Dump Mode Selector to the "T ave Mode" Placing the " Steam Dump Interlock Byp**s $ witches"
"A" and "B" to the "0FF" position ANSWER: A MISC 1NFO:
REFERENCES: OP MC STM IDE LESSON: OP HC STH-IDE TASK: M0 6309 OBJ ECTIVES: LPRO OBJ: 1 TIME: 3 MINUTES LPS0 OBJ: 1 KA041020 A2.02 3.6/ REV. DATE: 11/10/92
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7 SCENARIO QUESTIONS !
SSE05R01
1 Pt(s)
'
d ce current control room indications, which of the wir.g describes the most probable cause for the disparity ;
asen the T-hot Loop "A" and T hot Loop "B" temperature !
indications on the alB" ICCS display? One of the Loop "A" T hot Harrow Range Instruments has ;
failsd low !
t The "A" S/0 PORV is open The "A" S/G Level is higher than the other S/G Levels
.
' A failure of the Loop "A" NC Pump has occurred i
ANSWER: D ?
>
MISCINro:
REFERENCES: OP MC PS NCP LESSON: OP MC PS-NCP TASK: MO 5312
,
OBJ ECTIVES : LPRO OBJ: 4 TIME: -3 MINUTES LPSO OBJ: 4 KA003000 K5.03 3.1/ ' REV. DATE: 11/10/92
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8 SCENARIO QUESTIONS
$5E05R03 l
l 1 Pt(s) Based on present control room indications, which of the l following describes proper Auxiliary Feed Water System (CA) l operation? '
1 If the "A" CA Pump is manually started CA flow WOULD l increase to-the "A" and "B" S/C's If the "TD" CA Pump is manually started CA flow WOULD NOT increase to the "C" and "D" S/G's -
' If the "B" S/G 1evel decreases to 10%; and the other S/G levels remain constant; both "MD" CA Pumps would start i and CA flow WOULD increase _to all S/O's !
- If the "A" CA Pump Auto Start " DEFEAT" PB is depressed and then released and then the "B" S/G level were to >
decrease to 101, the "A" CA Pump WOULD NOT automatically _- '
start ANSWER: C MISCINFO:
'
, REFERENCES: OP MC.CF.CA LESSON: OP.MC.CF.CA TASK: MO-3314 *
OBJ ECTIVES : LPRO OBJ: 13 TIME: 3 MINUTES LP50 OBJ: 13 KA061000 K2.04 3.4/ REV. DATE: 08/24/92
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9 SCENARIO QUESTIONS SSE05R04 r
i i
1 Pt(s) Based on present plant conditions, which of the following describes Pressurizer Pressure response? '
(Assume No Operator Action) If the "A" Loop Pressurizer Spray Control Valve (INC 27)
were to fail open, the resultant pressure drop WOULD NOT-be great enough to generate a Safety Injection signal If Pressurizer Pressure Channel 3 were to fail low and "
then, actual Pressurizer Pressure were to increase to 2350 psig, Pressurizer PORV INC 36 WOULD open If actual Pressurizer Pressure were to increase to 2290 psig, the "A" Loop Pressurizer' Spray Control !
Valve (INC 27) WOULD NOT open If Pressurizer Pressure Channel 2 were to fail high, the resultant pressure drop WOULD be great enough to generate a Safety Injection Signal a
P ANSWER: A B
MISCINFO: ,
REFERENCES: OP MC PS IPE >
LESSON: OP MC PS IPE TASK: M0 6303 OBJECTIVES: - LPRO OBJ: 1 TIME: 3 MINUTES LPS0 OBJ : - 1 KA010000 A2.02 3.9/ REV.;DATE: 08/24/9 i
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10 SCENARIO QUESTIONS SSE05R05 1 Pt(s) Based on present control room indteations, which of the following describes the current Pressurizer Level Control?
(Assume No Operator Action) If Pressurizer Level Channel 3 were to fail low, letdown would isolate The Pressurizer Level Program is currently being generated from a Loop T ave other than the Loop "A" T ave The Charging Line Flow Control Valve (1NV 238) should be full open The Pressurizer level Program should currently be generating a value of 25%
ANSWER: B MISCINFO:
REFERENCES: OP.MC PS ILE LESSON: OP MC-PS.ILI TASK: M0 6305 OBJECTIVES: LPRO OBJ: 1 TIME: 3 MINUTES-LPSO OBJ: 1 KA011000 A1.04 3.1/ REV. DATE: 08/24/92
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11 SCENARIO QUESTIONS SSE0$R06 1 Pt(s) Based on present control room indications, which of the following statements,is incorrect? The Source Range Nuclear Instruments will eventually re energize with no operator action required If the Source Range Nuclear Instruments were manually re energized right now, a signal would be generated that would prevent closing and maintaining closed the reactor trip breakers
_ The Nuclear Instrumentation System is currently generating a signal that_would prevent closing and maintaining closed the reactor trip breakers If power to EKVA were lost, the Intermediate Range Nuclear Instruments would generate a signal that would prevent closing and maintaining closed the reactor trip breakers ANSWER: A MISCINFO:
REFERENCES: OP.MC IC ENB LESSON: OP MC-IC ENB TASK: MO 2302
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OBJECTIVES : 7 TIME: 3 MINUTES LPRO LPS0 OBJ:OBJ: _ 7 KA015000 A2.01 3.5/ REV. DATE: 08/24/92-
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12 SCENARIO QUESTIONS SSE05R09
1 Pt(s) Civen current control room indications, which of the following would occur to the Emergency Core Cooling System if the "B" Train Safety Injection " Manual" initiato PB were
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depressed and released? (Assume No Further Operator Action) Both NV Pump suctions would align to the FWST The "B" Train NV Pump would lose its suction source The "B" Train NI Pump would lose its suction source The "B" Train NV Pump suction would remain aligned to the VCT ANSVER: D HISCINFO:
REFERENCES: OP MC PS NV LESSON: OP-MC PS-NV TASK: MO 3305 OBJ ECTIVES: LPRO OBJ: 3 TIME: 2 MINUTES LPSO OBJ: 3 KA006000 A2.08 3.0/ REV. DATE: 08/24/92
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13 SCENARIO QUESTIONS SSE05R11
1 Pt(s) Based on control room indications, which of the following describes the correct response of the RN System, if both
"A" and "B" Train Safety Injection--signals are generated?-' ' The Reactor Building non essential header WILL be supplied by the "B" Train RN Pump The "B" Train RN Pump WILL remain aligned to the Lou Level Intake Cooling water flow to the "B" Train D/G WILL NOT automatically align , The "B" Train RN to CA WILL align automatically on a low CA Pump suction pressure <
ANSWER: C MISCINFO:
REFERENCES: OP-MC PSS RN -
LESSON: OP MC PSS RN TASK: M0 3333 OBJECTIVES : ' LPRO OBJ : 7 TIME: 3 MINUTES LPS0 OBJ: 7 KA076000 A4.04 3.5/ REV. DATE: 08/24/92 J
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i 14 SCENARIO QUESTIONS SSE0$R16 .
t
,
1 Pt(s) Based on control room indications, with no operator actions to control temperature,-apprcximately where will temperature
,
stabilize over the next several hours?
(Assume S/G Levels Are Maintained At 38%) i T ref ; T no load degrees F degrees F ANSWER: D MISCINFO: i REFERENCES: OP MC IC-IRX !
LESSON: OP MC IC IRX TASK: MO 3310 OBJ ECTIVES : LPRO OBJ: 3 TIME: 3 MINUTES -!
LPSO OBJ: 3 KA001000 A1.01 3.8/ REV. DATE: 08/24/92
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15 SCENARIO QUESTIONS SSE05R17 1 Pt(s) Based on control room indications, the control room operator must increase boron concentratica: By 450 ppa, but NV 265 must be opened locally By 300 ppm, but NV 265 must be opened locally By 450 ppm from the control room By 300 ppa from the control room ANSWER: B f MISCINFO: ,
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REFERENCES: OP MC IC IRE ,
LESSON: OP MC.IC-IRE TASK: MO 7313 ,
OBJECTIVES: LPRO OBJ: 16 TIME: 3 MINUTES l LPS0 OBJ: 16 l
KA001000 A2.03 3.5/ REV. DATE: 08/24/92
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PRINT NAME PROC. ID: OP MC LRQ SIGNATURE NRCMU PART B(SRO)
SSN Prepared by: f SHIFT DATE REVIEW / INITIAL
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LICENSED REQUAL ANNUAL EXAMINATION hl\/h SUBJ ECT: NRCMU PART B(SRO)
Total Points: 25.00 Total Questions: 25
- INSTRUCTIONS *** Use NO. 2 PENCIL onl . Fill in the appropriate information on the TEST COVER SilEE . Ask the test monitor instructor abouc any_ questions which are not clear to yo . Circle the correct answer on each question of this exa . When finished with exam, read the "non compromise statement" and sign the TEST COVER 5.iEE NON COMPROMISE STATEMENT:
"My Signature on this form is my declaration that the responses given on the attached test or exam are entirely my ow It further declares that 1 am aware that 1 am_ subject to termination from the training program immediately and in addition, will be subject to further disciplinary action up to and including discharge from the company for cheating and/or compromising on exams / tests / quizzes."
l
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1 EP 04, 05 SERIES EPEP04R05 1 Pt(s) Following a Safety Injection on Unit 1 due to a major SGTR, the following conditions / indications exist: All S/G Main Steam Isolation and Bypass valves closed All S/G SM PORV's in auto and closed .c TD CA Steam Supply from "C" S/G closed 4 S/G "C" SM pressure decreasing at 300 psig per minute _and cannot be controlled S/G's "A", "B", "D" S/G SM pressure decreasing _at 10 psig per minute due to the cooldown S/G narrow range levels: -
"A" S/G 38%
"B" S/0 40%
"C" S/G $7%
"D" S/C 39% Pressurizer Level is 10% NC System subcooling is 10 degrees F FWST level is 480 inches Which action should the operator take7 Go to EP/5.1 (SGTR with Continuous NC System Leakage -
Subcooled Recovery) Go to EP/5.2 (SCTR with Continuous NC System Leakage -
Saturated Recovery) Reinitiate Safety Injection, return to EP/01 (Reactor Trip or Safety Injection ) Continue with EP/04 (SGTR) until the cooldown method for a ruptured S/G is determined in step 33 ANSWER: A MISCINFO:
REFERENCES : EP/1/A/5000/04 ,12/17/90 EP/1/A/.5000/5.1 ,12/17/90 LESSON: OP HC EP-EP4 TASK: MO 8305 MO-4608 OBJECTIVES: LPRO OBJ: 7 TIME: 5 MINUTES LPS0 OBJ: 7 KA000038 G 12 3.8/ REV. DATE: 11/11/92
1 .
2 INCORE INSTRUMENTATION ICENAR01 i
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1 Pt(s) Unit 1 is at 100% powe Powar Range Channel 42 has been- : I declared inoperable due to detector failur The Reactor ;
'
Croup has attempted to run the Incore Instrument System to-determine QPTR. They report that 30 of the 58 thimbles are i INOPERABL l
Determine which of the following is the minimum action required to be take Monitor QPTR at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when above 75%
RTP using Incore Detectors Thermal Power is restricted to <.75%' RTP and the >
Neutron _ Flux High Trip setpoint is reduced to 5 85% RTP ,
within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Monitor QPTR at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> using incore thermocouples since the incore detection system is
'
inoperable Reduce thermal power to < 50% RTP within the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> *
'
snd reduce P.R. neutron flux high trip setpoint to s 55%
RTP within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> t
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ANSWER: B MISCINFO: '
REFERENCES: Tech. Spec. 3.3.- Tech. Spec. 3. LESSON: OP MC IC ENA TASK: MO 2316 OBJECTIVES: LPRO OBJ: 7 TIME: 6 MINUTES LPS0 OBJ: 7 l
KA015000 A1.04 3.5/ REV..DATE: .11/11/92
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3 EMERGENCY PIAN I RPEMPR15
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l 1 Pt(s) Given the following: l Unit 1 is in Mode 5 The 1A D/G is disassembled due to a fuel injection failure discovered during Surveillance Testing !
3. While running D/G 1B for Surveillance Testing the IB D/G -i
. _ loses oil pressure and throws a rod
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4 Neither D/G will be returned to service for at least ;'
9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> A lightning strike-in the switchyard causes PCB's 8, 9, 11, and 12 to open If it takes 18 minutes to re+close the PCB's, what course of action concerning Energency. Classifications should be take .
to address the situation? t You must declare la Notification of Unusual Event - You mustLdeclare an Alert You must declare a-Site Area Emergency .
' No Emergency Classification is warranted ANSWER: B MISCINFO:
t REFERENCES: RP/0/A/5700/00
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LESSON: OP MC EP EMP TASK: M0 9300 OBJECTIVES : LPRO OBJ: 8 TIME: 5 MINUTES-LPSO OBJ: 10
KA000055 G.2 2.9/ REV. - DATE': 11/11/92-
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4 MALFUNCTION OF NC PUMP APAP08R02 1 Pt(s) The Unit is at 55% Reactor Power when the following data was collected: "D NC Pump Seal Leakoff Hi" flow indicates 4 gpm and is stable "D" NC Pump Seal D/P is 400 paid "D" NC Pump Motor Frame Vibration is 3 mils increasing slowly "D" NC Pump " Motor Shaft Vibration" is 17 mils "D" NC Pump " Pump Shaft Vibration" is 22 mils "D" NC Pump " Motor Axial Vibration" is 12 mils - "D" NC Pump " Motor Flywheel Vibration" is 18 mils Based on these conditions, which of the following actions should-the operator take? Continue to monitor the "D" NC Pump Seal- Leakof f until-flow indicates 10 gpm and then trip _the Reactor Continue to_ monitor the "D" NC Pump Motor Frame Vibration and if it exceeds 5 mils trip the Reactor and then stop
"D" NC Pump
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C._ Trip the Reactor and then stop "D" NC Pump Reduce Reactor Power to lass than P 8 and then stop
"D" NC Pump ANSWER: C MISCINFO: -
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REFERENCES : AP/1/A/5500/08 12/05/91 LESSON: OP MC PS NCP TASK: MO-7307 OBJECTIVES: LPRO OBJ: 14 TIME: 4 MINUTES LPS0 OBJ: 14 KA000015 EA1.23 3.1/ REV. DATE: 11/11/92
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5 REFUELING WATER SYSTEM !
FHFWR04 -
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1 Pt(s) -The following conditions exist: i l Unit 1 at 100% RTP .* FWST Level channel 1 160 inches FWST Level Channel 2 149 inches FWST Level Channel 3 160 inches Select the correct response concerning these indications: Channel 2 must be placed in the tripped condition within !
.one hour Operation at 100% RTP may continue.with Channel 2 ;
inoperable as long as " Bypass" on the "Cntrl Permissive -
For Recirc Mode NI 184-and N1 185" are depressed
.. ; Channel 2 must be returned to operable status within 7 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in at least llot Standby within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and :
Cold Shutdown within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> Channel 2 must be placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />
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ANSWER; A MISCINFO: *
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REFERENCES: PT/1/A/4600/03A 11/21/91 Tech. Spec. 3. LESSON: OP MC Fil FW TASK: M0 3307 OBJECTIVES : - LPRO OBJ: 6, 8- TIME: 5 MINUTES-LPS0 OBJ: 6, 8 KA006020 A1.09 3.3/ REV, DATE: 11/11/92 ,
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6 ENGINEERED SAFEGUARDS- I ECCISER09 l
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I 1 Pt(s) Unit 1 is operating at 100% power. When the following information is observed on "D" S/0 Narrow Range (NR) Levels: j Channel 1 66% :
Channel 2 65% ?
Channel 3 58% ;
Channel 4 63%
Based on this inforwation, which of the following is required? No action is required since Channel 3 is within 4% of ;
the average of all 4 indicated "D" S/G NR levels
' No action is required since Channel 3 is stil1~ greater *
than the Low Low Level Rx trip /CA auto start setpoint Action must be tal'.en to place "D" S/G Lo Lo -Level and Hi Hi Level Channel 3 in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Action must be taken to place "D" S/G Lo Lo Level and ,
Hi Hi Level Channel 3 in the tripped condition-within i 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> .i
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ANSWER: D MISCINFO:
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REFERENCES: Tech. Spec. 3. PT/1/A/4600/03A 11/21/91 Tech. Spec.-Ref.-Manual .
LESSON: OP MC-ECC-ISE TASK: M0 2313-MO 162 .
OBJ ECTIVES: LPRO OBJ: 3- TIME: 4 MINUTES LPSO OBJ: 3-
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KA013000 C.11-3.5/ REV. DATE: 11/11/92-
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7 AIR ADD. AND RELEASE SYSTEM CNTVQR01 1 Pt(s) Civen: A VQ Release has been mad . The VQ Release was started at 112 . The VQ Release was stopped at 115 . Initial Containment Pressure was 0.19 psi . Final Containment Pressure was 0.12 psi . The VQ Totalizer is inoperabl What was the TOTAL VOLUME released? _ .2 Cubic Feet .8 Cubic Feet .0 Cubic Feet .5617.2 Cubic Feet ANSWER: B MISCINFO:
REFERENCES: OP/1/A/6450/17 Enc, 5.2, 09/26/90 .,
LESSON: OP MC.CNT-VQ TASK: MO 3340 OBJ ECTIVES : LPRO OBJ: 5 TIME: 4 MINUTES LPSO OBJ: 5- - - - -
KA103000 A4.01 3.2/ REV. DATE: 11/11/92-
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I 8 REACTOR COOLANT PUMPS 1 PSNCPR04 l 1 Pt(s) Unit 1 is at 29% RTP. The RO accidentally trips alA" ,
Reactor Coolant Pump (NCP) while replacing a burned out NCP i indicator. Af ter verifying ."1A" S/G narrow range level at :
its programmed level and noting the following-for "1A" NCP: Unit 1-at 29% RTP l' #1 Seal D/P is > 400 psi , NCP Standpipe alarms cleared 4 VCT Pressure is 40 psig t Seal Injection Flow is 8 gpm #1 Seal Leakoff is 1.5 gpm < NCP Oil Pot levels are satisfactory should "1A" NCP be restarted? 7
- Yes, all NC pump parameters are normal and reactor power ,
is less than P 8
- Yes, all NC pump parameters are normal and reactor power is less than 30%
, No, all NC pump parameters are normal, but reactor power is greater than 25% No, two of the NC pump parameters are not normal, but power level would permit a pump restart
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ANSWER: C MISCINFO: ,
REFERENCES: OP/1/A/6150/02A -
LESSON: OP MC-PS NCP TASK: MO 3308 OBJ ECTIVES: LPRO OBJ: 10 TIME: : 3 MINUTES LPS0 OBJ: 10 -
KA003000 C.10 3.3/ REV. DATE: . 01/15/92
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9 REACTOR POISONS RTRPR03 1 Pt(s) In preparation for a Unit 1 Startup, an Estimated critical Boron Determination is performed. The ECB is 1000 pp The present boron concentration is 1400 pp Determine the quantity of demineralized water to be addet to the NC System to achieve the desired boron concentration? Add 4,211 gallons of demineralized water Add 6,370 gallons of demineralized water Add 14,168 gallons of demineralized water Add 20,538 gallons of domineralized water .
l ANSWER: D l
MISCINFO: -
i REFERENCES: O ?/1/A/6100/22 Sect. ?/1/A/6150/09 10/15/86 LESSON: 08 MC RT RP TASK: MO 131 ,
MO 330 !
E OBJ ECTIVES : I PRO OBJ : 4 TIME: 2 MINUTES LPS0 OBJ: 4 KA004000 A4.04 3.2/ REV. DATE: 11/11/92 i
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, _ . . . ~ . . e 10 EP 14 SERIES EPEP14R05 1 Pt(s) During the performance of EP/1/A/5000/14.1, Response to Imminent Pressurized Thermal Shock Conditions, you are directed to depressurize the NC System to reduce subcoolin Containment pressure had peaked at 2.5 psig, but is currently 0.3 psig. Which of the following conditions WILL PERMIT continued depressurization? NC System Cold Leg temperatures are 363 degrees F and NC System pressure is 740 psig NC System Cold Leg temperatures are 390 degrees F and NC System pressure is 885 psig
- NC Systein Cold Leg temperatures are 337 degrees F .
'and NC System pressure is 435 psig NC System Cold Leg temperatures are 450 degrees F and NC System pressure is 1085 psig ANSWER: B MISCINFO:
REFERENCES : -EP/1/A/5000/1 LESSON: OP MC EP EP14 TASK: M0 8313 OBJECTIVES : LPRO OBJ : . 2 TIME: 3 HINUTES LPS0 OBJ : - 2 -
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KA000009 EA2.014.2/ REV. DATE: 09/22/92 i
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11 CONTAINMENT SPRAY SYSTEM
- ECCNSR01 1 Pt(s) During performance testing of NS Train "B", NS-128 (Containment Spray Pump B Discharge Isolation Valve) was determined to be incapable of automatic closin5 or opening, but could be manually positioned. What is the impact of NS.128 being open and incapable of automatic closing on the operability and operation of NS Train "B"7 NS Train "B" is operable, however inadvertent operation
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of "B" NS Pump would spray down containment NS Train "B" is operable, however in the event of an-automatic spray-actuation, the Containment Pressure Control System (CPCS) would not function to prevent exceedin6 the design negative pressure in containment NS Train "B" is inoperable'because operation of the "B" NS pump would result in a motor overload trip NS Train "B" is inoperable because the: Containment'
Pressure Control System (CPCS) would not function to prevent exceeding the desi6n negativo pressure in containment ANSWER: A MISCINFO:
REFERENCES: . ESP Valve Study Tech. Spec. 3. Tech Spec. 3. LESSON: OP MC-ECC NS- TASK: MO 332 M0 332 OBJ ECTIVES: LPRO C BJ : 2, 7 TIME: 3 MINU'iES LPSO (BJ: -2, 7 KA026000 C.11 3.2/4.1' REV. DATE: 5/21/92
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a 12 FUEL llANDLING THFCR05 1 Pt(s) The refueling cavity water level is greater than 23 feet above the top of the reactor vessel flange. Unit 1 is in Mode 6. Core reload is in progress. The fuel loading supervisor requests that the operating Decay Heat Removal Pump be secured to facilitate loading fuel assemblies adj ac ent to the C loop hot leg outlet. He states that the ND flow is causing the assemblies to swing enough that they cannot be seate Which of the following indicates a response which is in compliance with Tech Specs and Plant Operating Procedures? Do not secure the pump, in Mode 6 when water level is above the top of the reactor vessel flange by greater than 23 feet, at least one ND loop shall be operable and in operation Do not secure the pump, when in Mode 6 a boron injection flow path shall be operable and capable of being powered
. from an operable emergency power source Secure the pump, in Mode 6 when water level is above the top of the reactor vessel flange by greater than 23 fee The ND loop may be removed from operation for up to I hour per 8 Four period for core alterations in the vicinity of the hot legs Secure the pump, in Mode 6 the ND system is required to be operable but not in operation ANSWER: C MISCINFO:
REFERENCES: Tech Spec. 3. LESSON: OP MC FH FC TASK- MO 9313 OBJ ECTIVES : LPRO OBJ : 14 TIME: 2 MINUTES LPS0 OEJ: 14 KA015000 C.11 3.1/ REV. DATE: 04/08/92
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i 13 EP 02, 06, OB SERIES l'
EPEP02R08 l
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1 Pt(s) While evaluating the SI termination criteria following a liigh l Energy Line Break Inside the Containment (HELBIC), the following information is noted: ; NC System Pressure 1500 psig constant ! Pressurizer Level 34% constant NC Subcooling = 40*F constant Total CA flow to nonfaulted S/G's = 1000 gpm EMF-34 (L) S/G sample Inoperable All other EMF's Normal ! NC Loop "1A" Cold Leg Temp 400'F NC Loop "1B" Cold Leg Temp 390*F 9 NC Loop "1C" Cold Leg. Temp 410*F-1 NC Loop "1D" Cold Leg Temp 405'F Which of the following should be implemented? EP/1/A/5000/ (SI Termination Following Excessive Cooldown) EP/1/A/5000/4.0 (Steam Generator Tube Rupture) EP/1/A/5000/ (SI Termination Following a llELBIC) EP/1/A/5000/ (Post LOCA Cooldown and Depressurization)
ANSWER: D MISCINFO:
REFERENCES: EP/1/A/5000/02 2/17/90 LESSON: OP MC EP EP2 TASK: MO 8302-OBJECTIVES : LPRO OBJ: 1 TIME: 3 MINUTES LPS0 OBJ: 1 KA000040 C.12 3,8/ REV, DATE: 05/02/91 q4. -w .-
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l 14 SPENT FUEL COOLING SYSTEM i FHKFR0 ,
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f 1 Pt(s) Following shift turnover the Reactor Operator notices the Spent Fuel Pool level.at "MINUS 2.5 ft" on the Control Room :
Caug The same indication was verified on the local '
indicatio Based on this level, which course of action should-be followed? .
! Increase boron concentration to greater than 2000 ppm AND ensure Keff is less than .95 -' Initiate makeup to Spent Fuel Pool to restore level ,
within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and suspend all movement of fuel assemblies and crane operations with loads in the fuel l storage area Initiate makeup to Spent Fuel Pool to restore level ,
within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and suspend all. movement of' fuel assemblies and crane operations with loadr in the fuel storage area , Increase boron concentration to greater than 2000 ppm OR ensure Keff is less than .95
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ANSVER: B l
MISCINFO:
REFERENCES: OP/1/A/6200/05 Tech. Spec. 3.9.10 PT/1/A/4600/03C .
I LESSON: OP.MC FH KF TASK: MO 331 #
OBJ ECTIVES: LPRO OBJ: 6, 8 TIME: 4 MINUTES LPS0 OBJ:: 6, 8
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KA033000 A2.03 3.1/ REV. DATE: 11/11/92 .;
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'15 PRE REFUELING OUTACE
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CPPROR03
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1 Pt(s) During refueling operations the "S/G A Nozzle Dam Trouble" alarm is received. (The refueling canal level is normal and-not decreasing.) The Reactor Operator dispatched a -
Non Licensed operator to the local S/G Nozzle Dam Control -
Panel to determine the cause of the alarm. Given the i following information: l Air flow in the annulus is 15.7 Scr * No other abnormal indications exis .
Select the action the operator should take: Close the annulus shutoff valve, then close the seal shutoff valve Close annulus. shutoff and seal shutoff valves, open ,
cabinet and disconnect appropriately marked annulus-high pressure switch pilot hose connection ,
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' Increase dry seal pressure 5 psig in 2 minute increments until annulus flow stops or 90 psig maximum is achieve Reevaluate Increase wet seal pressuro 5 psig in 2 minute increments '
or 90 psig maximum and place annulus shutoff valve temp-orarily to the " Drain" position. Reevaluate +
ANSY" C MISCINFO:
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REFERENCES: OP/0/A/6150/15 (Ch 1)
OP/1/A/6100/10H (Chg 13)
LESSON: OP HC CP-PRO TASK: M0 7317 MO 7326 MO-900 OBJECTIVES : LPRO OBJ: 14, 15, 16 TIME: 4 MINUTES LPSO OBJ: 14, 15, 16 i
i KA000025 0.5.3.6/ REV. DATE: 11/11/92 i
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c 5 16 LDSS OF CONTROL ROOM ~
APAP17R02
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1 Pt(s) The Control Room has become uninhabitable ~and~tha following data was collected from OAC General Program 76: Control Bank "D" Croup 1 Rods-(D4 and M12) are NOT fully inserted y All other rods ARE fully insert Current boron concentration is 600 PPM
, Based on these conditions, we mast Emergoney Borate;to: PPM to account for the rods-not fully inserted PPM to account for the rods not' fully 1 msrted-
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.1 PPM to' account for the rods not fully inset ted : PPM to account for the rods not fully inserted ANSWER: A MISCINFO:
REFERENCES: AP/1/A/5500/17 11/26/91 e
LESSON: OP-MC CP SS- TASK: MO 7315 OBJECTIVES : LPRO OBJ : 1 TIME: 4 MINUTES LPSO OBJ: 1 KA000005 EA2.03 3.5/ REV. DATE: 11/11/92
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'17 AUXILIARY FEEDWATER CFCAR10
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.1 Pt(s) While performing the CA TD monthly operability test, during a unit startup, with Unit 1 in Mode'3, the TD CA Pump developed .g a discharge pressure of 1240 psig with a 970 CPM flo It was noted that main steam-pressure was 865 psig. -Based.on thi information the operator must: Declare the TD CA pump inoperable, because cteam pressure-is < 900 psig and the test should not be performed Increase steam pressure to > 900 psig and retest the T CA Pump prior to the time extension for performing the -
rest expires Consider the TD CA Pump as passing the operability test Declare the TD CA Pump inoperable due to the 970 GPM flow rate ANSWER: C MISCINFO:
REFERENCES: Tech. Spec. 3.7. Tech. Spec. . Interpretation 4.7. LESSON: OP-MC-CF-CA- TASK: MO 3314 OBJECTIVES: LPRO OBJ: 9B TIME: 4 MINUTES -
LPS0 03J: 9B KA061000 G 11 3.4/ .REV DATE: 11/11/9 s
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-18 RESIDUAL HEAT REMOVAL SYSTEM PSNDR02 4 1 Pt(s) Civen the-following information:
, Unit 1 is in Mode-5 . . The NC System is drained to a-level of +11 inches in'the ;
loops LMD Train alA" it in operation . S/C's "1A" and alD" are completely drained S/C's "1B" and "1C" have a narrow range. level of 38% E requests permission to-perform _a surveillance test ~
on the ND ? ump "1B" supply breaker The breaker will-be racked into the " Test" position for at least 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> Select the correct evaluation as to whether permission should be granted to perform the tes Yes, two steam generators have NR levels greater thanL12% Yes, an ND pump may be de energized for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> No, _an ND pump may only be inoperable for up to 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> No, two steam generators are completely drained ANSWER: C MISCINFO:
REFERENCES: Tech. Spoc. 3.4.1. PT/1/A/4600/03A-
LESSON: OP MC PS-ND TASK: MO-3311
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OBJECTIVES: LPRO OBJ : 9 TIME: 3 MINUTES
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KA005000 C.11 3.1./ .REV. DATE: 11/13/92:
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19 EP 13 SERIES EPEP13R05 1 Pt(s) While performing an NC System Fsed and Bleed as pe EP/13.1 " Response to Loss of- Secondary Heat Sink" the following Core Exit T/C's temperatures and NC System
. pressures.w ere recorded:
TIME CORE EXIT T/C's NC SYSTEM PRESSURE deg' 2200 psig deg 2000 psig- deg 1900 psi . 0930 605 deg 1800 psig deg 1700 psig deg 1400 psig deg 1200 psig deg 1050 psig deg 950 psig 10. 1030 530 deg 800 psig-(All'three Pressurizer PORV's are open and a Secondary Heat Sink cannot be established.)
Based on this information, which action should be taken?
_ Continue attempts to establish a secondary heat sink The operator should reset SI and the D/G load sequencers
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and stop one NI or NV pump to slow the cooldown rate The operator should close ces of the pressurizer PORV's ,
to slow the cooldown rate The operator should-reset SI, the D/G load sequencers,.
stop one NI or NV-pump and close one of the pressurizer l
.!
PORV's to slow the cooldown rate ANSWER: A MISCINFO:
REFERENCES: EP/1/A/5000/13.1, 12/'.9/91 LESSON: OP-MC-EP-EP13 TASK: MO-8312-OBJECTIVES: LPRO - 0BJ : '2 TIME: 5 MINUTES LPS0 OBJ: 2 KA000074 G 12 4.3/4.4- REV. DATE: 11/11/92
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20 LOSS OF ND SYSTEM APAP19R03
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1 Pt(s) The following conditions exist:
1) The Unit is Mode 5 and has been S/D for 3 days 2) NC System level is 80% on the Pressurizer Cold Ca ) The S/G manways are installed and the Reactor Vessel Head is set 4) Both ND Pumps were stopped due to ND 1 being inadvertantly closed 5) The Pressurizer PORV's are providing over-pressure protection ND 1 is reopene You are instructed to restart the ND Pumps and then to cool the NC Texperature'T-Cold to 102 degree If current NC Temperature T-Cold is 118 degrees, what-is the maximum Administrative coold.own rate you are permitted to use as per the Abnormal Procedure? Degrees Per Hour
. Degrees Per Hour Degrees Per Hour Degrees Per Hour ANSWER: D
. MISCINFO:
REFERENCES: AP/1/A/5500/19 LESSON: OP-MC-PS-ND TASK: MO-7317 OBJECTIVES: .LPRO OBJ : 11 TIME: 5 MINUTES LPSO OBJ: 11 KA000025 EA1.01 3.6/ REV. DATE: 10/07/92
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'4, 21 FIRE PROTECTION SYSTEM SSRFYR03 1 Pt(s) Mechanical Maintenance has submitted a work request fo approval to work on the "C" fire pump which will require tag out of the pum Can this work request be approved without relying on an Action Statement? Yes; Any two out of three t' ire suppression pumps. must be operable Yes; We must ensure an operable flow path exists from Lake Norman to the distribution headers in plant and this condition will still exist No; With any one fire suppression pump inoperable action must be taken/ log entry made within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> No; Either the "A" and "C" or "B" and "C" pumps must-be operable with their discharge aligned to the fire suppression header ANSWER: D MISCINFO:
REFERENCES: SLC 16.9-1 LESSON: OP-MC-SS RFY -TASK: MO-3343 OBJECTIVES : LPRO OBJ : 11 TIME: 3 MINUTES LPSO CBJ: 11 KA086000 C.ll 2.7/ REV. DATE: 09/01/92
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o; 22 H 2 SKIMMER & AIR RETURN SY CNTVXROS
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1 Pt(s) Following A Utait 1 LOCA. the H2 Recombiners must be-placed in service. Determine the power setting for H2 recombiner 1 Containment pressure is 9.1 psi = 324.6 KW q = 53.5 KW = 13.7 KW = 1.5 KW ANSWER: B'
MISCINFO:
REFERENCES: OP/1/A/6100/22 Curve 1.8 '(11 11-87)
OP/1/A/6450/10 Enc. 4.2 (11-17-87;
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LESSON: OP-MC-CNT-VX TASK: MO-3341 OBJECTIVES : LPRO OBJ : 11A TIME: 5 MINUTES LPSO OBJ: 11A KA028000 A2.01 3.4/ REV. DATE: 11/11/921
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23 PRESSURIZED THERMAL SHOCK TAPTSR04 1 Pt(s) You are in the process of recovaring from a steam line break inside containment where excessive cooldown has occurre You have completed the soak required in EP/14.1 Response to Imminent PTS and are about to initiate a cooldown to Mode Given the following information: The "A" S/G is DRY and DEPRESSURIZE . The NCP's are NOT runnin . NC Temperatures are as follows:
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Loop A B C D s
WR Th 420*F 425'F 425'F 422*F WR Tc 420*F 415'F 400*F 417'F Select the maximum allowable NC System pressure: psig
. psig psig psig ANSWER: B MISCINFO:
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REFERENCES: EP/1/A/5000/1 LESSON: OP-MC-TA-PTS TASK: MO-8313 MO-4615 OBJ ECTIVES: LPRO OBJ: 24 TIME: 4 MINUTES LPSO OBJ : 24 KA000040 C.12 3.8/ REV, DATE: 11/11/92
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24 SAFETY INJECTION SYSTEM ECCNIR03 1 Pt(s) Unit 1 is being cooled down to Mode 5 with the "1A" and "lB" NCP's runnin The following NC. Cold Leg temperatures exist:
Cold Leg Temperature
"A" 310 DEGREES F
"B" 305 DEGREES P
"C" 305 DEGREES F ,
"D" 310 DEGREES F Which of the following describes conditions UNACCEPTABLE for continued operation in this Mode?
All of the "A" Train Pumps are operable: Except for the "A" Train ND Pump which has its breaker racked out and tagged, while all of the "B" Train Pumps have their breakers racked out and tagged Except for the "A" Train NI Pump which has its breaker '
racked out and tagged, while all of the "B" Train Pumps have their breakers racked out and tagged, except for the
"B" Train NI Pump which is operable While all of the "B" Train Pumps have their breakers racked out and tagged, except for the "B" Train NI Pump which-is operable While all of the "B" Train Pumps have their breakers racked out and tagged ANSWER: A MISCINFO:
REFERENCES: Tech. Spec. 3. LESSON: OP-MC-ECC-NI TASK: M0-4326 OBJECTIVES: LPhD OBJ: 7 TIME: 4 MINUTES LPS0 OBJ: 7 KA006000 G.11 3.6/ REV DATE: 11/11/92
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iD 25 EXCORE NUCLIAR INSTRUMENTATION-ICENBR08
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1 Pt(s) Give.n the following information: The Turbine is being prepared for loadin . The reactor is critical at approximately 0% powe . Annunciator "IR HI VOLTAGE FAILURE" alarm . You determine that IR channel N36 has failed lo Which of the following best describes your required actions? Place the N36 LEVEL TRIP switch in the BYPASS position, and continue the power escalation A reactor trip should have occured, therefore manually trip the reactor and go to EP/01 " Reactor Trip or Safety Inj ec tion" Place the N36 LEVEL TRIP switch in the BYPASS position, then reduce power to less than 5%, then pull the N36 control power and instrument power fuses Restore N36 to operable status before increasing power above 10% of Rated Thermal Power
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ANSWER: D MISCINFO:
REFERENCES: Tech Spec 3. LESSON: OP-MC-IC ENB TASK: M0-1309 OBJECTIVES : LPRO OBJ: 14 TIME: 4 MINUTES LPS0 OBJ: 14 KA000033 EK3.02 3.6/ REV. DATE: 11/11/92'
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PRINT NAME PROG, ID: OP MC-IltQ SICNATURE NRCMU-SSE-09(SRO)
SSN Prepared by: ./,,
SHIFT DATE REVIEW / INITIAL QJEST&
. LICENSED REQUAL ANNUAL EXAMINATION SUBJECT: NRCKU-SSE-09(SRO)
Total Points: 16.00 Total Questions: 16
- INSTRUCTIONS *** Use NO. 2 PENCIL onl . Fill in the appropriate information on the TEST COVER SHEE . Ask the test monitor instructor about any questions which are not clear to yo . Circle the correct answer on each question of this exa . When finished with exam, read the "non-compromise statement" and sign the TEST COVER SHEE NON-COMPROMISE STATEMENT:
"My Signature on this form is my declaration that the responses given on the attached test or exam are entirely my own.'
It further declares that I am aware that I am subject to termination from the training program immediately and in addition, will be subject to further disciplinary action up to and including discharge from the company for cheating and/or compromising on exams / tests / quizzes."
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1 ENCINEERED SAFECUARDS ECCIS ER02
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1 Pt(s) Civen the following: Safety Injection (SI)'was initiated inadvertantly by-pushing the " Manual" SI pushbutton . SI was procedurely terminated and the capability o automatic SI initiation was reinstate . The NC System is at 557 degrees and 2235 psi . All reactor trip signals have.been cleared or " Reset" Which action, when completed, reinstated the capability of'SI-to initiate automatically?
7 When the SI "Reste" pushbuttons have been depressed an the " Reset" lights are lit When the Load Sequencer " Reset" pushbuttons have been depressed and the " Reset" lights are lit When the reactor trip breakers are closed When a " Manual" SI initiation occurs, the capability of~
automatic initiation is not lost at any time during-the SI Termination-procedure ANSWER? C MISCINFO:
REFERENCES: EP/1/A/5000/1.2 01/11/91
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LESSON: OP MC-ECC ISE TASK: MO 2313 5. OBJECTIVES : LPRO OBJ: 1 TIME: 4 MINUTES LPS0 OBJ: 1 KA013000 K4.12 3.7/ REV. DATE: -11/10/92 L
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2 ROD CONTROL SYSTEM ICIREROS 1 Pt(s) Unit 1 is at 82% RTP, increasing load at 2 MWe/ min, when the " Rod control Urgent Failure" (1AD2 A-10) annunciator alarms. Which of the following would ALLOW moving the Controlling Bank in the " Bank Select" mode in order to maintain T ave - T ref? The " Urgent Failure" exists in the Logic Cabinet The " Urgent Failure" exists in Power Cabinet "1AC" The " Urgent Failure" exists in Power Cabinet "1BD" ~-' The " Urgent Failure" exists in Power Cabinet "2BD" ANSWER: B MISCINFO:
REFERENCES: AP/1/A/5500/14 OP/1/A/6100/10B LESSON: OP-MC IC-IRE TASK: MO-2315 MO 6302 MO-7313 OBJ ECTIVES : LPRO OBJ : 10 TIME: 4 MINUTES LPS0 OBJ : 10 _
KA001050 A2.01 3.7/ REV. DATE: 11/10/92 _ _______ _ _ _ _ _ - _ _ _ - _ _ - . _ - _
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3 PZR LEVEL CONTROL PSILER08 1 Pt(s) Given the following information: Unit 1 is operating at 50% power All Control Systems are in Automatic The Pressurizer Level Control select switch is in the
"1-2" position Pressurizer Level Channel 2 fails high
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Which of the following describes the automatic control action which would occur and the required operator action ~
due to this instrument failure? The Reactor trips, all backup heaters energize, charging flow decreases to minimum; Channel 2 must be restored to operable or placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> All backup heaters energize, charging flow decreases to minimum; Channel 2 must be restored to operable or placed in tripped condition within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> All Pzr. heaters deenergize, letdown isolates, charging flow decreases to minimum; Letdown flow must be restored and Channel 2 must be restored to operable or placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> No automatic action occurs, but channel 2 must be restored to operable or pisced in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />
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ANSWER: D MISCINFO:
REFERENCES: OP/1/A/6100/10G AD6 - A7 Tech. Spec. 3. LESSON: OP-MC-PS-ILE TASK: MO-6305 b"_te OBJECTIVES : LPRO OBJ: lE, 3 TIME: 5 MINUTES LPSO OBJ: 1E, 3 KA011000 A2.10 3.4/ REV. DATE: 11/10/92
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4 REACTOR C001 ANT SYSTEM ;
PSNCR12- .
1 Pt(s) Civen tnat: Unit 1 is being cooled down to Mode , Letdown is isolate . NC Pumps "A" and "C" are runnin NC Temp 6tature - 340' F NC Pressure - 790 psig Pzr Temperature - 520*F VCT Temperature - 115'F NC Cooldown Rate -
40'F/hr Is it permissable to control pressurizer pressure by initiating NV Auxiliary Spray? Why? Since the temperature differential between the NC Temperature and VCT Temperature is 225'F; it is permissible to initiate NV Auxiliary Spray Since the temperature differential between-the Pzr Temperature and NC Temperature is_180'F;:it is permissible to initiate NV Auxiliary Spray Since the temperature differential between the Pzr Temperature and VCT Temperature is 405'F;'it is not permissible to initiate NV Auxiliary Spray - Since-the unit is not yet in Mode 5 it-is not permissible-to initiate NV Auxiliary Spray ANSWER? C MISCINFO:
REFERENCES: . Tech. Spec. 3.4. OP/1/A/6100/02
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LESSON: OP-MC-PS NC TASK: MO-5304.1~
OBJECTIVES : LPRO OBJ: 4 TIME: 3 MINUTES-LPSO OBJ: 4 KA010000 A1.08 3.2/ REV. DATE: 11/10/92 l :-
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5 GENERIC QUESTIONS I SSE00R053 1 Pt(s) A major steam leak has raised containment- temperature to 180 degrees. How, if at all, do~you expect this to affect ,
INDICATED pressurizer level? - The indicated level will decrease due to the decreased density of-the reference leg The indicated level will increase due to the decreased density of the reference leg No effect will be seen since the transmitters are temperature compensated No effect will be seen since the transmitters are-located in the electrical penetration rooms ANSWER: B MISCINFO:
REFERENCES: OP MC-PS-ILE LESSON: OP MC-PS-ILE TASK: MO-6305 OBJECTIVES: LPRO OBJ: TIME: 2 MINUTES LPS0 OBJ: KA011000 K6.05 3.1/ REV. DATE: 06/11/91
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6 CENERIC QUESTIONS SSE00R054 Pt(s) .The following plant conditions exist:
- A steamline rupture has occurred inside containment Containment pressure is 4.2 psig Steamline pressure is 700 psig NC system pressure is 1800 psig A steamline-isolation has occurred The low steamline pressure SI has been blocke Which of the following must occur before the steamline
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isolation signal can be reset? It can be reset under-the current conditions Containment pressure must decrease to less than 3 psig Steamline pressure must increase to greater than 775 psig Containment pressure must decrease to less-than 3.psig and steamline pressure must increase to greater than 775 psig ANSWER: MISCINFO:
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TASK: MO 2313
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LESSON: OP-MC STM SM OBJECTIVES : LPRO OBJ: 9 . TIME: -2 MINUTES;
- LPSO 0BJ : -9
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KA039000 K4.05 3.7/ REV. DATE: 06/11/91-
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7 GENERIC QUESTIONS SSE00R083 l 1 Pt(s) Civen the following conditions: Reactor power is 75% Channel N41 is the highest reading Power Range Channel Rod control is in AUTOMATIC Channel N42 instantaneously fails-LOW No operator action is taken Which of the following oescribes the resultant control rod system response? Control rods will drive in at maximum rate Control rods will drive in at minimum rate Control rods will drive out Control rods will not move ANSWER: D MISCINFO:
REFERENCES: OP MC-IC IRX LESSON: OP MC-IC-IRX TASK: M0 3310 i
OBJECTIVES: LPRO OBJ: 3 TIME: 3 MINUTES LPSO OBJ: 3
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KA015000 K3.02 3,3/3,5 REV DETE: 11/13/92.
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8 SCENARIO QUESTIONS SSE09R02-1 Pt(s) Based on present plant conditions, which of the following explains the actual position of the Main Feed Reg Valve for
"A" S/G (1CF 32)? Open since a " Reactor Trip with Lo Tave" signal does NOT exist Full closed due to a Safety Injection signal Full closed due to a Phase "A" Isolation signal Open since "A" S/G level is less than prograta level ANSWER: B MISCINFO:
REFERENCES: OP-MC-ECC-ISE LESSON: OP-MC ECC-ISE TASK: MO-2313 OBJ ECTIVES : LPRO OBJ : IN TIME: 3 MINUTES LPS0 OBJ: IN KA000009 EK3.03 4.1/ REV. DATE: 11/10/92
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9 SCENARIO QUESTIONS SSE09R06
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1 Pt(s) During this event, if the normal incoming breaker (IATD) to
'B' Train Essential Switchgear trips, how would the operation of the 'B' Train NV pump be affected? Pump is load shed and restarts via the sequencer Pump is load shed and must be manually restarted Pump is not load shed and restarts when the D/G breaker closes Pump will trip and " lockout" due to " anti-pumping" circuitry ANSk'ER : A MISCINFO:
REFERENCES : OP MC DC-EQB LESSON: OP-MC DG-EQB TASK: M0-7306 OBJECTIVES : LPRO OBJ: 8 TIME: 2 MINUTES LPSO OBJ: 8 KA064000 K3.01 3.8/ REV DATE: 11/10/92 -
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J 10- SCENARIO QUESTIONS '^
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SSE09R07 1 Pt(s) Based on present plant conditions, what is the approximate .
subcooling margin?
' Greater than or equal to 30'F subcooled
, Greater than 5'F subcooled but less than. 30'F- subcooled - Greater than or equal to 30*F superheated Creater than 5'F superheated but.less than 30'F superheated
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ANSWER: D ,
MISCINFO:
REFERENCES: OP-MC-THF-STM Data Book Curve 1.10B LESSON: OP-MC-IC-ICM TASK: - MO 2304
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OBJECTIVES : LPRO OBJ : 6 TIME: 4 MINUTES LPSO OBJ : 6 KA000009 EA1.16 4.2/ REV. DATE: 11/10/92 ;
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11 SCENARIO QUESTIONS SSE09R08 .;
1 Pt(s) Based on present plant conditions, if the "A"--NV pump were started, which of the following would occur? NV pump flow would increase by greater than 50 gpm and NI pump flow would increase by greater than 50 gpm .-3 NV pump flow would increase by greater than 50 gpm and NI pump flow would decrease by greater than 50 gpm' NV pump flow would increase by greater than 50 gpm and NI pump flow would remain within 50 gpm of it's original flow rate Flow from the NV and NI pumps would remain within 50.gpm of thair original flow rates ANSWER: C MISCINFO:
REFERENCES: OP-MC-ECC.ISE LESSON: OP-MC ECC-ISE TASK: -M0 8301
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OBJ ECTIVES : LPRO OBJ: 1 TIME: 3 MINUTES LPSO OBJ: 1 s
KA000009 EK3.03 4.1/ REV. DATE: 11/10/92
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SSE09R11 6
- 1-Pt(s) Which of the following describes why NC Pump seal flow is higher than normal in the current plant configuration? Due to NC System pressure being low
' Due to NC 241 (Seal Inj . Flow Control) being throttled '
closed too far Due to NC-241 (Seal Inj Flow Control) being. throttled open too far Due to NI Pump flow being so high ANSWER: A MISCINFO:
REFERENCES: OP-MC-PS-NV LESSON: OP MC-PS NV TASK: MO-3305 OBJECTIVES : LPRO OBJ: 3 TIME: 2 MINUTES LPS0 OBJ: 3 KA003000 Kl.03 3.3/ . REV. DATE: 11/10/92
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k, 13 SCENARIO QUESTIONS SSE09R12
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1 Pt(s) Based on present plant conditions, why are ALL RV' Pumps running?
The RV Pumps receive an auto start signal: From the load sequencer RB, Due to high containment temperature Due to all four VU (Upper Containment) units running Due to low RN non-essential header pressure ANSVER: D MISCINFO:
REFERENCES: OP-MC-CNT-RV LESSON: OP-MC CNT-RV TASK: MO-8302 OBJECTIVES: LPRO OBJ: 5 TIME: 3 MINUTES LPSO OBJ: 5 KA000062 EK3.02 3.6/3,8 REV-, DATE: 11/10/92
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14 SCENARIO QUESTIONS SSE09R13 1 Pt(s) Based on present plant conditions, which of the following describes the status of the Turbine Driven CA Pump?
A, The Turbine Driven CA Pump received no automatic start signal and therefore should not be running The Turbine Driven CA Pump should have started based en S/C levels The Turbine Driven CA Pump should have started based on WPT's status The Turbine Driven CA Pump should have started due to the safety injection signal ANSUER: A MISCINFO:
REFERENCES: OP-MC CF-CA LESSON: OP MC-CF-CA TASK: MO-2313 OBJECTIVES: LPRO OBJ: 5 TIME: 2 MINUTES LPSO OM: 5 KA000009 EAl.ll 4.1/ REV. DATE: 07/10/91
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15 - SCENARIO QUESTIONS SSE09R14 1 Pt(s) Which of the following statements describes steam dum operation under current plant conditions? Both condenser steam dumps and atmospheric steam dumps will modulate if temperature errorois high enough B, Only bank one (1) of the condenser steam dumps.will modulate regardless of the temperature error C. -Both banks of condenser steam dumps will modulate based on temperature error Both banks of condenser steam dumps will modulate based on steam header pressure being compared to the steam dump M/A station setpoint ANSWER: C MISCINFO:
REFERENCES: OP MC STM IDE LESSON: OP MC-STM-IDE TASK: MO-3318 OBJECTIVES : LPRO OBJ : 1 TIME: 2 MINUTES LPS0 OBJ: 1 KA041020 A3.02 3.3/ REV. DATE: 11/10/92
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16 SCENARIO QUESTIONS SSE09R17 1 Pt(s) Based on present plant conditions, if the Source Range select switches'(A&B).were " Reset" what would occur?-
A. The SRM's can NOT be energized in this condition B. Both SRM's would energize and peg high C. Both SRM's would energize and indicate on scale D. Neither SRM would energize; but "Hi Flux at S/D" alarm; would actuate ANSWER: B MISCINFO:
REFERENCES: OP-MC IC-ENB LESSON: OP-MC-IC-ENB TASK: MO 2302 b OBJECTIVES : LPRO OBJ: 4 TIME: 2 MINUTES LPS0 OBJ: 4 i
KA015000 A3,03 3,9/3,9 REV, DATE: 11/10/92
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