ML20246E877
| ML20246E877 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 08/16/1989 |
| From: | Brockman K, Curtis Rapp NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20246E857 | List: |
| References | |
| 50-369-OL-89-01, 50-369-OL-89-1, NUDOCS 8908300050 | |
| Download: ML20246E877 (187) | |
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@f!Eloq UNITED STATES '
f' 4, NUCLEAR REGULATORY COMMISSION.
, , [l ns REGION ti p
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- ,j. 101 MARIETTA STREET, N.W.
't . ATLANTA, GEORGI A 30323
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ENCLOSURE l' i
REPORT DETAILS Facility Licensee: Duke Power Company McGuire Nuclear Station
'P. O. Box 448
.Cornelius, NC 28031 Facility Docket Nos.: 50-369 and 50-370 Facility License Nos.: NPF-9 and NPF-17 Examinations were administered at the McGuire huclear Station near Charlotte, i North Carolina.
Chief Examiner: dmf '[2%.~ S//4 /B 7 j Curt Rapp.. ' / Dhte Signed ;
Approved By: Mbw/$w#
jfen Brochhan,fhief 8//s/S9 Date Signed
/ Operator LicFnsing Section 2 i Division of Reactor Safety .j i
Summary:
~1 Examinations were conducted on June 26 - 30, 1989.
4 Written and operating examinations were administered to six R0 applicants and five SRO applicants. Based on the results of these examinations, all applicants
' passed.
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4 l-l 8908300000 890BP3 !
, PDR ADOCK 05000369
(. V PNV
1 REPORT DETAILS
- 1. Facility Employees Contacted:
- B. Travis, Superintendent, Operations
- D. Baxter, Operations Support Manager D. McGinnis, Director, McGuire Nuclear Training
- C. Majure, Senior Nuclear Instructor
- B. Griffin, Senior Nuclear Instructor K. Carnely Operations Nuclear Instructor S. Helms. Operations Nuclear Instructor
- H. Deal, Operations Nuclear Instructor
- L.'Massey, Operations Coordinator
- D. Arndt, Operations Nuclear Instructor R. Pope, Assistant Shift Supervisor
- Attended Exit Meeting
- 2. Examiners:
- C. Rapp A. Lopez, PNL M. Lintz, PNL G. Benjamin, PNL K. Van Doorn, Senior Resident Inspector (Exit Only)
- Chief Examiner
- 3. Pre-administration Examination Review A pre-administration review of the written examination was conducted by representatives of the facility. The purpose of this review was to correct any technical inaccuracies in the examination prior to adminis-tration. Many of the comments addressed psychometrics changes to the examination. One question on testing of E0P bases was challenged but was resolved to the satisfaction of the reviewers.
- 4. Exit Meeting An exit meeting was conducted on June 30, 1989, with facility represent-atives. Several generic issues were discussed and are presented below.
Several candidates were confused about the effect of the control l room and local speed control potentiometers on TD CA pump speed during a Blackout Signal. Additionally, control room procedures were inadequate for local starting of the TD CA pump. l f
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-.Several SR0 candidates demonstrated unfamiliarity with the Emergency Plan Event Classification procedure and failed to properly classify events.
The turbine building deluge valve manual operators are covered by_
insulation. This prevents resetting of the valve as directed by procedure.
The table identifying the containment isolation valves covered by Technical Specification 3.6.3 has been removed from Technical Specifications and placed in the FSAR. There is no reference to the FSAR.-in Technical Specifications and there is not a copy of the FSAR in the control room. Additionally, some copies of Technical Specifi-cations still refer to this table.
A significant number of simulator deficiencies were noted during examination development and administration. These deficiencies are detailed in Enclosure 5 of this report. None of these deficiencies were identified by the facility to the examiners as required in ES-201.
During the control room examinations, several instances of failure to acknowledge control room alarms were observed. In one 4 stance, an alarm remained unacknowledged for approximately 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.
During the simulator examinations, the candidates relied entirely on the OAC to verify 51 alignment. When the OAC was failed, the candidates demonstrated confusion on how to manually verify 51 alignment.
The Technical Specification Reference Manual is in poor physical condition with several pages torn or completely loose.
The Key Control procedure refers to Orange Tag keys even though these keys are no longer used.
The cooperation extended to the examiners was noted and appreciated.
The facility did not identify any material as proprietary to the examiners.
- 5. Generic Weaknesses Noted During Examination Grading Several weaknesses were noted as a result of examination grading. This could be indicative of training weaknesses. These weaknesses are detailed below.
When asked for three (3) reasons for terminating SI as directed by EP/1/A/5000/14.1, both R0 and SRO candidates con >1stently gave " prevent l refilling the pressurizer solid." This response indicates the candidates 1
failed to recognize this ccndition would cause uncontrolled repressuriza-tion. Repressurization was given as a separate response.
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Several R0 candidates failed to recognize the source range detectors are l poly-lined. This would act to thermalize neutrons resulting in an increasing countrate as downcomer void fraction increased.
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3 Several R0 candidates exhibited confusion between the operation of the steam dump load rejection controller. and the turbine trip controller.
When asked to calculate and identify the QPTR, only one R0 candidate correctly stated the highest QPTR value. All other candidates stated all QPTRs that exceeded Technical Specification limits, but failed to identify the highest QPTR as most limiting.
Several SR0 candidates could not correctly state the indications of steam generator dryout during adverse containment conditions.
Several SR0 candidates falsed to recognize the mechanisms used to reduce NV system activity prior to cooldown.
Several candidates stated block tagouts are used only for system isolation instead portions of the plant which may encompass more than one system.
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'U. S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION REGION 2.
FACILITY: McGuire 1 & 2 REACTOR TYPE: PWR-WEC4 DATE ADMINISTERED: 89/06/26 l CANDIDATE: '#4ST## /i/V
-INSTRUCTIONS'TO CANDIDATE:
Use separate . paler for the answers. Write answers on one side only.
Staple question sleet. on top of the answer sheets. Points for each question are' indicated in parentheses after the question. The passing grade requires at least 70% in each category and a final grade of at least 80%. Examination papers will be picked up six (6) hours after the examination starts.
. % OF CATEGORY % OF CANDIDATE'S CATEGORY.
VALUE TOTAL SCORE VALUE CATEGORY 25.00 2S.00- 1. REACTOR PRINCIPLES (7%)
THERMODYNAMICS (7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM).
i 27.00 27.00 2. EMERGENCY AND ABNORMAL PLANT EVOLUTIONS (27%)
48.00 -::1.00 3. PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC RESPONSIBILITIES (10%)
1 100.00 % TOTALS FINAL GRADE All work done on this examination is my own. I have neither given nor received aid, f
Candidate's Signature
)
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- 1. REACTOR PRINCIPLES (7%) THERMODYNAMICS-(7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM)
QUESTION 1.01 (1.00).
HOW will indicated pressurizer level' compare to actual pressurizer level during a high-energy line break that raises containment temperature from 100 degrees F to 180 degrees F? Assume normal instrument operation. (1.0)
(a.) Indicated pressurizer level will be lower than actual pressurizer _ level.
(b.) Indicated pressurizer level will be equal to actual pressurizer level.
(c.) Indicated pressurizer. level will decrease to zero.
(d.) Indicated pressurizer level will be higher than actual pressurizer level.
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L1. REACTOR PRINCIPLES; (7%)- THERMODYNAMICS -
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.(7%)-AND COMPONENTS (11%) (FUNDAMENTALS EXAM)
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$ QUESTION: 1'.'02 : '(100)
A control rod has-its greatest differential reactivity' worth 'if.it .is
' inserted in WHICH ONE (1) .of the following locations? '(1.0)
(a.) At the edge of the core.
(b.) At'the center'of the core, t
(c.)- In a high Xenon concentration area.
$ '(d.) In'a low fuel ' concentration area.
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1; ' REACTOR PRINCIPLES (7%)' THERMODYNAMICS Page 6 (7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM) t 1
QUESTION 1.03 '(1.00)
WHICH ONE (1) of the following sentences describes why the moderator temperature coefficient becomes more negative from BOL to EOL7 (1.0)
(a.) A decrease in the fuel to clad gap over core age.
results in a decrease in the fuel temperature.
(b.) Boron concentration is reduced durin maintain power and as the core ages,g coreproduct fission life to poisons build up.
(c.) Plutonium build-up over core age results in more fissionable material being available to compete with boron atoms for neutrons.
(d.) Rod' withdrawal-causes T-ave to increase, decreasing moderator density, and allowing neutrons to travel farther, until they are absorbed by the rods.
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!. REACTOR PRINCIPLES (7%) THERMODYNAMICS-(7%) AND COMPONENT 5 (11%) (FUNDAMENTALS EXAM) w
-QUESTION 1.04- (1.00)
WHICH ONE (1) of the following statements does NOT describe why rod (1.0) insertion limits are maintained during reactor operations?
.(a.) To' augment the effects of the moderator temperature coefficient over core life.
(b.) To reduce the positive reactivity addition caused by an ejected rod.
-(c.) To produce an axial ~ flux' distribution that prevents high -
local peak power levels.
(d.) To compensate for the effects of the power defect following a reactor trip.
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$1. - REACTOR PRINCIPLES (70 THERMODYNAMICS (7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM)
QUESTION 1.05 (1.00)
During a reactor start-up,- an initial reactivity addition causes count rate to increase from 20 CPS to 40 CPS. A second reactivity 4 addition causes the count rate to increase from 40 CPS to 80 CPS.
WHICH ONE (1) of the in11owing statements is CORRECT 7 (1.0)
'(a.) Thefirstreabthityadditionwassmaller.
(b.) The second reactivity addition was smaller.
(c.) The first and second reactivity additions were equal.
(d.) There is insufficient data given to determine relationship of reactivity values.
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! QUESTION'it.06: . (1~.00) .
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h E WHAT! are.TWO:(2) physical characteristics 'ofi the fission product ' .. ..
~ Xe-135 that make it-a major concern during reactor operation?. :(1.0) v F"
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- QUESTION: 1.07: (1.00). .i WHICH ONEL (1)? of thel following circumstances lis-likely to. cause ~ .. '
l(1.0) water hammer?. ~
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(a.) . . Maintaining the. discharge'line of a pump filled with fluid.
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.(b.) [ Water collecting in a steam.line. ,
l(c.) ' Pre-waming 'of steam' lines.
(d.) . Slowly closing the discharge valve of an operating pump.
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/ - i . RE' ACTOR PRINCIPLES-(7%) THERMODYNAMICS
, .(7%) AND COMPONENTS (11%) (FUNDAMENTALS' EXAM) j QUESTION'L1.d8)(1.00) 5 - -When positive reactivity is'added by a step outward rod motion to an exactly critical reactor,.a transient. start-up-rate is. observed.
To,WHICH ONE,(1)'of the following-is this'" attributed? (1.0) .- .
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-(a.); ' A delayed. critical condition.
- (b.) .: ~A prompt jump condition.
.(c.)' A prompt critical-condition.
(d.) 'A' prompt drop condition.
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1 Page 12 T1. REICTOR PRINCIPLES (7%) THERMODYNAMICS (7%) AND COMPONENTS (11%) (FUNDAMENTALS' EXAM)
I x.y s QUESTION .1.09 _(1.00) 9 -WHICH ONE- (1)' of the following operating limits is based on ' <
minimizing the probability 'of brittle fracture? - (1.0) 39 (a.). Steam generator. temperature limit. _
(b.). Cooldown rate limit.
. (c.) . l Criticality curve limit..
(d.) T-ave limit. .
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- 1. ~ REACTOR l'RINCIPLES (7%) THERMODYNAMICS-
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.(7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM) t l
l QUESTION 1.10 (1.00).
WHICH ONE-(1) of the following sentences describes the reason for the height correction factor-(K(Z)) used in the heat flux hot channel (1.0) factor calculation?
(a.). K(Z)' compensates for the increased coolant temperatures that occur higher in the coolant channels.
.(b.) K(Z) takes into account that there is some delay in refilling.the core following a LOCA.
(c.) K(Z)isanuncertaintyfactortoallowforconservatism, since core' flow cannot be accurately measured.
-(d.) K(Z) allows for greater power production in the upper regions of the core near the end of life, due to axial flux shifting.
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- 1. ~ REACTOR PRINCIPLES (7%) THERMODYNAMICS (7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM)
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QUESTION 1.11 (1.00)
WHICH ONE (1) of the following statements explains why DNB is NOT a concern on.the secondary side of the steam generators,- if DNB were (1.0) to occur?
(a.) The secondary side has a lower nucleate void fraction.
(b.) The secondary side has a higher flow rate.
.(c.) The temperature is limited.
(d.) The heat transfer is more efficient.
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- 1. REACTOR PRINCIPLES (7%) THERMODYNAMICS Page 15 (7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM)-
QUESTION 1.12 (1.00)
WHICH ONE (1) of the following changes in plant parameters will result in a DECREASE in the shutdown margin? (1.0)
(a.) power level is decreased from 40% to 30% with no rod motion and constant boron concentration (b.) shutdown banks are withdrawn during startup while.
' maintaining constant NC temperature and boron concentration (c.) bank D rod height is increased from 125 steps to 200 steps while maintaining constant power and boron concentration (d.) boron concentration is decreased while maintaining constant power and no rod motion
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- 1. REACTOR PRINCIPLES (7%) THERMODYNAMICS Page 16 (7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM)
QUESTION 1.13 (1.00)
WHICH ONE (1) of the following phrases CORRECTLY completes the sentence?
In the condensate system, the operating point for two pumps operating in parallel will be at as compared to the operating point when one pump is operating and the other pump is isolated. (1.0)
(a.) the same flow rate and the same discharge pressure (b.) a higher flow rate and the same discharge pressure (c.) a higher flow rate and an increase in discharge pressure (d.) the same flow rate and an increase in discharge pressure l
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- 1. REACTOR PRINCIPLES (7%) THERMODYNAMICS-L {7%) AND COMPONENTS-(11%) (FUNDAMENTALS EXAM)
QUESTION 1.14 (1.00)
.WHICHSuction Head. NPSH) is CORRECT 7 ONE -(1)(of the following statements about pump Net (1.0) Positive (a.) NPSH is the amount by which the. saturation pressure is i
greater than the' suction pressure for the water being l pumped.
, ; (b'.) When~a pump is started, the NPSH will be reduced by the amount of.the pressure drop in the suction piping.
.(c.) NPSH is essential for operation of centrifugal pumps but not for positive ' displacement pumps.
(d.) NPSH can be calculated by subtracting the suction pressure from the discharge pressure.
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M (7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM)
-QUESTION -1.15 (1.00).
'Concerning'the mixed bed domineralizers:
- a. WHAT is the' maximum flow that each demineralized is sized -
- .to' accept? (0.25)
- b. HOW are demineralized resins protected from high temperatures?-
INCLUDE setpoint. (0.75) l l
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.-1. 1 REACTOR PRINCIPLES (7%) THERMODYNAMICS (7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM)-
QUESTION' .1.16 ' -(1.00)
WHICH.ONE (1) of'the following radiation types is the~ type that is primarily measured by~a.self reading poc at' dosimeter'l . (1.0) -
..(a.): ; alpha.
(b.): beta ,
l(c.): ; gamma' -
- (d.)- neutron o
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- 1. REACTOR PRINCIPLES (7%) THERMODYNAMICS (7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM)
QUESTION 1.17 (1.00)
WHICH ONE (1) of the following statements correctly describes the effects of post-transient downcomer voiding on source range detector response? (1.0)
(a.) Source range level increases with increasing downcomer void fraction.
(b.) Source range level decreases with increasing downcomer void fraction.-
(c.) Source range level initially increases as downcomer void fraction increases, and then decreases when downcomer void fraction becomes exceptionally large.
(d.) Source range level initially decreases as downcomer void fraction increases, and then increases when downcomer void fraction becomes exceptionally large.
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.(7%) AND COMPONENTS (11%)-(FUNDAMENTALS EXAM) j; i
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l QUESTION' '1.18- (1.'00)
WHICHONE-(1)'of.thefollowingdescribesHOW1etdownsystemUPSTREAMl
- ". ;.: pressure and flow pressure ,letdevn rate control are.(NV-124 valve affectedanby) manually additional closing the NV 10%?? ' low-
-(1,0).
4 (a.) oressure decreases and ftow rate increases.
pressure decreases and flow rate'. decreases o-
-(b.)4 (c.) ' pressure increases-and flow-rate decreases =
_(d.) .
pressure. increases and flow rate increases 1
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- 1. REACTOR PRINCIPLES'(7%) THERMODYNAMICS (7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM) p
. QUESTION- 1.19 ( 1.00)
WHICH ONE (1) of the following statements regarding centrifugal pump:
cavitation..is NOT correct? (1.0)
(a.).- Cavitation is the formation and subsequent collapse of vapor bubbles in the liquid flowing through a pump.
(b'.) If available net positive suction head (NPSH) is positive, cavitation will not occur.
(c.) The point where cavitation is most likely to begin is the high pressure discharge area of the pump.:
(d.) Undesirable consequences of cavitation may include erosion and pitting of the pump impeller, reduced flow rate being maintained.by the pump, and damage from excessive vibration.
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.LQUESTION 1.20. '(1.00) iNCP"LimitsandPrecautions" states"withinanytwo;h6urperiod}-. the' number of
- with a minimum idle period of thirty. (30); minutes prior to restart."
WHAT is,the basis for this precaution?- (1.0)-
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$1 LQUESTION' 11.21. .(1.00)
Transferring energy from the fuel to the reactor coolant requires; several different. types of. heat' transfer..
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WHICHONE(1):ofthe.followingstatementsisCORRECT7 (1.0)'
. (a.). . Heat transfer through.the fuel pellet'is via convection.
(b.)- Heat transfer across the.zire clad is via convection.
(c.). Heat transfer across the laminar water. layer (nearest fuel) is via conduction.-
'(d.) ' Heat transfer.from the laminar film into the bulk of the coolant is'via conduction.-
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..'s--REACTORPRINCIPLES(7%ITHRM0 g(7%) AND COMPONENTS (11%),(FUNDAMENTALS EXAM)
DYNAMICS.
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- QUESTIONf '1.22 ? .(1 LOO)'-
WHATiaeTWO.(2)_purposesofthePZRPORVs? (1.0)
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- II2 REACTOR-PRINCIPLES:(7%) THERMODYNAMICS (7%) AND COMPONENTS (11%)'(FUNDAMENTALS EXAM)
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I b' . : QUESTION. 1.23.-(1.00)
!" WHICH ONE (1) of the follo. wing parameter changes' would cause the
- outlet-> temperature of the KC system heat exchangers to DECREASE?-
. Assume.all.other parameters are held constant. (1.0).
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- .(a.) .A decrease in the NCP thermal. barrier temperature.
K (b.) An-increase in KC system pressure.
- (c.) A decrease in the sealwater heat exchanger temperature.
An increase in RN system flow.
-(d.)
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- 1. REACTOR PRINCIPLES (7%) THERMODYNAMICS- Page 27 (7%) AND COMPONENTS (11%) (FUNDAMENT ALS EXAM)
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. QUESTION 1.24 (1.00)
L WHICH ONE (1) of.the following statements is CORRECT concerning l
.the intermediate range compensated ionization chambers? (1.0)
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(a.)' The boron lined chamber is sensitive to neutron and gamma radiation, while the unlined chamber is sensitive only to gamma: rays.
(b.) The compensated ion chamber is designed to remove the gamma signal only at high reactor power levels.
(c.) Undercompensation will cause loss of some neutron current, as well as blocking gamma current.
(d.) Gannas that penetrate' the detector's lead shielding will cause ionization which results,in a voltage pulse.
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- , 1.- REACTOR-PRINCIPLES'(7%) THERMODYNAMICS-(7%) AND COMPONENTS (ll%) (FUNDAMENTALS EXAM)
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- QUESTION l l1.25 ((1.00h y
'.WHAT must be done to an engineered safeguards. valve after it has'.
been' manually operated 7 (1.0).
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b , 2? EMERGENCY AND ABNORMAL PLANT EVOLUTIONS-(27%)
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' QUESTION 2.01- -(1.00)"
H J" 'WHICH;0NEL(1) of the:following is' NOT an immediate operator action-for-EP/1/A/5000/09 " Loss of All AC Power"? l(1.0) p' ,
_. ( a . )Manually
- exercise Rx Trip Train 1A and IB switches.
(b.) Verify CA flow - greater than 450 gpm.
(c.)f Try to energize 4160 v bus with D/G from control' room.
,, 1(d.)' Initiate NC pump seal injection from SSF per procedure.
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QUESTION 2.02.L.(2.00)-
According to'EP/1/A/5000/2.2 " Post-LOCA Cooldown and Depressurization"-
foldout page, WHAT are FOUR (4) conditions ^that indicate that natural circulation flow is occurring? INCLUDE parameter and expected conditions. ASSUME containment conditions are normal. (2.0) 4 t
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i 2. Page 31 EMERGENCY AND ABNORMAL: PLANT EV0 Lilt 10NS.
j.; 3:.(27%)
t
. QUESTION 2.03 (1.00)
Inaddition' tot /CsNOTlessthan1200degF,WHICHONE(1)ofthe.
following also represents a red path for core' cooling assuming
,subcooling is less than zero?- (1.0)
At Least One RVLIS
~RCP Running Core Exit temperature : Vessel Level l .
(a.) no greater than 700 deg F' greate:.- than 43%
(b.) yes- less than 700 deg'F greater than 43%
(c.) no greater than 700 deg F less than 43%
(d.) yes .less than 700 deg F less than 43%
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- 2. EMERGENCY'AND-ABNORMAL PLANT EVOLUTIONS (27%)
1 QUESTION 2.04 -(1.50)~
As a result of a steam line break, you are directed to EP/1/A/5000/14.1,
" Response to Imminent Pressurized Thermal Shock Conditions," due to a-red path condition on an excessive cooldown rate.and NC system pressure limits. Step 10 of_this EP has you terminate SI, if the-SI termination
~ criteria is met.
STATE THREE'(3) reasons for terminating SI. (l'.5) 4 1
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- 2. : EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 33~
-(27%)
77
' QUESTION' 2.05' '(2.50)
,'< While performing.PT/1/A/4600/01, "RCCA Movement Test," a control w rod is dropped.
o a ca' ' STATE.THREE (3); indications or alarms.that would show such 3
- an event. occurred. (1.5)
P>
- b. WHAT are ALL-the immediate. actions that must be taken according -
to AP/1/A/5500/14, " Rod Control Malfunctions?" (1.0)-
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4- t . 2. : E'MERGENCY 'AND- ABNORMA1. PLANT EVOLUTIONS'
', .(27%)
l QUESTION 2.06l (1.50). ,
WHAT are:FIVE-(5) conditions that-require emergency boration (1.5);
3 according to.AP/1/A/5500/38,." Emergency Boration?"
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2 EMERGENCY ~AND' ABNORMAL PLANT EVOLUTIONS
, (274)
, QUESTION. 2.07 (2.00)
-Unit 1 just experienced an ATWS. 'The turbine did not trip following manual trip of the reactor. WHAT actions'are you required to take according to'EP/1/A/5000/11.1, " Response to Nuclear Power Generation /
ATWS," if a manual turbine trip .is ineffectual--(i.e., the. expected ~
response is not obtained)? (2.0) n l _
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v 2. EMERGENCY AND ABNORMAL PLANT EVOLUTIONS' hage36
.(274) i QUES 110N 2.08 (1.50)
If a control rod in bank D is verified to be misaligned, you are required to position that rod to within +/- 12 steps of the remainder of the bank in accordance with AP/1/A/5500/14, Rod Control Malfunctions, Case IV Control Rod Misalignment.
STATE THREE:(3) power distribution limits against which this action protects. (1.5) he
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i W ' 22 #EMERGENCII AND' ABNORMAL PLANT EVOLUTICas;: q.. Page 37::
F :(27%)-
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, . 1QUF.STIONLl239 (0.50)-
n
!If Unit:1. trips.due to a loss of off-site power. The R0 tries to
.connence NC cooldown using' the steam dumps in the steam aressure control mode, butiis unsuccessful. : EXPLAIN the reason t1at the isteam dumps do not open.. (0.5)
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1 Page S$'
~ 2. EMERGENCY AND ABNORMAL' PLANT EVOLUTIONS (27%).
":o
[ QUESTION' 2.10 -(1.00)
WHICH ONE'(1) lof the following statements concerning containment sump isolation valves following SI is CORRECT 7 (1.0)
(a.)' ' the containment sump. isolation' valves will automatically .open on low level alarm ~from the FWST.
(b.) unless bypassed, the containment sump isolation valves will NOT open unless.the ND pump suction valves'(from FWST) are closed.
-(c.) the containment sump isolation valves will NOT open unless tne containment _ sump reaches the interlock level.
(d.) the containment sump isolation valves will automatically open IF the ND pump suction valves (from FWST) are opened.
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- 2. EMERGENCY AND ABNORMAL PLANT EVOLUTIONS g (27%)
w
, s I, ; QUESTION! 2.11 '. (2.00) '
' Assume.McGuire Unit l'nas suffered a large SG tube rupture that.
s results in. a reactor trip and SI, actuation. In. addition to high L . activity levels in. the-secondary:
~
s "a. WHAT are TWO (2)'SG' indications that can be used to determine (1.0) which SG has a tube rupture?
- b. STATE TWO.(2) reasons why. isolation of the SG is necessary.' (1.0)'
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OS ' Paga.40 j-i~ , -2r EMERGENCY AND' ABNORMAL-PLANT EVOLUTI N -
p (27%)
I
- ' 2.12:_ (1.50) a (QUESTION y
e' JIn'accordance with EP/1/A/5000/02, "High Energy _Line Break Inside li ' ' Containment," foldout.page: -
'e s
..W HAT are the NC pump trip criteria?
~
(1.0).
- a. .
e
- b. ' WHAT is the' reason for' tripping the NC pumps when the. trip _
,,, (0.5) criteria.are met?
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[& 72. EMERGENCY AND ABNORMAL-PLANT EVOLUTIONS
'(27%)-
l- ,
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p, Q!!ESTION 2'.13 '(0.50)
Unit'l_is experiencing high radiation that forces Control Room.
E evacuation be fore the, reactor can be trip)ed. In accordance with'
' AP/1/A/.5500l17,- " Loss of Control Room," tie RO~ at the reactor trip switchgear~will trip the reactor DNLY after WHAT condition ~
is met?
(0.5).
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' Jl ' !2.'EMERGENCYANDdBNORMALDLANTEVOLUTIONS
.. : + . ,
(27%),
g pg. ,
4 -u
-QUESTION. 2.14- (1.00)
.STNTE'FOUR(4)'syytomsthatwould'indicatesteam.generatortube leakage','-in accort nce with AP/1/A/5500/10. . Symptoms from duplicat'e
- p. :. components.will-NO.. receive duplicate credit
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Page 434
',$,,$2/2.' EMERGENCY.'ANDABNORMALPLANTEVOLUTIONS' (27%)
i i QUESTIONL 2.15'-(l'.00).
4: ' STNTE TWO.'(2): sources of'e.onormally_high activity-in the reactor..
, coolant.
(1.0) q' 1
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M 2.- EMERGENCY AND ABNORMAL PLANT EVOLUTIONS-(27%)-
lr QUESTION 2.16- (2.50)-
'WHAT are FIVE (5) conditions th'at indicate that natural circulation.
flow.is occurring,-according to EP/1/A/5000/22,." Post-LOCA Cooldown.
.-and Depressurization" foldout' page? INCLUDE parameter and. expected ~ (2.5)'
condition. ASSUME that containment conditions are normal.
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Page 45
.2a. EMERGENCY AND'ABWORMAL PLANT EVOLUTIONS (27%)
n
.N-l' lQUE.5 TION .2.17- (1.00)
Fill.in the' blank.
.The Auxiliary Building and both containments have air headers that supply air only to those components required to maintain
. hot standby. .There is also a tie to these headers from the diesel air start headers through normally closed solenoid valves. These solenoid valves must receive a (I.0)
-signal and a signal to open.
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Page 46 S 20 EMERGENCY AND ABNORMAL PLANT EVOLUTIONS'
~
(27R n-p QUESTIONI 2.18 -(1.00)-
Unit 1 is.in Mode I when you notice decreasing pressurizer level
' and:the following. alarms: NC PUMP SEAL WTR L0 FLOW, REGEN HX LETDN-HI. TEMP, and LETDN HX OUTLET HI. TEMP. All other plant parameters-are normal.. WHICH ONE (1) of the following' plant conditions l': correctly describes these conditions? (1.0)
(a.) 'Pzr PORV has failed open.
SBLOCA,.
(b.).
(c.) Letdown has-isolated.
(d.) Charging has been lost.
3
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Page 47
- 2. EMERGENCY AND ABNORMAL PLANT EVOLUTIONS (27%)
i QUESTION- 2.19 (2.00)
'AP/1/A/5500/01 " Reactor Trip," step 5, verifies.SI Status,
- a. STATE THREE-(3) indications that you have to verify to ensure that.SI.is NOT. required. INCLUDE in your answer the applicable setpoint condition of each indication. (1.5)
- b. STATE ONE (1) indication that you would have to verify to ensure that SI'is NOT actuated. INCLUDE in your answer the required condition of the indication. (0.5)
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Page 48-
-31 PLANT' SYSTEMS'(38%) AND PLANT-WIDE G NE ERIC L RESPONSIBILITIES (10%)
' QUESTION' 3.01 -~ '(1.00).
W'HICH ONE (1) of'the following is the correct sequence of CA suction
-supplies for the turbine driven CA pump, in order of preference?- - (l'.0) .
E' _( ad AFW condensate storage tank,~ nuclear service water, upper.
o surge tank
, (b.). upper surge tank, nuc1 car service water, AFW condensate -
P storage. tank i o
~(c.) AFW condensate storage tank, hotwell, nuclear service water-(d.)' upper surge tank, hotwell, AFW condensate storage tank
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Page 49: ]'
' St ', ,
! 3'. PLANT SYSTEMS-(3B%) AND' PLANT-WIDE GENERIC:
RESPONSIBILITIES (10%)
x-
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QUESTION 3.02 (1.00)
'- WHICH'ONEl(1) of the following would cauce the CLA discharge -
" Lisolatien. valves to' receive an open signal? (1.0)3 1-
-(a.)i 'a:safetyfinjection. signal
- (b.) .anLautomatic diesel generator start -
'(c.) ' a blackout: signal
((d.) NC. pressure increasing above 1955 psig n
(
)
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-3. ' 8%) AND PLANT-WIDE GENERI'C PLANT SYSTEMSfI[L GO%)
RESPONSIBILITY i
4 QUESTION 3.03: (1.00)
As reactorLthermal power is increased,:the rod insertion limits ;(RILs).
are-required to'be progressively higher. From'WHICH ONE (1)_of the following parameters is the control rod bank low alarm determined?. (1.0)-
'(a.) .auctioneered high Tave (b.) tauctioneered high Tref'
~(c.) auctioneered high NI power level l(d.) auctioneered high delta t
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- 3. ' PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Page 51 RESPONSIBILITIES (10%)
- QUESTION 3.04 (1.00)
'In the diesel generator " Limits'and Precautions" section, it -
states, "The diesel generator must not be_ idled or its speed reduced-for extended periods of time under any conditions of operations." WHAT is the concern for operating the diesel generator at reduced speeds?l .(1.0).
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'Page 52-
- - 3. - ' PLANT SYSTEMS (38%) AND PLANT-WIDE GENERI'C RESPONSIBILITIES (10%)
s
._ QUESTION 3.05 _(1.00)
~The diesel' generator, during an automatic start, must be
~
. capable of accepting the loads assigned by the sequencer, '
(1.0).
while maintaining;WHICH ONE:(1) of the following conditions't (a.). 75% voltage'and 75% frequency.
(b.). 75% voltage and 95% frequency
- (c.)1 95% voltage and 75% frequency a
(d.) 95% voltage and 95% frequency l
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D Page 53 L 3.. PLANT SYSTEMS'(38%) AND PLANT-WIDE GENERIC- -
RESPONSIBILITIES (10%)
{
r QUESTION.' 3.06 (1.00)
WHICH ONE (1) of the following describes the plant response to a pressurizer level channel failure? ASSUME Level.I control channel failed LOW, .the system is in automatic, no operator action is taken, and the-reactor is at 100% power. (1.0) i:: ,
-(a.) Charging flow decreases, actual level decreases, letdown g
isolates, and the level stabilizes at setpoint.
(b.) Charging flow remains the same, letdown flow temperatures
' increase, backup heaters . turn on if actual level increases
. greater than 5% above program.
'(c.) Charging flow increases, actual level increases, letdown l.
isolates, and the reactor trips on high pressurizer level.
(d.) Letdown isolates, heaters turn off, pressurizer pressure decreases, and the reactor. eventually trips on low
~
pressurizer pressure.
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!? 'c 31.. >. :PLANT SYSTEMS (38%): AND PLANT-WIDE GENERIC.-
RESPONSIBILITIES (10%)
- s
h, s
, -;m : QUESTION 3.07i:(1.00).
.(
In accordance with OP/1/A/6450/15, " Containment Purge System,"'
Y Limits and Precautions, STATE the. reason that it is important
.to. ensure that the purge mode selector switch.is returned to~
..'" '(1;0);
the
- Normal" position after refueling..
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Page 55
- y. 3. PLANT' SYSTEMS'(385) AND PLANT-WIDE GENERIC
-RESPONSIBILITIES (10%)_
t-QUESTION 3.08 ' (2. 50) .'
In accordance with AP/1/A/5500/10, NC System Leakage Within Capacity of Both NV. Pumps," (Case I, Steam Generator Tube Leakage):
a.- STATE WHICH radiation monitors'would indicate a primary to.
secondary leak. (1.5)
- b. Primary to secondary leakage has been determined to be as follows:
' SG A.- 4 gph SG B - O gph SG C - 22 gph i
SG D - O gph WHAT Technical. Specification limit (s) is/are being exceeded? (1.0)
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- 3. - PLANT SYSTEMS (38%)' AND PLANT-WIDE GENERIC- {
. RESPONSIBILITIES (10%) <
1 l
. QUESTION 3.09- (1.00)
Containment-spray (NS) failed to automatically actuate during a
' steam line break inside containment.
- a. 'WHAT conditions are necessary for automatic initiation of the"
-NS system to occur?. INCLUDE setpoints and coincidences. (0.75)
- b. WHAT pressure is the NS system designed to maintain after all (0.25) of the ice in the. ice condenser has melted?
I
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~ 3.- PLANT SYSTEMS (38%) AND PLANT.' WIDE' GENERIC-RESPONSIBILITIES (10%)-
' QUESTION. 3.101 (l'.00)
MATCH each plant. condition in Column B to the. reactor trip:in Column A' for.which'it provides protection. (1.0)
Column A.- Reactor Trips - . Column B - Plant Conditions.
- a. _ over-power delt'a-T 1. loss of NC system integrity
- b. -over-temperature. delta-T' 2.. loss of heat sink
- c. _ pressurizer'high pressure. 3'. excessive. fuel centerline.-
temperature m
- d. . . steam generator low low-
~ level 4. themal shock
- 5. departure from nuclear boiling
- 6. start up accident
.)
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1 Pcge 58 N L31- PLANTi SYSTEMS (38%)'AND PLANT-WIDE GENERIC RESPONSIBILITIES (10%).
L . ..
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-QUESTION '3.11- (1.00).'
WHICH ONE (1) of the following describes the Automatic Fast Transfer feature associated with the 6.9 KV bus supply breakers? (1.0)-
Mode select' switches in auto, busses in sync...
(a.)- NC pumps in operation on both busses, normal breaker trips, alternate breaker closes..
'(b.). .NC pump in operation on bus power is transferred.from,
- alternate breaker closes, normal breaker trips.:
'(c.)- NC pump inLoperation.on bus being transferred to, normal breaker trips, alternate breaker closes.
(d.) NC pumps in operation on both busses, alternate breaker-closes, normal breaker opens.
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r Page 59 13J PLANTLSYSTEMS (38%) AND PLANT-WIDE' GENERIC L RESPONSIBILITIES (10%)-
f QUESTION '3.12- (1.00)
. -c LWhen synchronizing:the generator to the grid, an operator, of will regulate-turbine speed to slowly rotate the synchroscope.
7f- in the fast (clockwise) direction.
LWHICH ONE (1) of the following aairs of parameters correctly; identifies tho two parameters t1at the synchroscope is indicating >to the operator? (1.0)
(a.)- phase and current differences
. (b". ) voltage and frequency' differences (c.) current and voltage differences
-(d.) frequency and phase differences
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Page 60' 6), , / 3) : PLANTSYSTEMS(3B%IANDPLANT-WIDE' L GENERIC,
-RESPONSIBILITIES D0%).
e I; ' ' 'QUE'STION '3.13} (1.00))
. FILL in the' missing Lpressure. values forlht e 'pressuri zer f( .
L,' (1.0). ,
m protective system.;
N a;.. .PORVs;open, -psig-psig' 4
-bW :high pressure; reactor trip; L psig-c.- low-pressure SI.
." d. - enable' manual SI blocks psig' n
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' [i '-
QUESTION
.3.141 (3.00)-
' :Th'e' plant is operating:at 100%' power with all. control systemsLin automatic. - Feedwater flow channel for.'A" steam generator fails--
high. ' ASSUME no operator action taken.-
e :a.- EXPLAIN HOW=each'of the following is: INITIALLY affected
- Land WHY that affect occurs.*
"I'..i f eed: flow' (0.75)-
a" '
- 2. S/G;1evel .0.75)
(
3..Jsteam flow ~(0.75) o b.: The. reactor subsequently trips. STATE the most probable-
'cause. Specify setpoints ano coincidences. (0.75) 3
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, '[lf.' jyr_ b . 3;cPLANT SYSTEMS ~(38%:?AND' PLANT-WIDE GENERIC l ,
j7, T;-
s
- RESPONSIBILITIES D0%)- , ,
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- 'l., 4 l' QUESTION 3.152?(1.00);
- STATE FOUR"(4) automatic. actions / alignmenth c anges that take place:In:.
(1.0)
- q ,
.the.KC system during'an SI;."-
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~
RESPONSIBILITIES-00%) ,
V
- QUESTIONi.3'.16 -(1.00)
/ ~
! MATCH'the hydrogen concentration'with the appropriate plant-5 condition or VX system condition by placing the number from-Column B next'to the correct letter in. Column A' . (1.0)
Note: a response in Column B may-apply to more than one-condition .in Column A.
- Column A - Condition Column B . Concentration-
- a. The' hydrogen skimmer system 1. 0.35%
assures'a hydrogen concentra-tion of below . 2. 0.5%
1b. Hydrogen-recombiners~are not 3. 3.5%-
placed.in service above
- 4. 4%
c.- THydrogen concentration in containment isfnever allowed -5. 5%
Lto reach .
~
- 6. 6%.
- d. High hydrogen concentration annunciator setpoint is' .
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Page 64 J' .: 3. PLANT SYSTEMS (386 AND PLANT-WIDE GENERIC RESPONSIBILITIES D0%) ,
QUESTION 3.17[ (1.00)
' STATE THREE (3) PRT parameters,.ttiat would indicate .a stuck open (1.5)'
PORV . ..
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Page 65
- 3. PLANT SYSTEMS-MB%) AND PLANT-WIDE GENERIC RESPONSIBILITIES 5 (10%)
[
' QUESTION 3.18 -(2.50) ~
I
- a. WHAT are THREE (3) mechanisms employed in the NV system to reduce the recctor coolant system activity prior to cooldown? (1.5) f WHAT sre the Technical Specification limits far primary f b.. (1.0)
NC activity levels?
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i 43N PLANT SYSTEMS ~ (38%) AND PLANT-WIDE GENERIC ,
p :- ,_ RESPONSIBILITIES (10%)
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3.19 ;(1.50) fi.L 7'" [ QUESTION ,
WHAT are FIVE!(5) conditions that should exist be fore open ing ' (1.5)-
NV-92A (NC~ Pump Seal Bypass Return Header Isolation)?'
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- n. ' s .3. PLANT' SYSTEMS'(38%)-AND' PLANT-WIDE GENERIC-lI l - RESPONSIBILITIES (10%)
W >..
. QUESTION 3.20.- (1.00)
'" While.atl100% power,. firstLstage turbine. impulse pressure channel II ._
zf ails 110w. . ASSUME Tavg-Tref deviation is.8 deg F. . HOW will, this (1.0)
' affect the steam. dump system AND.WHY?>
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-- [_______m._______.____..__ __________.__m_._._____.___.__m -_m__ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _m._m_.m_.__________________._._____m______
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QUESTION. '3.21 ;(1.50)..
H '".:WHAT are THREE!(3) reasons. for the VCT outlet Lisolation'- ~ (1.5) .-
b^ " valves .;(NV-141; . -142)?.
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r'
- 3. PLANT SYSTEMS-(38%) AND PLANT-WIDE GENERIC Page 69 RESPONSIBILITIES (10%)
- u.
' QUESTION _ 3.22' .(1.00)
During, shutdown the low PZR pressure and low steamline pressure.
safety injections are blocked by the operator.. WHICH ONE (1) of the'following describes'what the operator must do to regain this
. protection? (1.0)
(a.)- Lower pressure below P-11..
- (b.) Raise pressure above P-11.
(c.)- Raise steam pressure above 585 psig.
(d.) Increase T-ave to 557 deg. F.
l
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.- 3. PLANT SYSTEMS? (38%)f AND PLANT-WIDE GENERIC -
RESPONSIBILITIES (10%).
-i QUESTION'. 3.23I (1.00)
WHICH ONE (1)iof. the phras'es below correctly completes' the following .
>(1.0) 4: sentence?-
The regulated power supply to KRP.will automatically swap to .its
. alternative source.'if:
(a.)L ' the invertor output breaker is opened..
t (b.). the battery charger fails'.
(c.)' the normal supply to._KRP is de-energized.--
(d.) the battery.is placed on equalize charge.
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' 3.
- p i PLANT! SYSTEMS-(38%) AND PLANT-WIDE GENERIC RESPONSIBILITIES (10%l-0 o-t >
b I _ .' QUESTION : 3.24L . _(1.00)l STATE FOUR (4)? systems 'or components supplied with' cooling water
- (1.0)-
.1 'from the.RC system.
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(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
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b-Page L35 PLANT SYSTEMS!(38%F AND PLANT-WIDE GENERIC
< ' RESPONSIBILITIES-(10%)
t;r ,
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F C'JESTION- 3.25 (0.50)
Fill in the blanks.
[ A'f -
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The condenser steam dunns are designed.to handle (1) .
i-
. total". steam flow,. and t3e atmospheric steam dumps' are designed to
.(0.5)
- handle-(2)- % of total steam. flow...
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j;'!' +k,/'m y3;.. ptANT SYSTEM $iN8%NANDPLANT.WIDEGENERIC l RESPONSIBILITIES 55(10%)
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p; l QUESTION. - 3.26 - -(1.50)
.Given the following-data concerning'the power range nuclear-W instruments (channel N42 is 005):
J.t N43 LN44~
N41 'N42 E ....... ...... ......
v, ......
. 52 mA. 0 '58'mA- 57 mA.
.z upper actual;. reading - 112 :::f, 100 ..,#
9;pp;r.100t. ceiret ' 10' mf, 0 i9 0 56'mA :54 nA-iH . !10werl actual reading' 53 mA 108 me,-
105 ^ 0 112 =^.
g" .f 6 ;r 100% d; e.,t U
,WHAT is the quadrant' power tilt ratio (QPTR)? .SHOW all work. (1.5) 1 1
(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
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LP/1/A/6100/22 ENCLDEUEE 4.3 tA ' TMLE 2.2
- Excore Carrents and Vcitages
' Correlated to 100% Full Foser at various Asial Offsets
. Unit 1 Eycle &
FULL PCWER DETECTOR CURRENTS (MICR0 AMPS) CORRESPONDING TO LETECTOR N-43 DETECTDRN-44 LETEtiDR N-41 DETECTOR N-42 INCORE AX14L B T ~B B T T.- B T.
GFFSET o 195.6 192.4 292.8 215.6 '270.2 289.4 204.4' 266.0
, 30'.0 277.8. 237.5 255.5 216.2 224.7 251.7 211.0 20.0 ~273.7 240.9 236.7 229.6 262.8 259.4
.258.1 245.0 237.3 10.0- 247.7 221.3 226.2 257.3 265.3 - 223.0 248.2 0.0 242.4 303.2 211.6 277.9 e 20B.7 ' 266.8 E32.7- *
-10.0 226.7 285.6 ' 298.4 217.7. 325.1 196.9
-305.9 194.4 2B5.4
-20.0 211.1 347.1 IB2.2 319.0 .
180.0 304.0 202.7
-30.0 195.4 326.2 0.9859 -0.9904 0.9BB0 -0.2B2 -
-0.9673
~- r* 0.9567 -0.9894 0.9895 S.
NORMALIIED DETECTOR VOLTAGES (VOLTS 1 AT VARIOUS AIIAL GFFSET DETECTDR H-43 DETECTOR N-44 DETECTOR N-42
~
INCDRE DETECTOR N-41
~
A!!AL T B T-B T B T-B T B T-B GFFEET T 'B- T-B 3,462 9.950 6.332 3.617 3.478 9.B45 6.3E3 6.417 3.527 9.936 6.45B 2.411 30,0 9.944 7.032 2.30B 9.410 6.998 2.351 ~ 9,400 7.052 2.319 8.340 20.0 9.406 7.055 B.B70 7.664- 1.206 1.159 E.235 1.691 1.154 1.176 B.ELS 7.706 0.000
-10.0 3.B6B ' 7.692 B.330 B.330 ' O.000 B.330 E.330 0.000 B.330 E.330 0.000 0.0 B.330 E.330 7.525 B.979 -1.154 7.790 2.996 -1.206 7.792 B.96B -1.176 7.795 2.954 -1.!!9 7.250 9.662 -2.411
-10.0. 7.320 9.629 -2.308 7.254 9.605 -2.351 7.260 9.578 -2.319 6.710 10.32B -3.617
-20.0 6.815 10.277 -3.462
-30.0 - 6.716 10.243 -3.527 6.724 10.202 -3.47B AFD ICDRE/EICDRE RATIDS FOR GUAEANTS 1 - 4 GUG 3 000 4 000 2 GUAD 1 N-43 N-44 N-41 N-42 f:
l- r, s 1.8 37 M
- 1.444 M s 1.3E2 M s 1.417
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- ' , i3./ PLANT' SYSTEMS
- -(38%)-AND PLANT-WIDE GEN RIC.
RESPONSIBILITIES-(10%)-
LQUESTIdN .3. 27 ' .(1.00)
STATE FOUR-(4) signals. that will automatically initiate feedwater.
-(1.0)
, , isolation.(setpoints not required).
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., :QUESTIONL: 3.282 : (1.'00) i un p4 ~ STATE;TWO (2)J reasons (purposes) that sodium t'etraborate' is added .
-toitneficein:thelceCondenser. System. (1;0)-
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[3. !5L N'T SYSTEMS -(38%) hND PLANT'-WIDE GENERIC.
(h- RESPONSIBILITIES-(10%1
- c , ,
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- QUESTION 3.29 .(1.00)
LWHICH ONE.(1) of:the-following conditions will NOT automatically' '
(1.0):
b ,
!. start the turbine driven .CA pump?
r l(ai).- loss of VI to solenoid valves n
l.:- '(bi) . loss'of power to' solen'oid valves (c.)' preactor trip wish_ low Tave
[ '
1/1 det'from SSF SG 1evel on 2/4 SG's [+0.25] --
[ ,
'(d.)
w.
(***** CATEGORY 3 CONTINUED ON NEXT PAGE*****)
b _ --, _. _ ._ __
-1
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,-u g Page;77 L ' , : 3. : PLANT' SYSTEMS - (38%) AND PLANT-WIDE GENERIC RESPONSIBILITIES (10%)
L E . QUESTION '3.30 :(1.00) c MATCH the following , rod bank and mode of operation in' Column B with (1.0)
'the. rod. speeds in Column A.
COLUMN A COLUMN B.
- 1. Max. speed for auto control of 7
'a. 8 control banks.
'b. 48
~ 2.. Manual operation of shutdown-
- c. 64 banks.
- d. 72 3. Max speed for auto withdrawal of shutdown banks.
- 4. Manual operation of control banks.
- 5. Minimum speed for auto rod movement of control banks.
I
(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
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- vf~3.;PLANTLSYSTEMS'(38%)ANDPLANT-WIDE-GENERIC =
~~
. RESPONSIBILITIES (10%)
t ,
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., QUESTION ' 3.31: '(1.00)
- . Source range, instrument N31'had read 40 cps _'for,the;1ast several<
~
~
hours while~in Mode 5 at 1250 ppm boron concentration. Electronic noise from a . welder caused N31 to- reach 3000 cps for 30 seconds..
g WHICit 0NEl(1)"of: the' following describe's plant response?: (1.0) fI.[ > L cs
- " '3uctioniof the centrifugal charging. pumps switches from (a.)
a- 'VCT to FWST.
~(b.) Containment evacuation alarm sounds.'
-(c.) Containment purge supply and exhaust dampers close.
i(d.): - An automatic reactor trip signa 1Eis ; generated.
(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
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- 3 PLANT SYSTEMS'(38%) AND PLANT-WIDE' GENERIC -
, RESPONSIBILITIES-(10%)
in
\'. :.
- ;. ( '
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' QUESTION 3.32-?(1.00):
e>
- WHAT automatic: action ' occurs in-ihe waste'.' gas' system when the
- - trip-twoi setpoint of either the unit . vent gas 1 EMF 36(L) or the waste; gas: 1 EMF 50(L). is : reached? -
. (1.0)L r . ,
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s, 1
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QUESTION: 3.33! (0.50). - .
, - 1 (FILLLin the blank):
lA' f tag shall be placedf on a Lvalve which; if opened,
- could result-.in equipment damage. -(0.5)-
g
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- :9::: 3;_lptggy. SYSTEMS (38%) AND PLANT-WIDE GENERIC
, sig i. - ' RESPONSIBILITIES (10%)-
- v: ,
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'.' 1 I LQUESTION:
3.34: ;(1.00).
~
- InL'regards'to-StatibnDirective3.1.19,J" Safety;. Tags,"WHAT'is'the:
, ~
(1.0)L
. purpose.of:a BLOCK TAGOUT7..
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.Page. 82 :
'3L PLANT SYSTEMS-(38%) AND PLANT-WIDE GENERIC RESPONSIBILITIES (10%)-
S. 3 1
t, QUESTIONL=3.35 (1.00) 4
.The buddy!.cystem.of. entry'shall be used under all, EXCEPT (1.0)
WHICH ONE (1) of the following situations?
- (a.) to enter the' ice condenser while the unit is in Mode 4-(b.)- to enter:the Lannulus while the reactor coolant system is at 240'deg FL f(c.): 'to' enter upper containment.while the unit is in Mode.5
.(d.) to enter' lower' containment while the reactor coolant -
. system is at 210 deg F i,
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13.'PLANTSYSTEMS(38%1ANDPLINT-WIDEGENERIC j 4 : RESPONSIBILITIES (10%)
9 QUESTION 1'3.36.,(1.50)' -
osure' limits.if necessary to save lives or
.The Planned Emergency Exp/or extensive damage to property _are:
L'_ 1
- p(revent-loss.of. life andINCLUDEvalue'andunits.)
whole body; -(0.5)- r a..
(0.5)1
- b. skin .
.c; extremities (0.5) j
(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
i
di I Page'84 k.;.
- 3. PLANT. SYSTEMSf (38%) AND' PLANT-WIDE GENERIC RESPONSIBILITIES-(10%)
. QUESTION: : 3.37- (1.'50)
. Station . Directive 3.1.8 " Access to Containment" requires the ..
!com)1etion of DPC form #35414,'" Upper / Lower Containment Aut1orization," prior to entering the Radiation Control area.
p .An approval shall be' granted depending on the current operating-
. mode of-the unit.
. ~ .a' For Modes;1,2,3 4 (NC. temperature 200 deg F 'or greater)
WHOSE. approval is required .and WHO will verify this approval? (1.0)-
v' b.: For' Modes 5,6 (NC temperature less than.200 deg'F) WHOSE' (0.5) approvaliis required?.
1
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Page 85-I' '3. PLANT. SYSTEMS-(38%) AND PLANT-WIDE GENERIC RESPONSIBILITIES (10%)
3.38 1 QUESTION (1.00)
~
ANSWER the following questions regarding fire. brigade staffing.-
- a. -For the fire brigade, HOW MANY members must be maintained (0.5) onsite at all times?
- b. In order to accommodate an unexpected absence, the fire brigade composition may be less than the minimum requirements (0.5),
for a period of time. WHAT is that time limit?
i
- )
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. RESPONSIBILITIES (10%):
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LQUESTION -3.39 '(1.00)'
t 1WHEN may! a' non-licensed person *.anipulate' the controls which may
. affect the reactivity or. power' level of the reactor? . (1.0)-
)
s 1
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RESPONSIBILITIES-(10%)- >
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- QUESTION: '3.40.. (1.00)1 WHAT is~a' Restricted ~ change to a procedure? ,
(1.0) '-
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1 ii ____ _ _____a.___'._.___E._
Page 88
- 3. PLANT SYSTEMS (38%h AND PLANT-WIDE GENERIC RESPONSIBILITIES 00%)
QUESTION 3.41 (1.50)
Per 0-M-P 1-7, " Shift Manning and Overtime Requirements", FILL in the blanks concerning overtime. An individual shall not work more than (1) hours straight (excluding shift turnover time).
hours in any An individual shall not work more than (2)in any 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period, nor period (all excluding shift
, 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period, nor more thanhours morethan.(4) hours in any turnover time). A break of at least (3)T' shallday (5) be between j
work periods (including shift turnover time). (1.5)
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(***** END OF CATEGORY 3 *****)
(********** END OF EXAMINATION **********)
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- 1. ' ret.CTOR PRINCIPLES (7%)(THERMODYNAMICS -- ,
-(7%) AND COMPONENTS (11%) (FUNDAMF.NTALS EXAM) p
!?
ANSNER .:1.01:. (1.00)
L
-(d.); [+1.0] L
- REFERENCI-1.- - MNS:4.OP-MC-PS-ILE, p. 15.
2.- MNS:J0P-MC-PS-ILE, Objectives IE, IF, 10.
192005K105 191002K108- ..(KA's).
p o
ANSWER '1.02 (1.00)
' (b.);
.[+1.0].
REFERENCE 1.' MNS: OP-MC-RT-RCO, Obj. 20,p.34-37 1192004K106 192005K105 -..(KA's)
ANSWER: 1.03 _1.00)-
(
- (b;). [+1.0]
' REFERENCE
.1.- .MNS: OP-MC-RT-RCO, Obj. 8 & 14, pp. 21, 22, 24 & 26.
192004K106 192005K115' ..(KA's)
ANSWER 1.04 (1.00) f
- (a.) = [+1.0]
(*****
CATEGORY 1 CONTINUED ON HEXT PAGE *****)
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- r (7%) AND COMPONENTS-(11%) (FUNDAMENTALS' EXAM) y,,,,o " ,
.w TREFERENCE',
n ,
t v"
- MNS: OP-MC-CTH-CP, Obj! 35,'p. 96, 97..
'.. . 1. : ' '
, t 2. '
. MNS: :OP-MC-RT-RD, p. 14..
T192005K115- ; 193004K115 ..(KA's)'
s jw t r
'ANSWERL l'.05; (1.00).
L(b.) .[+1.0]i REFERENrc 1.. i4NS: OP-MC-SPS-RT-SM,;0bj.'6, 7, 8, & 10,'pp. 12-16.-
192004K1131 192008K'103; ..(KA's) r ANSWER 1.06 .- (1.00)-
f1 '. ; ;.high,[ fission] yield ,
- 2. . . :large thermal absorption.[ macroscopic] cross section
- 3. concentration chang'es.with power changes
- Any; two (2) [+0.5] each .
-.c
' REFERENCE
.1'. - 'MNS: OP-MC-RT-RP, p. 15.
2.. MNS: -OP-MC-RT-RP, Objective 12.
- 192003K106 192006K102 ..(KA's)
ANSWER' 1.07 (1.00) g
((b/Ji [+1.0]
CATEGORY 1 CONTINUED ON NEXT PAGE*****)
(*****
.+ :
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5 W, g .il;d REACTOR PRINCIPLES (7%) THERMODYNAMICS:
~
E' , < (7%) . AND COMPONENTS (11%) - (FUNDAMENTALS EXAM)'
y .
+
[ 3, 9-l 1 ..
1 t T_ s REFERENCER 3
'r,,
P=
i MNS": _0P-MC-THF-FF, p.E30L
.g
. 1?
IN( O
- 2. 1MNS: OP-MC-THF-FF,.0bjectives 12, 12a..
Plm --
...(KA's) p, 3,, . 193008K1051 2193006K104-g\
e.
- k. .,
t:4 .
y*% ANSWER- .1.08" ! (1.00);
- (b)
. ~ > . [+1.0)-
- p g- 3 N . REFERENCE : .. .e m .a-O iib 4 NS: M J0P-MC-SPS-RT-RK, pp. 21 and 22.
e _
L + ,
'MNS: OP-MC-SPS-RT-RK,ObjectiveL14.
2.-
f ij ,
F , 193009K105.: ' 192003K108. ..(KA's) .
ANSWER '1.09' :(1.00):
(b.)- -[+1.0]l
REFERENCE:
h l1. MNS: OP-MC-PS-RVI,-pp~.-24-25. _.
' 2. MNS: OP-MC-PS-RVI, Objectives 15 & 16.
u 193009K107 ..(KA's) 193010K104 -193010K107 b
- ANSWER. 1.10- (1.00)--
p :
(bh) [+1.0]
p_; ,
.f e ;,
.(***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)
1'_ _ _ __ _ _ - - - - _ _ - - _ -___- _ _ _ _ - - - _ _ - _ _ _ _ - -
l% ,
i .!
'I
($ 'Page 92
!b , ! 1.1 REACTOR PRINCIPLES (7%) THERMODYNAMICS' ..
[ft 4
, -(7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM) l q
L .
P . REFERENCE
- 1. MNS: OP-MC-CTH-CP, Objectives;14 & 15, pp. 92-94.-
U 193007K101
'193009K105 ..(KA's)'
s k, - :ANSWERL 1.11. (1.00)
[ y- . (c.) - [+1.0]
. : REFERENCE 1.' MNS: .0P-CN-THF-HT, Objectives 6, 6A, 6B, 6C,' pp. 16-18 m
193008K104 000074G011 ..(KA's) i- ' ANSWER. 1.12 (1.00)
(d.). '[+1.0].
REFERENCE-
-1.. MNS: OP-MC-RT-RB, Objectives 8, 9, pp. 20.and 22.-
191002K117 192002K114 ..(KA's) .
4 ANSWER 1.13 (1.00)
(c'. ) [+1.0]
REFERENCE
- 1. .MNS: OP-MC-THF-FF, Obj. 6e, pp. 22-23.
191004K109 192002K114 ..(KA's)
(***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)
g ,g ,
Page 93~
'1. REACTOR PRINCIPLES-(7%)' THERMODYNAMICS
> (7%)> At:D COMPONENT 5 (11%) (FUNDAMENTAL 3 EXAM)
~
" ANSWER' . '1.14
.(1.00)
- (b.) . - [+1'.0)
REFERENCE-
?1. MNS:. OP-MC-THF-FF, pp.~17-18.
- 2. MNS: -0P-MC-THF-FF,. Objectives 6B, 7, 7A.
191004K106 191004K109 191004K120 ..(KA's)
ANSWER 1.15 -
-a.. 120 gpm Q\-[+D(1.00) 0.25]
- b. 'If NV letdown temperature increases to 138 (+/- 2) 'deg F [+0.25],
letdown'HX outlet diverter valve [NV-127]) diverts letdown from the bypasses) demineralizers (to the VCT) [+0.5]
REFERENCE
- 1. MNS: OP-MC-PS-NV', Objectives 2E, 3A, 3J, 3K, 5, 9, pp. 7 and 16.-
191007K104 191006K107' 191007 109 ..(KA's)
ANSWER ~ 1.16 (1.00)
-(c.) [+1.0]!
REFERENCE
- 1. MNS: OP-MC-RAD-FRP, p. 17.
2.- MNS: OP-MC-RAD-FRP, Objective 14.
191001K108 191002K119 ..(KA's)
-(***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)
n- - -- ._ . - - -
y e . s ;.
p Page 94'
!1. REACTOR PRINCIFLES (7%) THERMODYNAMICS'
. (7%)- AND COMPONENTS -(11%) - (FUNDAMENT ALS EXAM)
~
b:
- b. .
j- ,. U l-'i , . ANSWER' :1.17 (1.00)
(a.) - [+1.0] '
- p. ,
I REFERENCE'
~
.1.- MNS:.-.0P-MC-TA-AM,.0bj. 5c, 5g, p. 45.
1 i
191005K106 191002K117 ..(KA's) j; cANSWER 1.18 (1.00)
- (c.) - [+1.0] ..
REFERENCE-
- 1. . MNS- 'OP-MC-THF-FF,;p, 19.
- 2. MNS: OP-MC-THF-FF, Objectives 9, 9A, 9B.
t 191001K103 193006K110 ..(KA's) i ANSWER 1.19 (1.00)
-(c.) [+1.0]
REFERENCE-
- 1. MNS: OP-MC-THF-FF, p. 17.
- 2. MNS: OP-MC-THF-FF, Objectives 8, BA, BB, 8C.
191002K107 191002K108 191004K101 ..(ra's)
(***** CATEGORY 1 CONTIN'JED ON NEXT PAGE *****)
q=w . . . .
-7 ,
f ,
., "? J. 3 :y 4
Pagi.95
' . m o
- fli REACTOR PRINCIPLES (7 4 THERMODYhAMICSh
, :(7%) AND COMPONENTS-(11%)-(FUNDAMENTALS EXAM)
>:s ;c ; >
y .i ? ' y' 9
'g y ~
3 "9 .
11.20: ;(1.00).
- ANSWER '.
~
i 'r - (Too~ frequent starting]of the NCP heatmay result(during. in) damage to the NCPc
' motor (windings [+0.5 due to (excessive): generated L starting) - [+0.5 y -
REFERENCE-12 :MNS: 'OP-MC-EL-ETR,.:pp._48-50.
f2. 'MNS: OP-MC-EL-ETR,' Objectives 6 &'7.
'3. -MNS: OP-MC-PS-NCP,.0bjectivs 10...
191005K106:. 192008K103 ..(KA's)
ANSWER. '1 .21- (1.00).
' (h. )1 -[+1.0];
l
REFERENCE:
- .s
- 1. - .MNS: OP-MC-TA-AM, p. 25..
- . .2. MNS
- ' OP-CN-THF-HT, Objectives 1, 1A, 2, 2A, 2C, pp. 8-15.
191002K118 193007K101 - ...(KA's)
-- ANSWER . 1.22 (1.00)
- 1. .(to limit NC system pressure) to prevent undesirable opening of safety valves
- 2. 'to provide (cold) overpressure protection (a rMt ph wbb b edere
.3.- to prevent reactor trip "' f '** fMM m Any two (2) at [+0.5] each
(***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)
m
+ ,
1
[' Q' \
T Page 96:
'1.'REACTORPRINCIPLES(7%)-THERMODYNAMICS (7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM)
- r;; .
.8-REFERENCEI
-: 11, [ .MN $_-3:- LessonP1an PZR-01-C, pp.-14.and 19..
.2h MNS: l0P-MC-PS-NC, Objectives 1,' 10h g 8 ..
- ,000011A209- 191001K102 ..(KA's)-
. ANSWER 1.23' (1.00)~
.(d.)7 [+1.0]
( : REFERENCE' T- :.1.
- MNS:. 0P-MC-PSS-KC, Objective 3, pp. 6-9.
c191006K108 -000040K101- 191006K107. ..(KA's)
" ANSWER 1.24-- .(1.00) r (a.) [+1.0]
tr REFERENCE.
MNS: OP-MC-IC-ENB, Objectives 4, 6 -7.
1,
~000057K301 191002K118 ..(KA's)
ANSWER. .1.25 (1.00) it must be cycled electrically (to assure operability)
~
[+1.0]
. REFERENCE 1.- MNS: OP-MC-PS-ND, Objectives 7, 8.
000003A201 191002K118 000003K304 ..(KA's)
(***** END OF CATEGORY 1*****)
1
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I Page.98 '
20[2i7 EMERGENCY AND ABNORMkl PLANT EVOLUTIONSI
, gw (27%)s ,
y x , ,
o '
p: .
M ;
REFERENCE:
MNS: L EP-12;1', " Response to In' adequate: Core Cooling.".
s 1.:
K ej .
2.s :MNS:) OP-MC-EP-EP7,DObjective B.. .
g .
-000029A113' .000074G011,: '000007A107 ..(KA's)
It
~ ANSWER- :2.04 (1.50)l 1.; SIlmay be contributing.to the'cooldown [+0. 5] .-'
2., Poor mixing. of? SI will: increase thermal stress- [+0;5] .
H E 1 3.' SI may. cause the plant to.repressurize [+0.5]
, REFERENCE
- 1. MNS: OP-MC-EP-EP9, Objective B.2., p.;7.
- 2. .MNS
- EP/1/A/5000/14.1,." Response to Imminent Pressurized Thermal Shock Conditions.
' * -000040K1014 000015G007 ..(KA's) e ANSWER '_2.05f (2.50)
- ' a. 11 ' RPI . AT BOTTOM R0D DROP alarm
- 2. individual rod. bottom. light-
- 3. ~ P/R HI- NEUTRON FLUX RATE ALER,T alprm .
- 4. P/R CHANNEL' DEVIATION alarm (Qf T)'
5.- decrease in Tavg 4,
Any. ' rathreemed (3) [k.od b %%Jc
> 5] each.
.b.. 1. Place CRD selector in manual [+0.5]
- 2. check if reactor trip is required: [+0.5]
(a) 2/4 PR high flux rate bistables actuated (b) ensure reactor trip and go to AP/1/A/5500/01, "ReactorTrip"]
(***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)
= _ _ _ _ _ - - - _ _ _ _ _ _ _ _ - _ - . - _ _ - _ - _ _ - _ - - - _ _ _ _ ___ - -___ _- _ - -
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Page.99f.
- 2b ! EMERGENCY 1AND' ABNORMAL PLANT' EVOLUTIONS' t . (27%) .
- [
4
&. REFERENCE $ .
y 3-; y ;1.: .'MNS::l AP/1/A/5500/14,; " Rod Control Malfunction;" p.'6. '
'MNS:;l0P-MC-IC-IRE, Objective?ll.
2...
! 3.l MHS: OP-MC-IC-EDAl Objectives 4:& 5.
m ..
000003K304 ..(KA's)
" 000003A201.- 000055G011 p
' ANSWER L2.06HL(1.5'0)T
- n. ,.
- 1. Excessive control rod. insertion.
2.: Failure of two or more control rods to drop following a
' . reactor trip.
7
- 3. Unexplained or uncontrolled reactivity increast.
- 4. . . Inadequate shutdown margin.-
m 5.1 Control rod bank.Lo-Lo limit alarmi a
- 6.- Less'tha'n 2000l ppm boron.in Mode 6. ..
AnyL five[(5)l [+0.3] each REFERENCE.
p.~
H 1. . ~McGuire:AP/1/A/5500/38,." Emergency Boration."
000009K323' 000024G011- ..(KA's)
-ANSWER- 2.07. (2.00)
- If the turbine not-tripped, then:
~
1.; _stop both DEH pumps [+0.5]
2.- place turbine in manual and close GV's in fast action [+0.5]
- 3.. , locally trip
- the turbine [+0.5]
~
(***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)
_ _ _ - - - _ - . _ - - _ _ . _ . - - = - - _ - .-_______----_1__----- __ - . _ - - - _ _ . _ _ . - - - -
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3 Page100 Q < j2E' EMERGENCY'AND ABNORMALLPLANT' EVOLUTIONS
.(27%); ,
~~
f :q; 1
- , w
.REF'ERENCE4
- 1". - MNS:;EP/1/A/5000/11.1,"ResponsetoNuclearPower-
-Generation /ATWS."
"I 'MNS: OP-MC-EP-EP6$.0bjective.B.2.
(2 l000029A113 000038A101 *000038A203' ...(KA's).
, :000038A202/
~
ANSWERi 2.08'i(1.50)
- 1. .QPTR:
2.
3.
AFD [ delta heat flux hot'I:channel or' axialfactor-
- 14. enthalpy rise hot channel factor [ peaking. factor](yq -
offset][ peaking factor] (4d
- Any;three!(3)' [+0.5] each, +1.5~ maximum.
- o. ,
' REFERENCE-
- 1. . MNS: AP/1/A/5500/14,pp.'11through16.
E ;
2.- MNS:l0P-MC-CTH-CP, ppc 95 through 99.
000032K302- 000005K101- 000005K305
?000005K106 000032G011 L
..(KA's):
ANSWER' 2.09 . (0.50) . . .J '
.-(as Permissive interlock C9 (condenser available) has not been met [+0.5]
the_ circulating water pumps are not running):(vacuum is lost)
' REFERENCE L
1.- MNS: OP-MC-STM-IDE, p. 8. ,
.2.- MNS: OP-MC-STM-IDE, Objective 1F.
]
' 000025A207 000025K303 000051K301 ..(KA's)
(***** CATEGORY 2. CONTINUED ON NEXT PAGE *****)
i.
~ ' ~~ ~ ~
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(, .
Page101 P .
- 2. EMERGENCY AND-ABNORMAL PLANT EVOLUTIONS (27%)-
t
!i l A p.7
'2.10- (1.00)~-
]
l ANSWER-L(a.)' [+1.0].
p JREFERENCE'
- 1. =
MNS:' Nuclear Systems Description ND.MC-1223.12, pp.15 and 18.
.MC-1562-3.1; and MC-1561-1.0.
L. ,
2.- MNS: . OP-MC-PS-ND Obj. 5 & 7, p.18.
c 000074A111 000dO7K301 ..(KA's).
i'
' ANSWER 2.11 (2.00) _'
- a. 1.- rapidly increasing water levellin the affected SG [+0.5]-
- 2. steam flow /feedwater flow mismatch % in theeq affected e vor SG"[+0.5] % %
b..
. 1.w hw %w .E sG ieder (to,Qlimit the 5] spread of contamination [+0.y-%
.2. allow maintaining ruptured SG pressure above the pressure of the intact SG's, as a prerequisite for stopping break flow [+0.5]
REFERENCE (1.- MNS: OP-MC-EP-EP-4, ' Objective Cf (f. IB,D,
- 2. HNS: EP/1/A/5000/04, " Steam Generator Tube Rupture."
00003BA203 000038A202 000055K302 000038A101 ..(KA's)
I
' ANSWER 2.12 -(1.50)
- a. If flow verified from one NV or NI pump [+0.5] and NC system subcooling'less_ than or equal to 0 deg F [+0.5].
- b. Necessary to minimize inventory loss for SBLOCA (to limit core uncovery and peak clad temperature) [+0.5].
1 I
i
(
(***** CATEGORY 2CONTINUEDONNEXTPAGE*****) l
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=-
7 N
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-Page102 -l )
E M 2. EMERGENCY AND ABNORMAL; PLANT EVOLUTIONS- .
l g , -(27%)- ;
s, w < .
b u
- Y ;
REFERENCE:
)
~1.
MNS: EP/1/A/5000/02, HELBIC. foldout page.- l l
- 22 - MNS:; 0P-MC-EP-EP2, Objective B3, p.18. - !
~
000009K323 000068G011 ..(KA's)- C t :
L ,i C 2.13' (0.50)
ANSWER:
when directed by the SRO at the~ auxiliary shutdown panel [+0.5) l REFERENCE 1 a
, L1. MNS: AP/1/A/5500/17, " Loss of. Control Room," p. 3.
i 000054K304 00006BG005 ..(KA's)
- I ANSWER 2.14 (1.00) i,
- 1. - 1 EMF 33 (condensate air l ejector exhaust high radiation) alam i 1 EMF 34 ;(steam' generator sample high radiation) alarm
[ _2. -!
- 3. steamline EMF (24, 25, 26, 27 high radiation) alarm
- 4. increase in frequency of automatic makeup to VCT .
- 5. fecdwater' flow and CF regulator valve position indication
-decreasing in any steam generator (higher SG 1evel)
- 4, ,' 2; ,_
- b e m:t -( w=;. , - App ;
Any four (4) at [+0.25] each I REFERENCE
- 1. MNS: AP/1/A/5500/10, "NC System Leakage Within Capacity of Both NV Pumps," pp. 2.
000076K305 000036K303 000036A202 ..(KA's) :
i L
'(***** CATEGORY 2 CONTINUE 0 ON NEXT PAGE *****)
1: i
v- - - - - -
g; -T E" ,, ,,
N *
+
Page103 ,
- 2. ' EMERGENCY AND' ABNORMAL PLANT EVOLUTIONS p
-(27%)
k n
H ANSWER 2.15: (1.00)
I fl.
crudburst.[+0.5))-.
failed fuel [+0.5 2.
e b
o -REFERENCE o
- 1. . "MNS: ' AP/1/A/5500/18, pp. 2 and 3.
..000076G008 000051A202 ..(KA's) n.
b ANSWER 2.16 (2.50)-
- 1. core exit' TC's [+0.25] ' stable or decreasing ;+0.25;
- 2. NC subcoolin +0.25] - greater than 0.deg F .+0.25J
- 3. SG pressure + .25] . ' stable or decreasing [+0.25]
[+0.25]
- 4. NC hotleg-temperature.
leg _. temperature
- 5. NC cold [+0.25 [+0.25))- stable or decreasing- at' approximate temperature for SG pressure '[+0.25]
REFERENCE-
- 1. MNS: EP/1/A/5000/22, " Post-LOCA Cooldown and Depressurization," foldout page.
-000024G010 000011A209 000011K101 _..(KA's) 000007A103.
ANSWER _ 2.17 (1.00) blackout diesel running)[+0.5] [+0.5 b yadar C "Y* Sid
- 1. MNS: Instrument Air System, p.13.
,000065K304 194001K102 ..(KA's)
(***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)
t_______.i__12___ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ . _ _________________________________________________._._________________________________________._____________m
- m m p y- , .....s ,, m.
j . ' - I i
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..( Page104- l n
g.: l L2.E EMERGENCY 274)-
AND2 ABNORMAL PLANT EVOLUTIONS q F, t ..
( .
p iq J , 'I r.. !
I n
't NANSWER; 2.18: L(1.00)c b'.
h;. 1
-[ (d.)j ![+1.0]:
L. ,
~ '
u REFERENCE'.. ,
e .. .
L
?1. "MSN:1AP/1/A/5500/12,p.17.. .
L4 000028A212L 194001K102l ..(KF's)-
- r. ,
p LANSWER. 2.19 ' (2.00) _'
1.; Containment' Press [+0.25]L - Less than,1- psig . [+0.25]l
, : ai -
- Greater than 185% psig [+0;25 2.- PZRPress-[+0.25::;+0.25] - Greater than 585 psig []+0.25]
- 3. S/G:Stea P ss b'. " Safety Injection ' Actuated" status light' [+0.25] - dark 1[+0.25]
-REFERE'NCE'
- 1. :McGuire: AP/1/A/5500/01, " Reactor Trip."
, L 2.. 9:32 i 0 f- MC.-ttc.-I$f,, p 2.5,
~194001K103 .000007K301 ..(KA's)-
e
!,5
'c i'. -
(***** END OF CATEGORY 2*****)
. _ _ . . _ _m__- __ _ _ _ _ _ _ _ _ .___. __.._...___..______________m
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, Page105c z
- i. . ,
[3) PLANTlSYSTEMS'(38%)"AND PLANT-WIDE' GENERIC;
'* JJ " RESPONSIBILITIES-(10%).
a l
q'i , '
~
! ANSWER? -3.01= -(1.dO)5
{
<' ~
2 (c.)L [+1.0) -
' REFERENCE 1.1 _'MSN:-OP-MS-CF-CA, p. 9.- .
a .
- 193003K125? 193003K117 061000K401 ..(KA's)-
j.::
!ANSWERE 3.02: -(1.00)1
[+1.0]i n l (ai)--
or G.Y REFERENCE' (1. MNS: 'OP-MC-ECC-CLA,!0bjective 6 g 9-l0 L
059000A412 013000K106- ..(KA's)
\
- ANSWER 3.03 . .
(1.00)
'(d.)L [+1.0]
. REFERENCE
- 1. - MNS: OP/1/A/6100/10C, panel 1AD2-A9.
014000A103 025000G004 ..(KA's)
LANSWER 3.04 .(1.00)
(operations at s l can) damage the exciter ,
regulator-[+0.5]peeds lower than normaand the generator field (windings) l i
4
(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) !
== _ :_
_ _-__--_a______- - _ - = _ - _ _ - _ - _ _ - - - _ . _ __ _ _ _ _ _ _ __-_.-_____-_____--______-____-_=_-
7;-n . . . .
.e
! ?% \
.s..
Page106:
- 3. . PLANT SYSTEMS 1(38%) AND PLANT-WIDE GENERIC.
RESPONSIBILITIES--(10%)-
TREFERENCEJ
'1." MNS: OP-MC-DG-DG, " Diesel Generator," Objective' 8,-- p.11.
'064000A206i 004000K104 ..(KA's)
" ANSWER- 3.05- - (1. 0'0)'
(b.) [+1.0]
i REFERENCE;
- 1. MNS:' OP-MC-DG-DG,[" Diesel Generator," Objective 3.
035010A202: 064000A103 059000K104' ...(KA's)
ANSWER. 3.06',(1.00). T (c.) [+1.0]~
REFERENCE!
- 1. McGuire: 'OP-MC-PS-ILE, " Pressurizer Level Control,"
Objective E.
004000A101- 004010K618 004000G004 . . (KA's)
-011000A211 1
l l ANSWER 3.07 .(1.00)
To prevent overpressurization [+0.5] of the upper containment [+0.53 1
~
L
(***** CATEGORY 3 CONTINUED ON HEXT PAGE *****)
~ ^ - - - - - - . - _ . - - , . - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
l-
-Page107' '
- .- 3 " PLANT'.SYSTEMSt(38%) AND PLANT-WIDE' GENERIC
. RESPONSIBILITIES-(10%)' I d '
.j
' REFERENCE-
- 1. ,MNS: OP/1/A/6450/15 " Containment' Purge System."
' /2. MNS::dP-MC-CNT-VP, Objective.7. .
g
- 029000A103. 062000K403 029000A203 ..(KA's)
ANSWER' 3.08 (2.50)'
a.'.1.
- 2. :1?1 EMF-33 EMF-34 SG Sample Cond Hi Rad"AE alarmExh Hi Gas Rad" alarm [+0.5)[+0.5]
- 3. "1 EMF-24,.25,'26, 27 Steamline' Hi Rad" alarm [+0.5]
- b. (SG will.have flow of 528 gr.d, which exceeds the) Technical Specifications 500 gpd total leakage' limit [+1.0]
REFER $NCE
- 1. MNS: Technical Specifications 3.4.6.2, and Bases.
- 2. MNS:.~AP/1/A/5500/10, "NC System Leakage within Capacity of NV Pumps."
'035010A408. 012000K402 035000G011 ..(KA's)
-3.09 (1.00)
ANSWER.
- a. Hi Hi- Containment Pressure (Sp signal)33 psig [+]0.25]
logic: 2/4 [+0.25] and CPCS E 0.35 psig [+0.25
- b. < 15 psig- [+0.25]
REFERENCE
- 1. MNS: OP-MC-ECC-NS, Objectives 1 and 3.
l l
035000G011 026000A301 026000A101 026000G004 035010A408
..(KA's)-
- , (***** CATEGORY 3 CONTINUE 0 ON NEXT PAGE *****)
L F
L_ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
, w. -
- > ' E[
.g- . . . . .
m
,.7,1,- +
- Page108j f ( l3.-- PLANT' SYSTEMS (380 AND PLANT-WIDE GENERIC ~
ug;pg RESPONSIBILITIES (10%): l
)
l y (ANSWER / 13.10 (l'.00) l
^; ,J ' a. 3 '+0.25' a'
- b. '5~ '+0.25'
- . . c. 1~ '+0.25' <
l
.ld.1 12 l+0.25l REFERENCE' .;
li.
MNS: LOP-MC-IC-IPE," Reactor'ProtectionSystem," o Objective 1.F,. pp. 9 through 20.
'029000A203' 012000r402' 029000A103 ..(KA's) l l
'l 3.11 ANSWER. (1.00)- .3 1
(a.) [+1.0]
l REFERENCE-; l
- 1. ' MNS: OP-MC-EL-EP,'
- Main Power Distribution," Objective 21.
4
. a. '!
. 011000A211" 062000K403 .. (KA's)
' ANSWER 3.12 (1.00)' l (d.) [+1.0]
.l
-REFERENCE i
.1. .MNS: OP/1/A/6300/01, Enclosure 4.1, p. 8. )
062000A403 064000A103- ..(KA's) 1 I
(***** CATEGORY 3 CONTINUE 0 ON NEXT PAGE *****)
i
7g-k.
n.
t d
,', 1 Page109-32 PLANT SYSTEMS-(38%) 1.ND PLANT-WIDE GENERICJ 'I
/ , RESPONSIBILITIES (10%)
)
V l 1
k 1 r.
- - ANSWER
- . -3.13 .. (1.00)
![withcontrolat2235psig]'
O ; a. : :2335; +/- 15 2385: +/- 15
'b. -
1845 I +/- 15
,c..
!d.; -1955-(+/ !15 z [+0.25] each iREFERENCE.
. fl. MNS: OP-MC-PS-IPE, p.'5..
010000K102 .064000A206 010000K101 ..(KA's)
ANSWER- 3.14~ (3.00).
a.- 1. actual feed flow decreases [+0.25] due to main feedwater:
regulating valve closing in response to'the false high.
feed flow signal [+0.5]
- 2. tsteam generator level decreases [+0.25].duetodecreased feed-flow' [+0.5]
- 3. no chance 0.25]: due to steam demand at 100% power-
[+0.5]lupu[+ntiltrip).
to b.- .on S/G lo, level 40% [+0.5] setpoint 2/4 in 1/4 S/G 1evel
[+0.25]
REFERENCE.
l'. McGuire: OP-MC-CF-IFE, Objectives 8, 10, 12 f.0-059000K104 035010A202 033000G006 ..(KA's) i.' \
(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
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J Page1101 p , J3.' E PLANT SYSTEMS (38%)1 AND PLANT-WIDE GENERIC:
p ,
- RESPONSIBILITIES (10%)
[ Eh .i e
- l L c L >
-ANSWER. 3.15 '
- (l'.00) ~
1.. .al1 KC pumps start F
e
- 2. . , auxiliary building non-essential headers) isolate
- 3. . isolation valves to ND.HX open: ,
t 4.- 'NDHXcontrol'~ valves (f,ailhpen b 5. - NCOT and excess !1etdown isolate Any fourJ.(4) fat [+0.25]- each M .R'EFERENCE il.- 'MNS:-OP-MC-SPS-SY-KC, Obj. 4, p. 17.
L- N15' Of FC- PSS-kt, p,18. oy. r
, 008000A401 006000K606 004000G007 '008000K401 ..(KA's) g ANSWER ~3.16- (1.00)-
- a. 4 '+0.25'
- b. '6 '+0.25 :
- c. 4 "+0.25
- d. 3/ l+0. 25.'-
REFERENCE
- 1. :MNS:.0P-MC-CNT-VX, pp. 8, 12, 13, and 20. .
041000G007 028000A101 ..(KA's)
ANSWER 3.17. (1.00)
- 1. - temperature (114 deg F) [+0.33]
- 2. - h.88%) +0.33 ,
llevel pressure- (hig(8 psig) ~
.+0.33,1
-3.-(
.r
(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
L_ _ _ _ _- - __ -_- _ _ __ -__-______ _ ____-- - -__ _ _ _ _ _ _ - _ _ - - _ _ _ _ _ _ - _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ - - - - _ _ _ _ _ _ _ _ _ -
- - .y i3? \ PLANT
- SYSTEMS'(38%) AND' PLANT-WIDE GENERIC' Page111-N <
RESPONSIBILITIES (10%)
G ,
. .4
{ REFERENCE t
1.- MNS:1OP-MC-PS-NC, p. 4. .
007000A201- .008000A401 008000K401' ..(KA's) y L-ANSWER 3.18 .(2.50)
L ,
- a. :1. - deg'asi fication -(purge). ,
2.- filtration-
.3..= demineralization
[+0.5] each' b.. 1..$1.0 uCi/gm doset equivalent I-131 .[+0.5]
- 2.; 5100/E uCi/gm * [+0.5];
oh a speak =ch y
- REFERENCE Kl. .McGuire: OP-MC-PS-NV,'"CVCS',"; Objective:1-and 9.
i 2. - 'McGuire:l Technical Specifications, 3.4.8.
.022000K402. 004000G00'4 004000A101 004010K618- ..(KA's)
EANSWER 3.19 (1.50)-
- 1. No. 1 Seal Leakoff temp. exceeds approx. 200 deg. F.
- 2. NCS pressure > 100 psig but < 1000 psig.
3.. No. 1 Seal 11eakoff valve open.
- 4. No. I Seal leakoff is less than I gpm.
- 5. ^ Seal injection flow to.each NC pump is > 6 gpm.
[+0.3] each REFERENCE' 1.- McGuire: OP-MC-PS-HV, p.8,.LPS0 #9.
000057G010 004000K104 ..(KA's)
,. (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
g(.< - ,-nc . 7.;
y: . 7=
b,,'M ' '
l3; PLANT: SYSTEMS (j8%)'AND PLANT-WIDE' GENERIC- Page112-W, <
!(., . RESPONSIBILITIES (10%).
g ,
- m. <
$ f.
8
' ANSWER 3.20- .. (1.00);
b :C-7[(loss'ofload.inteEleck)willactuatetopermit
's .:
. steam: dump [+0.5]~ due Tavg-Tref greater than 5 deg F .[+0.5].
' REFERENCE
, 1.- McGuire:~-. OP-MC-STM-IDE, " Steam Dump. Control System,"'
Objective F.-
000074A111 041000G007 ..(KA's)
. ANSWER .3.21 (1.50) r 1.- : Ensure isolation between. safety and not-safety systems
'during an emergency.
r
- 2. -Prevent _the. injection of Hydrogen into'the safety related.-
-NV pumps suctions.
3.- Prevent the. loss of ST' water via the non-safety portion
, ~o f the NV system in the event of a pipe rupture.
'4. Prevents the dilution of NC system with VCT water during an accident..
Any three (3) [+0.5] each; max. [+1.50]
REFERENCE
- 1. 1HcGuire: OP-MC-PS-NV, Obj. 3 & 6.
006000K606 004000G007 ..(KA's)
ANSWER 3.22 (1.00)
(b.) [1.0]
(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
___ . _ _ _ _ _ _ _ _ _ _ - _ _ _ - _ _ _ _ - -- A
p .,. .-.-- N ' '
l
^
3! PLANT ~ SYSTEMS'(38%) AND ' PLANT-WIDE GENERIC Page113 ,
d b RESPONSIBILITIES (10%)- ,
a
?!
. REFERENCE ~
s '1. lMNSU'0P-MC-ECC-ISE-2,Obj.'1.Mm , .,s t'
P 4
1006020K406 ..(KA's) g h
a : ANSWER 3.23.'(1.00)-
F
~(c.) .[+1.0].
i REFERENCE
- 1. - ..
MNS: OP-MC-EL-EPL, Objective :17.
-062000K403' ..(KA's):
ANSWER: 3.24 ' (l'.00) l '. l RN ' ..
2.
RF 3.- .RL-4.- - KR coolers-5 .- feed pump condensers 6.- condensate coolers 7.. main condenser any four [+0.25] each REFERENCE-
- 1. . MNS: OP-MC-MT-RC, Objective 5A.
L008000K102 ..(KA's)
ANSWER 3.25 (0.50) l '. 40 '+0.25
- 2. 45 '+0.25
- i
(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
=- -- - _ - - _ - - = _ - _ _ - - - _ . _ _ _ _ - .___ - -_ __- .- _- __ -- -. . _ _ _ _ _ _ - . . - _ _ _ _ _ _ _ _ _
+,
E l
o '
Q 7 33,; PLANT SYSTEMS:(38%) AND' PLANT-WIDE' GENERIC- 'Page114 c' '
~ RESPONSIBILITIES (10%)
lt:p l * ' -
_ .REFEREt!CE' 1.- MNS: OP-MC-STM-IDE, Objective '1A.
-4. ..
041000G005; 041000G004 ..(KA's)
+
1 ANSWER' 3.26 (1.50)
. normalized currents-' N41 N42 N43 N44 avg. .
- upper. ' O.5 tms 0 0.5M2m 0.528'2520 0.5n uw
, . lower , 0.B M B 0- 0 5t%i 0.9 to% 0.S zo2.T max upper / avg upper =' 1.0I166 max'~ 1ower/ avg lower = 1.03 45 w- [QPTR=1.07'166 l+0.75,1 for normalized currents' and average current,+ h Maud faces,
+ 0.75.!- for QPTR determination,4 Aw JuM pace.
REFERENCE
.1. MNS: Technical; Specifications 3.2.4, Quadrant Power Tilt l Ratio Limits."
2.- MNS: OP-MC-CTH-CP, Obj. 13.
015000A104 194001K105 ..(KA's)
ANSWER. 3.27 '(1.00)'
t
- 1. Hi Hi dog house level ~
- 2. Injection
- 3. Safety Hi Hi S /fq'1evel
- 4. ' Rx trip with lo Tavg
[+0.25] each i
l
(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
gg g ~ m; g .-
o , .q nv'
.f"t * ' '
o 9.,
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$5 5 t:T;)G
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' W ;3. ' PLANT > SYSTEMS"(38%)'AND PLANT-WIDE' GENERIC:; .
Page115l pf: ... RESPONSIBILITIES-(10%): <
y m ,
I-t
.j
, l. . - , . .!
1 0:% .3- T
REFERENCE:
-l
]
4,L' DL .
t
- 1. ~ McGuire:;- OP-MC-CF-CF, " Main: Feedwater," Objective 9.
q.
i 1 D b 194001K116. '059000A412~ ..(KA's) ..
+
m' y l ANSWER- >3.28 .(1.00).
c .. .
- t. ,~, ,
!1. 1. Results-..in a neutron ' absorbing medium'[+0.5];
{,
in 2. :IncreasesLthe . retention of iodine' or increases the PH
(' (following an accident). [+0.5] .
REFERENCE-
- 1. . McGuire: OP-MC-CNT-NF, " Ice Condenser," Objective 1. A', p. 29.
-194001K116- 025000G004 ..(KA'.s)
. ANSW'ER- 3.'29 - (i.00)
-(c.). .[+1.0]
REFERENCE;
-1. MNS:~0P-MC-CF-CA, pp. 8,.13, and 16.
g 061000K402= 194001A103 ..(KA's)
ANSWER. 3.30 (l'.00)
- a. 5
- b. 4-
- c. 2
- d. ' 1 is
(***** .
CATEGORY 3CONTINUEDONNEXTPAGE*****)
s t -.
. . _ . - _ _ _ _ . _ . . _ - _ _ _ . _ - - - . _ - _ _ - . - - _ - - - . _ _ w
m,m g -
= -
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- RESPONSIBILITIES-(10%) ~
? y . .,
, gy Y.'/.0 p ,
' v <s, i>
g-
" t
- i. REFERENCE;
(( g (1, : McGuire:- 0P-MC-IC-IRE, Tobje'etive ' 131 g;
d, ' '2. McGuire:l0P-MC,IC-IRX,.obje'ctive3.I' -
r
- -001010K404' 194001A103L ..(KA's).
4, ' ANSWER. :3 31 ' (1.00) .;
l(b.): )[+1.0] .
i: ' y iREFERENCEL ;
, 1. . l i. ; MNS: OP-MC-IC-ENB, p. 10. .
1 1194001A109 :015000K604 004000K107 ..(KA's)
, o
'3.32-
.ANSWERn (1.00)c 1WG160p waste gas discharge flow controller![+0.5],. trips closed
- [+0.5]
REFEREN'CE~
-1. 'MNS: OP-MC-WE-WG', p.~8.
194001A116 071000A407 ..(KA's)
-ANSWER 3.33 (0.50) white (white safety) [+0.5]
l(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
, e; * - _ - - - - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ - , - _ - _ _ _ _ _ _ _ _ - _ - . _ . _ _ _ _ - _ -
( h wn j
1 g . 3. PLANT SYSTEMS'(38%)'AND PLANT-WIDE GENERIC' Page117; ll g, ; RESPONSIBILITIES (10%)- '
p TREFERENC'E~ -
1.- McGuire: S.D. 3.1.19 " Safety Tags",'Section'4.2.
I cp
~ 045000K412 -
.194001K107 ...(KA's) ye ,
!? ANSWER- ^ 3.34 (1.00) l Block Tagout is-the isolation and tagging [+0.25] of a defined
- portion of the, plant [+0.25] 'for the purpose of allowing work by e _ various work grou)s: [+0.25] to be accomplished concurrently within the boundary of t1e block tagout [+0.25].
Credit will be given for'similar wording.
REFERENCE
- 1. McGuire: S.D. 3.1.19, " Safety Tagt," p. 4.
194001K102- 026000A101 026000A301 025000G004 ..(KA's)
EANSWER. 3.35 (1.00)
(c.) [+1.0].
' REFERENCE 1.. MNS: SD 3.1.8, p. 2.
002000A103 194001K114 002000G006 ..(rA's)
ANSWER 3.36 (1.50) to.Q vy
- a. .
r 25,Remg.,q yy[+0.5J
- b .' 150, Rem [+0.5]
pc.Q Sy
- c. 375; Rem [+0.5]
l-(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
L - - - - - _ . - - - - _ - - - . - _ _ _ _ _ - - - - _ _ _ _ _ _ , _ _
- x x m-- ...
q e s:u ,M?n J;d . < , , s' J mu, ,
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a . , 1 m .g" I3. EPLANTSYSTEMS'(38dANDPLANT-WIDEGENERIC . Page118,
- , , RESPONSIBILITIES-(10%)
? ,,
j 'jp (L , l
'^
[L, l' " ' l$ .),
i l aje , -w '
-j L Eh l REFERENCE; <, 1 j.y -' ,
}
$;n'. ,. ~ 1. ;. LMdGuire: . OP-MC-RAD-HPM;; Objective.11. , , Il r j 4,' <
l .001010K404- 194001K103~ ..(KA's). j H
jlF ' ,
- j!
s LANSWERL L.3.37.: -(1.50) t 'a. .
lapprovalby'nShift.engineeri[+0.5] y p 'l verification (in. person or via phone). by Security [+0.5] - -
.+- <.. > .
l ,
,* b.L
- Health ~ Physics (Supervision)l '[+0.5]
, j i
. REFERENCE 1 l s
' 1 L l1. . ! McGuire: - S.D. 3.1.8,I" Access to Containment [" p. 2.:
1
}l 062000G0074 !003000G007 194001K105 ..(KA's) j
.1 ll . ..
\
lb l
? ANSWER- 4
. 3.38f ;(1.00). ,
.j a . ., iat11 east 5 .[+0.5] l i l' b.. .'(notLtoexceed).2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> -[+0.5] 'j
- REFERENCE. I i
.~ . -
1.-
McGuire: OMP, 1-7 section 6.1, I and J. l 1
E
.001050A202-- =194001K116- ..(KA's)
J 1
. ANSWER 3.39 (1.00)- i j
When under the' direction 'and in the presence of a licensed operator j or, licensed senior operator [+0.5]' as a .
.qua'lify 'for an operator license [+0.5] under (part 10 of his CFRtraining 55). to .
1 i
u 1
J i
(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
i I
_ __ ___--_-______--_d
y -- , . . m- .
.x 3 ,
g.
4;~t , 3. PLANT SYSTEMS'(38%) AND' PLANT-WIDE GENERIC Page119 RESPONSIBILITIES (10%)
A i
' REFERENCE-q . . .
1.. 'McGuire: 5.D. 3.1.4, ' Conduct. of Operations," Sec' 1.3.
194001A103. 003000K602 '003000K404 ..(KA's)' ..
ANSWER' .3.40' -(1.00)
An approved major change to a. procedure'[+0.5]. which.is valid ...
e[ . , only for 'a specified. period of. time' or duration of an event [+0.5]'.
+
(,
-g ~ REFERENCE.'
- 1. .McGuire: ES.D. 4.2.1, " Handling of Station Procedures."'
- 194001A103 000027K303 ...(KWs)
ANSWER 3.41 -(1.50)-
l- (1 16.
l- (2 16 28 72 8,
[+0.3] for each part.
i REFEP.ENCE i
- 1. McGuire: 0-M-P 1-7, Sec 6.2 B
'194001A109 000009G011 ..(KA's)
(***** END OF CATEGORY 3 *****)
(********** END OF EXAMINATION **********)
- ~-
mp'g!;g%y g, = - =
,- " n; .
g!
? ! .'. <,a
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-F Page 97f.
- _ I 7 2h ~ EMERGENCY AND' ABNORMAi.' PLANTi EVOLUTIONS '
U ', ,' (27%)s
,1 w -
1 LANSWER; -2.01S (1.00)L r"
1 L- 1_ (b . ) [+1.0]i ka E 1 IREFERENCE'
& ?1.- McGuire:' EP/1/A/5000/09,'" Loss 'of All AC Power."
l, ,
191006K108 '000055G011: ' . . (KA's) 191006$107
[',
'2.02L _(2.00) n.- ' ANSWER l'. , core exit T/Csi [+0.25] - stable or decreasing. [+0.25]
n , , . <.
,i NC subcooling - [+0.25]' - greater than 0 deg F- [+0.25]
. 2.
3.- . SG pressure _ [+0.25] - stable .or decreasing [40.25]
r '
- 4. NC hot' leg temperature [+0.25]'- stable or decreasing
- 5.. NC cold leg . temperature [+0.25] -Lat approx saturation temp for SG pressure [+0.25] .
Any four (4)-- of lfive (5) for total of [+2.0]
REFERENCE'
- 1. McGuire: EP/A/5000/2.2, " Post-LOCA Cooldown and-p
+ Depressurization," Foldout page..
p
'000011A209 191007K109 191007K104 . .(KA's) 1 i
n ANSWER ~ 2.0? -(1.00)
-(c.). - [+1'.0]
-(***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)
,x
_ . _ _ _ _ . . . . _ - . _ _ _ _ _ _ . _.__.__m__.___ __m__ _ _ _ _ ._____-__m_.__.______m__.__m_____--
L "' DRAFT COPY U. S. NUCLEAR-REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION REGION 2 FACILITY: McGuire I & 2 __
REACTOR TYPE: PWR-WEC4 i-
'DATE ADMINISTERED: 89/06/E6 CANDIDATE: #15754 ' C2/V -
INSTRUCTIONS TO CANDIDATE:
Use separate paper for the answers. Write answers on one cid: caly.
Staple question sheet on top of the answer sheets. Points for each question are indicated in parentheses after.the question. The passing grade requires at least 70%.in each category and a final grade of at
.least 80%. Examination papers will be picked up six (6) hours after the examination starts.
% OF CATEGORY % OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY 24.00~ 24.00 4. REACTOR PRINCIPLES (7%)
THERMODYNAMICS (7%) AND COMPONENTS (10%) (FUNDAMENTALS EXAM) 33.00 33.00 5. EMERGENCY AND ABNORMAL PLANT EVOLUTIONS (33%)
43.00 43'.00 6. PLANT ' SYSTEMS (30%) AND PLANT-WIDE GENERIC-RESPONSIBILITIES (13%)
100.00 % TOTALS FINAL GRADE All work done on.this examit.ation is my own. I have neither given nor received aid.
Candidate's signature
/
DRAFT COPY
_ _ - -___-___-_w
[
~
Page 2
< 4. ' REACTOR T'RINCIPLES '(7%) THERMODYNAMICS :
(7%) AND COMPONENTS (10%)-(FUNDAMENTALS EXAM)
-QUESTION .4.01 -(1.00)
WHICH ONE (1).of the following changes in plant parameters will result in a DECREASE-in the shutdown margin? (1.0)
(a.) power level is' decreased from 40% toL30% with no rod-motion and constant boron concentration
'(b.) shutdown banks are withdrawn during startup while maintaining constant NC. temperature and boron concentration
- (c.) bank'D rod height is increased from 125 steps to 200 steps while maintaining constant _ power and boron concentration
~
.(d.) boron concentration is decreased while maintaining constant power and no rod motion ANSWER 4.01 (1.00).
(d.) [+1.0)
REFERENCE
- 1. MNS: OP-MC-RT-RB, Objectives 8, 9, pp. 20 and 22.
192002K114 ..(KA's)
QUESTION 4.02 (1.00)
A control' rod has its greatest differential reactivity worth if it is inserted in WHICH ONE (1) of the following locations? (1.0)
(a.)- At the edge of the core.
(b.) At the center of the core.
(c.) In a high Xenon concentration area.
(d.) In a low fuel concentration area.
(***** CATEGORY 4 CONTINUED ON NEXT PAGE *****)
r=; -
4; REACTOR-PRINCIPLES'(7%) THERMODYNAMICS' Page 3 (7%) AND COMPONENTS (10%) (FUNDAMENTALS EXAM) s 4 t ,
? ANSWER: 4.02 '(1.00)-
. (b.) ' [+1.0]
REFERENCE
- 1. 'MNS: OP-MC-RT-RCO, ' Obj. 20,p.34-37
'192005KIO5
..(KA's)'
l
. QUESTION 4.03. '(1.00)
.'WHICH ONE- (1) of the following- sentences describes why the moderator
. temperature coefficient becomes more negative from BOL to EOL7 (1.0) ;
(a.)' A decrease in the fuel to clad gap over core age :
results in a' decrease in the fuel temperature.
(b.)- Baron concentration is reduced during core life to ,
i maintain power and as the core ages, fission product poisons build.up. l
'(c.) Plutonium build-up over core age results in more fissionable material being available to compete -
j with boron atoms for neutrons. ;
(d.) Rod withdrawal causes T-ave to increase, decreasing l moderator density, and allowing neutrons to travel farther, until they are absorbed by the rods.
)
ANSWER 4.03 (1.00) ']
(b.) [+1.0] l REFERENCE
- 1. MNS: OP-MC-RT-RCO, Obj. 8 & 14, pp. 21, 22, 24 & 26.
192004K106 ..(KA's) )
i
)
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r
J4. REACTOR PRINCIPLESJ(7%) THERMODYNAMICS Page 4 l-' (7%) AND COMPONENTS (10%) -(FUNDAMENTALS EXAM).
1 QUESTION-- 4.04'.'(1.00)
, . WHICH ONE-(1) of the following statements does 'NOT. describe why rod insertion limits are maintained during reactor operations? (1.0) ,
'(a.) . To; augment the effects of the moderator temperature coefficient over core life.
-(b.) 'To reduce the positive reactivity addition caused by an 17 ejected rod.:
(c.)' To prod'uce an axial- flux distribution that prevents high
. local . peak power levels. .
.(d.) To compensate.for the. effects of the power defect following a reactor trip.
ANSWER 4.04 (1.00)
(a.)~ [+1.0]
REFERENCE
- 1. NNS: OP-MC-CTH-CP, Obj. 35, p. 96, 97.
- 2. MNS: OP-MC-RT-RD, p. 4.
192005K115 ..(KA's)
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Page 5
- 4. REACTOR PRINCIPLES (7%) THERMODYNAMICS (7%) AND COMPONENTS- (10%) (FUNDAMENT ALS EXAM) .
L' QUESTION 4.05' (1.00)~
During a reactor start-up, an initial reactivity. addition causes count rate to increase from 20 CPS to 40 CPS. A second reactivity addition-causes the count rate to increase from 40 CPS to 80 CPS.
WHICH ONE (1)'of the following statements is CORRECT 7 (1.0) r (a.) The first reactivity addition was smaller.
(b.) The second reactivity addition was smaller.
(c.) The first and second reactivity additions.were equal.
(d.) There is insufficient data given to determine relationship of reactivity values.
ANSWER 4.05 (1.00)
-(b.) [+1.0)
REFERENCE
- 1. McGuire: OP-MC-SPS-RT-SM,-Obj. 6, 7,'8, & 10, p.12-16.
192008K103 ..(KA's)
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i;
- 4. REACTOR PRINCIPLES (7%) THERMODYNAMICS Page 6' (7%) AND COMPONENTS (10%) (FUNDAMENTALS EXAM) 1
. QUESTION 4.06 (1.00).
WHICH ONE (1) of the'following statements.concerning power defect is correct?- (1.0)
(a.) The power defect is-the difference between the measured power coefficient and the predicted power coefficient.
(b.) The power defect increases the rod worth requirements necessary to maintain the desired shutdown margin following
, a reactor. trip.
L (c.) Because.of the higher boron concentration, the power defect is.more negative at beginning of core life.
(d.) The power defect necessitates the use of a ramped Tavg program to maintain an adequate RCS subcooling margin.
ANSWER 4.06 (1.00)
(b.)~ [+1.0]
REFERENCE
- 1. Westinghouse Reactor Core Control for Large PWRs, pp. 3 '29 to 3-41.
- 2. McGuire: OP-MC-RT-RCO, " Reactivity Coefficients," Objective 13 and 14.
192004K113 ..(KA's) i
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)
A ' '
l ,
Page '7 b6' 4. REACTOR ' PRINCIPLES (7%) THERMODYNAMICS (7%) AND COMPONENTS (10%)-(FUNDAMENTALS' EXAM)-
e
,4 b-b QUESTION 4.07 (1.00)
WHICH ONE (1):of the'following-phrases correctly completes the-
- sentence.
[" As the core ages from BOL'to EOL,.the. ratio of Pu-239 atoms to
- :U-235 atoms increases. This changing ratio causes the....... (1.0)-
L(a.). r eactor SUR'to increase for a given reactivity additio.1.
p (b.). void coefficient to become less negative.
(c.)- ,-moderator, temperature coefficient to become less negative.
', (d.)- . delayed neutron fraction to increase.
ANSWER- 4.07. (1.00)
(a.). [+1.0)
REFERENCE
- 1. McGuire: OP-MC-RT-FP, " Fission Process," Objective 7.
- 2. Westinghouse Reactor Core. Control, Chapter 2.
192003K106 ..(KA's)
QUESTION 4.08. (1.00)
WHICH ONE (1) of the following statements is correct about departure from nucleate boiling (DNB)? (1.0)
,(a.) Increasing RCS pressure decreases =the margin to DNB.
(b.) -Increasing. coolant flow rate decreases the margin to DNB.
- (c.) Increasing core inlet temperature increases the margin to DNB.
(d.) Increasing. reactor power decreases the margin to DNB.
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g ,.
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Page 8- -]
b4.>iREACTOR PRINCIPLES (7%)' THERMODYNAMICS:
(7%) AND COMPONENTS (10%) (FUNDAMENTALS EXAM)
- y, .
i
.l',
.q ANSWERi ~ 4.08i:(1.00);
'(d.) ~ [+1.0] - ,
, REFERENCE ~
1.- McGuire:' OP-CN-THF-HT, Obj. 6.c, p.-17.-
2.- .McGuire: .OP-MC-CTH-CP, Obj. 26 l193008K105' _..(KA's)
- QUESTION '4.09; L(1.00)
If a relief valve opens with 885 psig saturated steam,iWHICH ONE (1) of the following.is_the temperature of;the pipe downstream of the relief valve. assuming it is vented to the atmosphere? (1.0)'
'(a.) 212.deg F
"(b.)- ' 308~deg F-(c.) 532 deg F
'(d.)- 705'deg F ANSWER 4.09 (1.00)
(b.) . [+1.0]
REFERENCE-
- 1. McGuire: Steam Tables.
-193004K115 ..(KA's)'
~
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h y s' c
e4. ' REACTOR PRINCIPLES (7%)' THERMODYNAMICS .
Page 9 (7%) AND COMPONENTS (10%) (FUNDAMENTALS EXAM)
E ,,
QUESTION 4.10 (1.00)
.WHICH ONE (1)' of the following is NOT an example of a circumstance
- which can cause water hammer?. (1.0)
L i
. (a.)' sudden closure of a valve in a system in which there is l' *
' water flow:
i (b.) cavitation occurring at a flow orifice in a closed system.
(c;) . rapid pressurization of an otherwise stable system ,
(d.)'- ' starting.a pump on a partially empty system ANSWER 4.10 .(1.00)
(c.) [+1.0]
REFERENCE
- 1. . McGuire: OP-MC-THF-FF, " Fluid Flow," Objective 12a.
193006K110- ..(KA's)
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' 4. REACTOR: PRINCIPLES (7%) THERMODYNAMICS Page 10 (7%) AND COMPONENTS (10%)-(FUNDAMENTALS EXAM)
QUESTION 4 J, ! (1.00)
WHICH~0NE (1) of the.following sentences describes the reason for the height correction factor (K(Z)) used in the heat flux hot channel factor _ calculation? (1.0)
'(a.) . K(Z); compensates for the increased coolant temperatures that occur higher in the coolant. channels.
(b.) K(Z) takes into account-that there is some delay in refilling the core following a LOCA. -
(c.) K(Z) is an uncertainty factor to allow for conservatism, since core flow cannot be accurately. measured.
(d.) K(Z) allows for greater power production in the upper regions of the core near the end of life, due to axial flux. _ shifting.
-ANSWER 4.11 (1.00)
(b.) .[+1.0]
REFERENCE
~1. MNS: OP-MC-CTH-CP, Objectives 14 & 15, pp. 92-94.
193009K105 ..(KA's).
i QUESTION 4.12 (1.00)
Hot channel factors are normally only measured periodically l by performing incore flux maps. This is sufficient to ensure the j core is operated as designed, provided that five (5) operational limitations are monitored and maintained. l l
STATE FOUR (4) of these five (5) operational limitations. (1.0) l
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1 ._. - _ _ _ _ _ _ _ _ _ - _ -
jir l4. REACTOR PRINCIPLES (7%) THERMODYNAMICS Page 11 (7%) AND COMPONENTS (10%) (FUNDAMENTALS EXAM)
ANSWER' 4.12 (1.00).
- 1. Rodtogroupalignmentismaintained.(within+/-12 steps) 2 '. Rod banks are(sequencedhnd) overlapped,
.3. Rod Insertion Limits are maintained.
'4. Axial Flux Difference limits are maintained.
- 5. QPTR is maintained within limits.
any four (4) [+0.25]. each REFERENCE
- 1. McGuire: OP-MC-CTH-CP, Obj. 32, pp. 95 & 96.
193009K107 ..(KA's)
QUESTION 4.13 (100)
Transferring energy from the fuel to the reactor coolant requires several different types of heat transfer.
WHICH ONE (1) of the following statements is CORRECT? (1.0)
(a.)~ Heat transfer through the fuel pellet is via convection.
(b.) Heat transfer across the zire clad is via convection.
(c.) Heattransferacrossthelaminarwaterlayer(nearestfuel) is via conduction.
(d.) Heat transfer from the laminar film into the bulk of the coolant is via conduction.
ANSWER 4.13 (1.00)
(c.) [+1.0]
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[9- 3 ,
, ' :D '4. I REACTOR PRINCIPLES-(7%). THERMODYNAMICS Page ji .(7%) AND COMPONENTS (10%) (FUNDAMENTALS EXAM)
[. ,
B:'? ..
REFERENCE-
- 1. McGuire
- L OP-CN-THF-HT, Obj. la, 2a, & 2c, pp. E - '.
L2. 7 McGuire: 'OP-MC-TA-AM, p. 25. .
i193007K101 "..(KA's) i
- g. ,
b ' QUESTION'. 4.14L (1.00)
~ " .' If the NCPs isolated, WHICHare:.tripp(ed:following ONE a LOCA and the breek.has been-1) of:the fo best subcooling?s -(1.0)
F ,
.PZR PRESSURE. '. HOT LEG TEMP
. COLD LEG TEMP 500 470-(a.)' 600 800. 530 510 (b.)-
(c.) .1000 540 .530 1200- 570 560 (d.)
ANSWER- 4.14 (1.00)
- (c.) [1.0]
-REFERENCE
- 1. Steam Tables 193003K125 193003K117 ..(KA's)
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m f
Page 13'
- 4. REACTOR PRINCIPLES (7%) THERMODYNAMICS-
-(7%) AND COMPONENTS (10%)-(FUNDAMENTALS EXAM) hN >
g'
-QUESTION L4.15'.(1.00)
WHICH ONEi(1)'of the.following parameter changes would cause the
~
" outlet: temperature of the KC system heat exchangers to DECREASE?
Assume all other parameters are held constant. .(1.0) o
.(a.) A decrease in 'th'e NCPl thermal barrier temperature.
(b.)1 .An increase in KC system pressure.
.(c.) A decrease'in'the sealwater' heat exchanger temperature.
An increase in RN' system flow.
^
.(d.)'
ANSWERL 4.15- (1.00) q (d.) [+1.0)
' REFERENCE
- 1. MNS:: OP-MC-PSS-KC,' Objective 3, pp. 6-9.
191006K107 .191006K108 ..(KA's)
QUESTION 4.16 (1.00)
Concerning_the mixed bed demineralizers:
- a. WHAT is the maximum flow that each demineralized is sized (0.25) to accept?
- b. HOW are demineralized resins protected from high temperatures?
E INCLUDE setpoint. (0.75) n
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1
L:
Page 14 l4. REACTOR PRINCIPLES (7%) THERMODYNAMICS (7%) AND COMPONENTS (10%) (FUNDAMENTALS EXAM)
ANSWER 4.16 (1.00)
- a. 120'gpm [+0.25]
- b. IfNVletdowntemperatureincreasesto138(+/-2)degF[+0.25],
(letdown HX outlet diverter valve [NV-127]) diverts letdown from the (bypasses) demineralizers (to the VCT) [+0.5]
REFERENCE
- 1. MNS: OP-MC-PS-NV, Objectives 2E, 3A, 3J, 3K, 5, 9, pp. 7 and 16.
191007K109 191007K104 ..(KA's)
QUESTION 4.17 (1.00)
, WHICH ONE (1) of the following statements correctly describes the effects of post-transient downcomer voiding on source range detector response? (1.0)
(a.) Source range level increases with increasing downcomer void fraction.
(b.) Source range level decreases with increasing downtomer void fraction.
(c.) Source range level initially increases as downcomer void fraction increases, and then decreases when downcomer void fraction becomes exceptionally large.
(d.) Source range level initially decreases as downcomer void fraction increases, and then increases when i~
downcomer void fraction becomes exceptionally large.
ANSWER 4.17 (1.00)
(a.) [+1.0)
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c -
- c '
o
-4.= REACTOR. PRINCIPLES (7%) THERMODYNAMICS Page 15l
(
__7%).ANDCOMPONENTS-(10%)(FUNDAMENTALSEXAMl
- u REFERENCE m , ~ 1. .MNS: .- OP-MC-TA-AM, 'Obj. Sc, Sg, p. 45. .
191002K117 ...(KA's).
QUESTION 4.18 .(1.00)-
WHICH.ONE;(1) of the following phrases CORRECTLY con.pletes the-sentence?
"In the condensate system,'the operating point for two pumps operating.in parallel;will be at-as' compared,to the operating point when one pump is. operating and the other pump. is isolated." (1.0).
(a.). the same flow rate and thefsame discharge' pressure
.(b.) .a higher flow' rate and the same discharge pressure (c.)' -a higher flow rate.and an increase in discharge pressure (d.) the same flow rate and an increase in discharge pressure
. ANSWER. 4.18 (1.00)
-(c.) . [+1.0]
REFERENCE
- 1. McGuire: OP-MC-THF-FF, Obj. 6e, pp. 22-23.
1 191004K109 ..(KA's)
L- QUESTION 4.19 (1.00)
STATE two (2) advantages of a counterblow heat exchanger over a parallel flow heat exchanger. (1.0)
L 1
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o - - _ - - _ _ _ __
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- 4. 'REACTO PRINCIPLES (7%) THERMODYNAMICS Page 16 (7%) AND COMPONENTS (10%) (FUNDAMENTALS EXAM)
ANSWER 4.19 (1.00) 1
- 1. more uniform temp difference between the two (2) working fluids minimizes thermal stresses in Hx. ;
.2. Heat transfer rate is greater than for a. parallel heat exchanger of the same size.
- 3. moreuniformtemperaturedifferencebetweenthetwo(2) working fluids, produces a more uniform rate of heat transfer (average delta-T is at its. maximum all along the tubes). (,m % cf/44rd.)
Any two (2) [+0.5] each, [+1.0] maximum.
REFERENCE
- 1. McGuire: OP-CN-THF-HT, " Heat Transfer," Obj. 7.a. p. 18.
191006K107 ..(KA's)
QUESTION 4.20 (1.00)
What must be done to an Engineered Safeguards valve after it has-been manually operated? (1.0)
ANSWER 4.20 (1.00)
Must be cycled electrically (to assure operability) [+1.0]
REFERENCE
-1. McGuire: OP-MC-PS-ND, Obj. 7 & 8, p.5.
191001K108 ..(KA's)
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y _ _ _ _ _
g' , x L. ,
'4. : REACTOR PRINCIPLES-(7%)' THERMODYNAMICS Page 17 (7%) AND COMPONENTS (10%) (FUNDAMENTALS EXAM) l 1,,
QUESTION- l4.21 (1.00)
H- NCP " Limits-and Precautions" state "within any two-hour period,
', the number of starts ~should be limited to a maximum of three (3) with a minimum idle period of. thirty (30). minutes priorf to restart."
I
.WHAT is the basis'for this precaution? (1.0) r LANSWER 4.21- (1.00)
(Too frequent starting of the NCP may result'in) damage to the NCP
. motor-(windings) [+0.5] due to excessive heat generated -(during starting) [+0.5].
REFERENCE
- 1. McGuire: OP-MC-PS-NCP " Reactor Coolant Pump," Objective 10.
191005K106 ..(KA's) 0DESTION 4.22 (2.00)
ANSWER the following questions concerning level detectors,
- a. WHY is the indicated level lower than actual level in a system where reference leg temperature is less than.the temperature at which it was calibrated? (1.0)
- b. HOW is the pressurizer level indication system assured to be accurate for all temperature ranges? (1.0) l
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- 4. REACTOR PRINCIPLES (7%) THERMODYNAMICS Page 18 (7%) AND COMPONENTS (10%) (FUNDAMENTALS EXAM)
ANSWER 4.22 (2.00)
-a.- Due to the density of the fluid in the reference leg being greater than the density of the rest of the fluid [+0.5].
As a. result a larger differential pressure results [+0.5]
(which makes indicated level lower than actual level).
- b. three channels are calibrated for hot operating conditions
[+0.5] and the fourth channel is calibrated for plant cooldown conditions [+0.5].
REFERENCE
- 1. Westinghouse, Thermal-Hydraulic Principle and Application to PWR-11, chapter 11-28.
2.- McGuire: OP-MC-PS-ILE, " Pressurizer Level Control," Obj.1.c,1.0 191002K107 191002K108 ..(KA's)
QUESTION 4.23 (1.00)
WHICH one (1) of the following statements is CORRECT concerning the intermediate range compensated ionization chambers? (1.0)
(a.) The boron lined chamber is sensitive to neutron and gamma radiation, while the unlined chamber is sensitive only to gamma rays.
(b.) The compensated ion chamber is designed to remove the gamma signal only at high reactor power levels.
(c.) Undercompensation will cause loss of some neutron current as well as blocking gamma current.
(d.) Gammas which penetrate the detector's lead shielding will cause ionization which results in a voltage pulse.
AMSWER 4.23 (1.00)
(a.) [+1.0]
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4
- _ _ - _ _ _ _ _ l
,a j;fi , , ;. ;
< 7h.'
.. 4; REACTOR PRINCIPLES-(7%)z THERMODYNAMICS Page.19
'.O ~~
(7%) AND COMPONENTS (10%): (FUNDAMENTALS ~ EXAM)
, T ' REFERENCE McGuire: OP-ME-IC-ENB,' " Nuclear Instrumentation," Obj. 4,' 6, & 7
- 1.
g 191002K118~ ...(KA's)'
k r
r 1
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l r
i
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- 5. EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 20 (33%)
QUESTION 5.01 (1.00)
In addition to T/Cs NOT less than 1200 deg F WHICH ONE (1) of the following also represents a red path for core cooling assuming subcooling condition is less than zero? (1.0)
At least One RVLIS RCP Running Core Exit Temperature Vessel Level (a.) no greater than 700 deg F greater than 43%
(h.) yes less than 700 deg F greater than 43%
(c.) no greater than 700 deg F less than 43%
(d.) yes less than 700 deg F less than 43%
ANSWER 5.01 (1.00)
(c.) [+1.0]
REFERENCE
- 1. McGuire: EP/12.1, " Response to Inadequate Core Cooling."
- 2. McGuire: OP-MC-EP-EP7, Objective B.
000074G011 ..(KA's)
QUESTION 5.02 (2.00)
According to EP/1/A/5000/2.2 " Post-LOCA Cooldown and Depressurization" foldout page, WHAT are FOUR (4) conditions that indicate that natural circulation flow is occurring? INCLUDE parameter and expected conditions. ASSUME containment conditions are normal. (2.0) l l
l
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- 5. EMERGENCY AND: ABNORMAL PLANT EVOLUTIONS.
(33%).
Page 21
]
'1
<, I
' ANSWER 5.02 (2.00)i
- 1. .. co re .~ exit T/Cs ' [+0.25] . - stable or' decreasing '- @0.25] ,
- 2. NCLsubcooling - [+0.25] - greater thanl0 deg F - [+0.25]
- 3. SG pressure [+0.25] - stable or decreasing [+0.25] ~
-4. NC hot leg temperature [+0.25] - stable or decreasing .
- 5. NC. cold leg temperature [+0.25] - at' approx saturation temp'
, for SG pressure [+0.25]:
Any four (4) of five '(5)' for total of [+2.0]
REFERENCE il. 'McGuire: EP/A/5000/2.2, " Post-LOCA Co' oldown and Depressurization," Foldout page.
000011A209 ...(KA's)
QUESTION 5.03 (1.50)
As a result of a steam line break, you are directed to EP/1/A/5000/14.1,
" Response to Imminent Pressurized Thermal Sho:k Conditions," due to a red path condition oli an excessive cooldown rate and NC system pressure limits. Step 10 of this EP has you terminate SI, if the SI termination criteria is met.
STATE THREE (3) reasons for terminating SI. .(1.5)
ANSWER 5.03 (1.50)
- 1. SI may be contributing to the cooldown [+0.5]
2.. Poor mixing of SI will increase thermal stress [+0.5]
- 3. SI may cause the plant to repressurize [+0.5]
)
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.=-__-____-____-_-___:-_--_-_-_-_-_-__-____--_-_-__-____-_-_____-__-_____.
- p. ;n 6,
$ 15. EMERGENCY AND' ABNORMAL PLANT EVOLUTIONSJ Page 22:
(33%)-
g
[;
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- REFERENCE
- 1. 'MNS:' OP-MC-EP-EP9, Objective B.2.. p. 7.
- 2. MNS: 'EP/1/A/5000/14.1,'" Response to Imminent Pressurized.
Thermal Shock Conditions."
, l000040K101 ..(KA's)
(QUESTION . 5.04 ' -(1.00).
WHY is there a precautionary note in EP/1/A/5000/09, " Loss of All
~
-A/C Power";, to monitor the CSF Status Trees for.Information only,'
but.not for purposes of implementation?- (1.0) l-ANSWER 5.04 (1.00)
Because none of the electrically powered safeguards equipment
.used to. restore Critical Safety Functions is operable. [+1.0]-
-(noneof'theFRG's.canbeimplemented).
REFERENCE
- 1. Westinghouse Background Information for ECS O.0 Users Guide for ERG's'and Background Documents,
- p. 17/18.
- 2. McGuire: EP/1/A/5000/09, p. 2.
000057K301 ..(KA's)
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- 5. EMERGENCY AND ABNORMAL PLANT EVOLUTIONS-Page 23 )
(33%)
QUESTION 5.05 (2.50)
While performing PT/1/A/4600/01, "RCCA Movement Test," a control rod is dropped. ;
- a. STATE THREE (3) indications or alarms that would show such an event occurred. (1.5)
- b. WHAT are ALL the immediate actions that must be taken according to AP/1/A/5500/14, " Rod Control Malfunctions?" (1.0)
ANSWER 5.05 (2.50)
- a. 1. 0D DROP alarm
- 2. RPIATBOTTOM[dbottomlight individual ro
- 3. P/R HI NEUTRON FLUX RATE ALERT alarm
- 4. P/R CHANNEL DEVIATION alarm
- 5. decrease in Tavg
. Any three (3) [+0.5] each,
- b. 1. Place CRD selector in manual [+0.5]
- 2. check if reactor trip is required: [+0.5]
[(a) 2/4 PR high flux rate bistables actuated (b) ensure reactor trip and go to AP/1/A/5500/01,
" Reactor Trip"]
REFERENCE
- 1. HNS: AP/1/A/5500/14, " Rod Control Malfunction," p. 6.
- 2. MNS: OP-MC-IC-IRE, Objective 11.
- 3. MNS: OP-MC-IC-EDA, Objectives 4 & 5.
000003A201 000003K304 ..(KA's)
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Page 24' /
5 .' EMERGENCY AND ABNORMAL PLANT EVOLUTIONS' (33%)
i: !
QUESTION 5.06- (2.00) l- Unit 1 just experienced an ATWS. The turbine did not trip following manual trip of the reactor. WHAT actions are'you_ required to take according'to EP/1/A/5000/11.1, " Response to Nuclear Power Generation /
ATWS~ " if'a manual turbine trip is ineffectual (i.e., the expected responseisnotobtained)? (2.0)
L l
l l' ANSWER 5.06 (2.00)
If the turbine not tripped, then:
- 1. stop both DEH pumps [+0.5]
- 2. place turbine in manual and close GV's in fast action [+0.5]
- 3. locally trip the turbine [+0.5]
If the turbine will not trip, close all SG SM isolation valves [+0.5]
REFERENCE
- 1. MNS: EP/1/A/5000/11.1, " Response to Nuclear Power Generation /ATWS."
- 2. MNS: OP-MC-EP-EP6, Objective B.2.
000029A113 000007A107 ..(KA's)
QUESTION 5.07 (1.50)
AP/1/A/5500/04, " Loss of Reactor Coolant Flow," is being performed due to NC (RCP) pump "A" tripping at 43% power. The procedure contains a caution that the NC pump may not be restarted unless below 25% nuclear power.
- a. What is the basis for this caution? (1.0)
- b. WHY must NC 27 (A Loop PZR Spray Control) be closed before starting NC (RCP) pump A? (0.5)
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- 5. EMERGENCY AND ABNORMAL PLANT EVOLUTIONS (33Ss) p l
ANSWER 5.07 (1.50) a.- Prevent a reactivity excursion tha't could occur due to 17 cold water addition. [+1.0]
b.- (Starting the NCP with the spray valve open could result in) rapid pressure decrease due to PZR Spray Flow (when the NCP is started). [+0.5]
REFERENCE
- 1. McGuire: OP-MC-PS-NCP, " Reactor Coolant Pump," Objective l' 10, pp. 11 and 13.
- 2. McGuire: AP/1/A/5500/04, " Loss of Reactor Coolant Flow."
- 000015G007 ..(KA's)
L QUESTION '5.08 (1.00)
WHICH ONE (1) of the following is NOT an immediate operator action for EP/1/A/5000/09 " Loss of All AC Power"? (1.0)
(a.) Manually exercise Rx Trip Train IA and IB switches.
(b.) . Verify CA flow - greater than 450 gpm.
(c.) ' Try to energize 4160 y bus with D/G from control room.
(d.) Initiate NC pump seal injection from SSF per procedure.
ANSWER 5.08 (1.00)
(b.). [+1.0]
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v- ..
3 a; . .t
?52 EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 26-(33%).
o REFERENCE-
. . 1. .McGuire: EP/1/A/5000/09, " Loss of All AC Power."
000055G011- ..(KA's) J i
j.,
-QUESTION- 5.09 (1.50).
'In accordance with EP/1/A/5000/02,."High Energy.Line Break Inside' of Containment," foldout page: l
- a. . WHAT are the NC pump trip criteria? (1.0) .s i
- b. IWHAT is the reason' for tripping the NC pumps when the trip criteria are met? (0.5) i' l
.i
.l L- LANSWER: 5.09 (1.50) a.
If flow verified subcooling less from one than or NVtoor0NI equal degpump F 0.5 [+[+0.5))and
. NC system !
1 L Necessary to minimize inventory loss for SDLOCA (to limit core l uncovery and peak clad temperature) [+0.5]. l REFERENCE.
- 1. MNS: EP/1/A/5000/02, HELBIC foldout page.
- 2. MNS: OP-MC-EP-EP2, Objective B3, p. 18.
l-000009K323 ..(KA's) l i 1 ;
q 1
1'
\
I 1
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- 5. EMERGENCY AND ABNORMAL PLANT EVOLUTIONS- Page 27 (33%) )
i
.i d
QUESTION 5.10 (2.00) J Assume McGuire Unit I has suffered a large SG tube rupture that results in .a reactor trip and SI actuation. In addition to high activity >1evels in the secondary:
- a. WHAT are TWO (2) SG indications that can'be usec' to determine which SG has a tube rupture? (1.0)
- b. STATE TWO (2) reasons why isolation of the SG is necessary. (1.0)
ANSWER 5.10 (2.00) AM8
- a. 1. rapidly increasing water level in the- affected SG
- 2. steam flow /feedwater flow mismatch in the affected SG [+0.5]
b.
1.
% semp/< .f 5/GA E ra,$)
limit the spread of contamination [+0.5]
w ay**A&%fo% % q
- 2. allow maintaining ruptured SG pressure above the pressure of the intact SG's, as a prerequisite for stopping break flow S-jg Nc.s M
[+0.5] (W S/51%j(>w)- 4 pc,p m 4 e.a . 0 REFERENCE
- 1. MNS: OP-MC-EP-EP-4, Objective C.
- 2. MNS: EP/1/A/5000/04, " Steam Generator Tube Rupture."
000038A202 000038A101 000038A203 ..(KA's)
QUESTION S.11 (1.00)
With Unit 1.in Mode 6, WHAT are the immediate actions if both source ran3e nuclear instruments are lost according to AP/1/A/5500/16,
" Malfunction of Nuclear Instrumentation System" (Case I - Source Range Malfunction)7 (1.0) r
(***** CATECORY 5 CONTINUED ON NEXT PAGE *****)
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I 52 EMERGENCY AND~ ABNORMAL PLANT EVOLUTIONS Page 28 is L, ,
(33%)
r c.p L ANSWERL 5.11- -(1.00)l q
- (If. Source Range lost in Mode 6, then) suspend core. alterations and-positive reactivity changes. [+1.0] (to .y s a m)
C
[ REFERENCE
.1. . McGuire: AP/1/A/5500/16, " Malfunction of Nuclear Instrumentation System Case 1," p. 2.
p 000032G011 000032K302 ..(KA's)
QUESTION. 5.12- _1.50) (
-Assume the unit is in cold shutdown with'the NC drained for mid loop operation:-
- a. .HOW will ND pump cavitation be detected? (0.5)
- b. WHAT immediate action according AP/1/A/5500/19, " Loss of Residual Heat Removal System," (Case I-Loss'of ND Train (s)
During Decay Heat Removal) are you required to take?. (0.5)'
c.- WHAT action are you required to take if the action in part b.
CANNOT be satisfied? (0.5)
-ANSWER 5.12 (1.50)
.a. current, flow, pressure, level oscillations (accept pump any one / loop (1) symptom for full credit)
[+0.5]
- b .- Check NC System:
1.. NC loop pressure - Less than 555 psig [+0.5]
mas: no m p n w 4 eed st m a ,a - a.u. n
- c. 1.
2.
Ensure:1ND-1B and 2A closed. [+0.25]
Stop operating ND pumps. [+0.25]
Nwg mf
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= - -
p gc s m
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Page 29,
, 5." EMERGENCY,AND' ABNORMAL' PLANT EVOLUTIONS
$p (33%)-
l :p t
. a_
t' ;
'LREFERENCE
- 1. ~. 'McGuire: R AP/1/A/5500/9, " Loss of Residual' Heat Removal:
P, ' . ,
System" (Case I)."
^
000025A207 000025K303 . .-. (KA's) 3- ,
QUESTION- 5.13 ~(2.00)-
[c AP/1/A/5500/01 " Reactor Trip," step 5, verifies SI Status.
h
- a. STATE THREE (3) indications that~'you have to verify to ensure -
'that SI'is NOT required. INCLUDE in your answer the applicable-setpoint condition of each indication. (1.5)-
- b. . . STATE ONE (1) indication that you.would have to verify'to ensure
,that SI is NOT actuated. INCLUDE in your answer the required condition of the indication.. (0.5) s ANSWER 5.13. .(2.00)
- a. 1. Containment Press [+0.25] - Less than 1 psig [+0.25]-
- 2. . S/G PZR Press [+0.25? - Greater than 18b~5B5 psig7+0.25]sig [+0.2
- 3. Steam Press [+0.25] - Greater th. an
'b. " Safety. Injection Actuated" status light [+0.25] - dark [+0.25]
REFERENCE
- 1. McGuire: AP/1/A/5500/01, " Reactor Trip."
000007K301 ..(KA's)
[
l',
... . QUESTION'-
5.14 (1.00)
A EP/1/A/5000/09, " Loss of All AC Power," step 18 has you depressurize intact S/Gs to limits of TABLE I. WHAT is the basis for these limits?
See attached procedure. (1.0)
I
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I_ _ _ - _ _ . -. _ _ _ _ _ - _ _ _ - - _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _
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i5. EMERGENCY AND ABNORMAL PLANT EVOLUTIONS t ,
(33%)-
h >
ANSWER. 5.141 '(1.00) y '
-l 1. l Prevent the core' returning:to critical due to moderatorL r
. temperature effects [+0.5].
h
- 2. Prevent injection of accumulator nitrogen into the NC--
I'
~
system [+0.5].
? -
- REFERENCE-1.- McGuire: EP/1/A/5000/09, " Lass of All AC Power," p. 10, step l' .-
118.
1000055K302 ..(KA's)'
- QUESTION- 5;15- 41.00) a-A control room evacuation is necessary. Under WHAT condition should .
AP/1/A/5500/17, " Loss of Control Room" NOT be used? (1.0) 5.15 ANSWER: :(1.00)-
Should not be used if a plant fire is forcing control room evacuation. [+1.0]-
REFERENCE
- 1. McGuire: AP/1/A/5500/17 " Loss of Control Room", p. 8.
000068G011 ..(KA's)
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l
F.
I
- 5. EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 31 l (33%)
l QUESTION 5.16 (1.00)
Per EP/1/A/5000/13.1, " Response to Loss of Secondary Heat Sink,"
feed and bleed must be initiated if subcooling is less than 0 deg F and steam generators have dried out.
- a. STATE the indications of steam generator dryout under normal
' containment conditions. (0.5)
- b. STATE the indications of steam generator dryout during adverse containment conditions. (0.5)
ANSWER 5.16 (1.00)
[.c Als
- b. Core exit T/Cs increasing [+0.25] and PZR PORVs open or I PZR pressure greater than 2335 psig [+0.25].
REFERENCE
- 1. MNS: OP-MC-EP-EP8, Objective B.1.
000054K304 ..(KA's)
QUESTION 5.17 (1.50)
Per AP/1/A/5500/40, " Loss of Refueling Canal Level:"
- a. STATE FOUR (4) symptoms of a loss of refueling canal level. (1.0)
- b. WHAT are TWO (2) sources of makeup water to the spent fuel pool? (0.5)
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_ _ _ _ _ _ _ _ _ _ . _ i
l;
- 5.- EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 32.
(33%)
ANSWER 5.17 (1.50)
- a. 1. " Spent Fuel Pool Level Low" Computer Alaru (M y he).
- 2. ' Decreasing Level in Refueling Canal (vi.a #em guv%y
- 3. " Incore Instrument- Room Sump Hi Level" Alarm'Cersed
- 4. EMF-16 " Refueling Bridge" Alarm
- 5. . EMF-17 " Spent Fuel Building" Alarm Any four (4) [+0.25] each I
.b. 1. FWST 2.- (Demineralized water from) RMWST .
3; Nuclear. Service Water (gg)
. Any two (2) [+0.25] each REFERENCE 1.. McGuire: . AP/1/A/5500/40, " Loss of Refueling Canal Level."
- 2. - McGuire: OP-MC-SPS-SY-KF, Obj. 5 000036K303 000036A202 ..(KA's)
- QUESTION 5.18 (0.50)
(FILLintheblanks)
In responding to AP/1/A/5500/23, " Loss of Condenser Vacuum," the operator must manually trip the turbine if exhaust hood' temperature
-exceeds or main condenser vacuum drops below and no turbine trip has occurred. (0.5)
ANSWER 5.18 (0.50) exhaust hood temperature > 250 deg F [+0.25]
main condenser vacuum < 20" Hg [+0.25]
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_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - i
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.t s De */ "5.
EMERGENCY?AND: ABNORMAL' PLANT EVOLUTIONS Page 33-j@ (33%)-
> S
' REFERENCE
- 1. McGuire: AP/1/A/5500/23, " Loss of Condenser Vacuum."
000051A202; l
..(KA's)
QUESTION: 5.19 (1.50)
'_WHAT are FIVE (5) conditions that1 require emergency boration according to AP/1/A/5500/38, " Emergency-Boration?"- (1.5)-
ANSWER 5.19 _(1.50)-
- 1. - Excessive' control rod insertion.
- 2. Failure of.two or more control rods to drop following a reactor trip.
3.: Unexplained or uncontrolled reactivity increase.
- 4. Inadequate shutdown margin.
' 5. ~ Control rod bank Lo-Lo limit alarm.
- 6. Less_than 2000 ppm boron in Mode 6.
Any five (5) [+0.3] each REFERENCE 1.- McGuire: AP/1/A/5500/38, " Emergency Boration."
000024G010 ..(KA's)
QUESTION 5.20 (1.00)
While at 100% power the "PZR HI PRESSURE" alarm was received. Per AP/1/A/5500/11, " Pressurizer Pressure Anomalies" (Case II-Pressurizer Pressure Increasing), WHAT immediate actions are you required to take? (1.0)
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Page 34
- 5. EMERGENCY AND ABNORMAL PLANT EV0LUTIONS (33%)
ANSWER _5.20 (1.00)
- 1. Check all Pzr Press channels -- indicating the same. [+0.33]
- 2. Verify all Pzr Htr Grp Sup BLrs -- off. [+0.33]
- 3. Check Pzr Spray Control vtlves -- open (INC-27 and INC-29). [+0.3 REFERENCE
- 1. McGuire: AP/1/A/5500/11," Pressurizer Pressure Anomalies" 000027K303 ..(KA's)
QUESTION 5.21 (2.50)
- a. Per AP/1/A/5500/35 "ECCS Actuation During Plant Shutdown" imediate actions, WHAT conditions must exist which would require the operator to proceed to EP-01 " Safety Injection"? (1.5)
- b. WHAT are the other immediate a,tions that must be taken if the transition to EP-01 was NOT required? (1.0)
ANSWER 5.21 (2.50)
- a. 1. NC syste.m T-Ave greater than 350 degrees AND EITHER [+0.5]
- 2. NC system pressure decreasing abnormally OR [+0.5]
- 3. Containment temperature, humidity or pressure increasing abnormally. [+0.5]
- b. 1. Open or verify open the following to ensure operable NV pump (s)ialigned to FWST (INV-221,1NV-222). [+0.5]
- 2. Ensure Pzr PORVs actuate to provide overpressure protectionE to.aCJ IF T. Ave is less than 300 degrees. [40 6]
no.ac]
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Y, O>e
- 5. EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page.35
'7 s
-(33%)
y L.n ,
p REFERENCE-.
rig r R 1.: .McGuire: AP/1/A/5500/35 "ECCS A'ctuation DuriAg; Plant Shutdown"-
000009G011 1 ..(KA's)..
y b
I QUESTION. 5.22 (1.50)I WHAT. are the 'immediate actions.for loss of ETA or ETB per.
JAP /1/A/5500/07, " Loss of Electrical: Power?" (1.5)..
v.
ANSWER 5.22 '(1.50)
. MD
- 1. ~ Verify D/G starts and loads on.the affected bus.^[+0.5]
2.. ' Verify # 1 TD.CA pump running [+0.5]
- 3. ~ Notify Unit 2 operator. to start 2A RN pump. [+0.5]
REFERENCE'-
3
- 1. McGuire:- AP/1/A/5500/07, " Loss of Electrical Power", p.2
. 000057G010 ..(KA's) 1
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l e-li ;5. EMERGENCY AND ABNORMAL PLANT EVOLUTIONS' Page 36:
(33%)
QUESTION 5.23c (1.00)
! .WHICH ONE~(1) of the following statements concerning containment sump isolation valves following SI is CORRECT? - (1.0)
(a.) the containment sump isolation valves will automatically open on low level' alarm from the FWST.
(b.) unless. bypassed, the containment sump isolation valves will NOT open unless the ND pump suction valves (from FWST) are closed.
(c.) the containment sump' isolation valves will NOT open unless the containment sump reaches the interlock level.
'(d.) the containment l sump isolation valves will automatically open IF the N0 pump suction valves (from FWST) are opened.
ANSWER -5.23 (1.00)
(a.) [+1. 0] '.
REFERENCE
- 1. MNS: Nuclear Systems Description ND.MC-1223.12, p.15; MC-1562-3.1; and MC-1561-1.0.
- 2. MNS: OP-MC-PS-ND Obj. 5 & 7, P. 18.
000074A111 ..(KA's)
(***** END OF CATEGORY 5*****)
my .;y.
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-.fyffll4 V',
2 y' ,
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e+ L6.t' PLANT SYSTEMSJ(30%) AND PLANT-WIDE GENERIC-Page37l' p#L',
S
. RESPONSIBILITIES-(13%).
fbl ug , R g
[ , , .
. .c , ,
.f , ' , -: ;.
i
< a .
, f, '
r M[QUESTIONlL6.01.'(1.00)?
O@ - .
- STATE.F00R'(4) signals.that will automatically ~ initiate feedwaterf
~
-isolation (setpointsnotrequired). .'(110),
'b l.:*
f.i , s N. .. ... ._
F 1
' ANSWER. 6.011. (1100)-. '
L1. ' ; Hi Hi dog house' level Safety Injections .- -
~ 2.1-3.- HiLHi S/& level G6/N:
, 4.- .
. Rx tripj with lo Tavgj
[+0.25].e'ach n
J
REFERENCE:
1 '. ' . McG0 ire:i OP-MC-CF-CF, " Main feedwater," Objective' 9.
059dOOA412 '..(KA's)/
. +-' 2
+ ; QUESTION. ~ 6.02 -(1.00)
W 3
STATE.TWO1(2)1 reasons-(purposes)fthatsodiumtetraborate"is'added' "
- to the ice inithe: Ice Condenser System. .- (1.0) -
f gW:
4 w ".
-ANSWER. 6.02: (1.00) e M
(
- 1.- ' Results in a neutron absorbing medium 4 +0.5]
- 3. , .
.2. . Increases the retention of iodine or increases.the PH g
. (following an accident). [+0.5]
\ t
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1 ,
- _1,. ----,---a--.- -,------_-asu-_. ----u- ma_w--u_n_.-- .s- -s--a--.-n.---,------ --.. - -----a-.._n __ - - - - - - - -a - - - - - - - - - . _
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'6.-' PLANT? SYSTEMS ~(30%):-AND PLANT-WIDE GENERIC 4- RESPONSIBILITIES-(13%)
n .-
L' 6 '. , : REFERENCE-7 ;1. f cGuire:
M 'OP-MC-CNT-NF,." Ice Condenser," Objective 1.A.
p 025000G004 ..(KA's)
- QUESTION
~6.03' (1.50)'
'r WHAT areL FIVE (5) conditions' that should exist before opening
NV-92A (NC Pump Seal Bypass. Return Header Isolation)'l (1.5)
ANSWERL -6.03 .(1.50):
' 1.
No.11 Seal Leakoff- temp.. exceeds approx. '200.deg. F.( Led
' b .: 7 %/)f
.2. NCS' pressure > 100 psig but < 1000 psig.
- 3. No. 1 Seal leakoff: valve open.
- 4. No. 1 Seal. leakoff is=less-than 1 gpm.
- 5. . Seal injection flow to each NC pump is'> 6 gpm.
[+0.3] each REFERENCE.
1.- McGuire: 'OP-MC-PS-NV, p.8,' LPSD #9.
004000K104 ..(KA's) i
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L L6. = PLANT ' SYSTEMS J30%) AND PLANT-WIDE GENERIC' Page 39 b RESPONSIBILITIES-(13%)
1
-QUESTION '6'. 04 ' (3.00)
~The plant is operating at 100% power with-all control systems in l
L automatic.- Feedwater flow channel fer "A" steam generator fails -
high.,-ASSUME no operator. action taken.
1
- a. EXPLAIN HOW each of the.following is INITIALLY affected and WHY that affect occurs..
- 1. feed flow- (0;75).
1_
- 2. S/G 1evel' (0.75)
-3. steam flow- (0.75)
_b. -The reactor subsequently ~ trips. STATE the most probable cause. Specify setpoints and coincidences. (0.75)
I ANSWERL 6.04 (3.00) a.- 1. actual feed flow decreases [+0.25] due to main feedwater regulating valve closing in response to the false high
~ feed flow signal [+0.5]
- 2. steam generator level decreases [+0.25] due to decreased feed flow [+0.5]
r
- 3. no change [+0.25] due to steam demand at 100% power
[+0.5] (up until trip).
to .
- b. on S/G lo/Gevel 40% [+0.5] setpoint 2/4 in 1/4 S/G 1evel
[+0.25]
REFERENCE
- 1. McGuire: OP-MC-CF-IFE, "S/G Level Control System." Obj. 8,10 & 12 i
035010A202 059000K104 ..(KA's) 1
)
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Page 40 "6. PLANT-SYSTEMSi(30%) AND' PLANT-WIDE GENERIC RESPONSIBILITIES-(13%)
1, e
-QUESTION 6.05 -(2.00) x a.. WHAT'are THREE (3) mechanisms employed.in the NV system to-reduce the reactor coolant system' activity prior to cooldown? (0.75) i b.- WHAT are the Technical Specification ' limits .for ' primary NC activity: levels? (0.5).
c.x WHAT'is.the basis for the primary NC activity limits? (0.75)
-ANSWER 6.05 ~ (2.00)
- a. 1. degasification (purge)
- 2. filtration
- 3. demineralization
[+0.25] each
- b. 1. <1.0 pCi/gm dose equivalent I-131 [+0.25]
- 2. <100/E uti/gm [+0.25]
-c. the limit on RCS activity ensures- (2-hour) doses at site boundary does not exceed 10CFR100 [+0.25] limits,
'following-a steam generator tube rupture accident with steady state piimary to secondary leak of 1.0 gpm [+0.5]
REFERENCE
- 1. McGuire: OP-MC-PS-NV, "CVCS," Objective 1 and 9.
- 2. McGuire: Technical Specifications, 3.4.8 and Bases.
004000A101 004010K618 004000G004 ..(KA's)
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~
! 6'. PLANT SYSTEMS-(30%)-AND PLANT-WIDE GENERIC-L .-
-RESPONSIBILITIES (13%)
I
(1.00)..
QUESTION. 6.06 r-WHICH ONE (1) of the following describes the Automatic Fast Transfer feature associated with the 6.9KV bus _ supply breakers 7 (1.0)
Mode select switches in auto,' buses in. sync...
(a.), NC Pump in operation on bus being transferred to, normal breaker trips, alternate breaker closes.-
NC Pump in operation on bus power is-transferred from,.
(b.) alternate breaker closes, normal breaker trips.
, -(c.)' NC pumps in operation-on both busses, normal breaker trips, alternate' breaker closes.
' (d.)' NC Pumps in operation on both busses, alternate breaker closes, normal-breaker opens.
~ ANSWER 6.06 (1.00)
- (c.)- [+1.0]
REFERENCE
- 1. . .0P-MC-EL-EP, " Main Power Distribution," Objective 21.
062000K403 ..(KA's)
QUESTION 6.07 (1.50)
WHAT do EACH of. the following reactor trips protect against7
- a. over-power delta-T (0.5)
- b. over-temperature delta-T (0.5) b c. pressurizer hign pressure (0.5)
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.L Page.42 6.'-PLANT' SYSTEMS-(30%)-AND' PLANT-WIDE GENERIC'
. RESP 0riSIBILITIES (13%)
e
.l'
~ ANSWER- 6.07 (1.50);
l(over power delta-T) protects against excessive fuel centerline-
~
- a.
-temp (kw/ft). [+0.5]-
b.- (over; temperature delta-T) protects against DNB [+0.5) c .- ' Prevents RCS over pressurization .(which ensures system piping integrity). -[+0.5]
' REFERENCE
-1. McGuire: OP-MC-IC-IPE, " Reactor Protection l System," Objective
- 1. F.-
012000K402 ..(KA's)
. QUESTION 6.08' '(1.50) .
In accordance with AP/1/A/5500/10, NC System Leakage Within Capacity of Both IN Pumps,"'(Case I, Steam Generator Tube Leakage):
- a. STATE WHICH radiation me titors would indicate a primary to secondary leak. (0.75)
- b. Primary to secondary s sakage has been detennined to be as follows:
SG A - 4 gph SG B - O gph SG C - 22 gph' !
SG D - O gph WHAT Technical Specification limit (s) is/are being exceeded? (0.75) 1
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- L6. PLANT SYSTEMS- (30%) AND PLANT-WIDE GENERIC t
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i ' ANSWER. .'6.08 '(1.50)
K a. .1. "1 EMF-33'Cond AE Exh Hi Gas Rad" alarm lt i 2..
1-EMF-34, SG sample Hi Rad" alarm L 3. "1 EMF-24,.25, 26,.27 steamline Hi Rad"' alarm ' ;
. [+0.25] : each
- b. (SG total leakage is-528 gpd which is'in excess of the)
Technical' Specifications 500 gpd total leakage. limit [+0.75)
REFERENCE
- 1. McGuire: Technical Specifications, 3.4.6.2 and Bases.
2.- -McGuire: AP/1/A/5500/10, "NC System Leakage Within Capacity of NV. Pumps"..
035010A408 035000G011 ..(KA's).
' QUESTION l 6.09 (1.00)
In accordance with OP/1/A/6450/15 " Containment. Purge System,"
Limits and Precautions, STATE.the reason that it is important to ensure that the purge mode selector switch is returned to the " Normal" position after. refueling. (1.0)
- ANSWER 6.09 (1.00)
To prevent overpressurization [+0.5] of the upper containment [+0.5].
, . REFERENCE 1.. MNS: OP/1/A/6450/15, " Containment Purge System."
I
- 2. 'MNS: OP-MC-CNT-VP, Objective 7.
029000A203 029000A103 ..(KA's)
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- 6. PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC -Page'44 m RESPONSIBILITIES (13%)
7 QUESTION '6.10 (1.00)
WHICH ONE (1) of-the following describes the plant response to a l pressurizer level channel failure? ASSUME Level.I control channel failed LOW, the system is in automatic, no operator action is taken, and the reactor is at 100% power. (1.0)
(a.) Charging flow decreases, actual level decreases, letdown isolates, and.the. level stabilizes at setpoint.
(b.) Charging flow remains the same, letdown flow temperatures increase,. backup heaters turn on if actual level increases greater than 5% above program.
(c.) Charging flow increases, actual level increases, letdown isolates, and the reactor trips on high pressurizer level.
(d.) Letdown isolates, heaters turn off, pressurizer pressure decreases, and the reactor eventually trips on low .
pressurizer' pressure.
ANSWER 6.10 (1.00)
(c.) [+1.0]
REFERENCE
- 1. McGuire: OP-MC-PS-ILE, " Pressurizer Level Control,"
Objective E.
011000A211 ..(KA's)
~
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'6. PLANT SYSTEMS'(30%) AND PLANT-WIDE GENERIC Page 45 RESPONSIBILITIES (13%)
QUESTION 6.11 (1.00)
The Diesel Generator, during an automatic start, must be capable of accepting the loads assigned by the sequencer while maintaining which of the following: (1.0)
(a.) 75% Voltage and 75'; frequency (b.) '75% Voltage and 95% frequency (c.) 95% Voltage and 75% frequency (d.) 95% voltage and 95% frequency ANSWER 6.11 (1.00)
(b.) [+1.0]
REFERENCE
- 1. McGuire: OP-MC-DG-DG, " Diesel Generator," Objective 3 064000A103 ..(KA's)
QUESTION 6.12 (1.00)
In the Diesel Generator " Limits and Precautions" section, it states, "The Diesel Generator must not be idled or its speed reduced for extended periods of time under any conditions of operations."
WHAT is the concern for operating the diesel generator at reduced speeds? (1.0) <
l ANSWER 6.12 (1.00)
(Operations at s Regulator [+0.5]peeds lower than and the Generator Field normal can)
(windings) damage
[+0.5] (due to the Exciter excessivefieldcurrent).
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- 6. PL' ANT SYSTEMS (30%) AND PLANT-WIDE GENERIC Rf.SPONSIBILITIES (13%)
REFERENCE
'). McGuire: OP-MC-DG-DG, " Diesel Generator," Objective 8, p. 11.
064000A206 ..(KA's)
QUESTION 6.13 (1.00)
Technical Specifications 3.9.10, " Water Level-Storage Pool," states that "at least 23 feet of water shall be maintained over the top of irradiated fuel assemblies seated in the storage rack." WHAT is the basis for this limit? (1.0)
ANSWER 6.13 (1.00)
Ensures that sufficient water depth is available to remove 99%
of the' assumed 10% iodine gap activity [+0.5] released from the rupture of an irradiated fuel assembly [+0.5].
REFERENCE
- 1. McGuire: Technical Specifications 3.9.10 and Bases.
- 2. McGuire: OP-MC-FA-KF, " Spent Fuel Pool Cooling," Objective 8.
033000G006 ..(KA's)
QUESTION 6.14 (1.50)
WHAT are THREE (3) purposes for the VCT outlet isolation valves (NV 141,142)? (1.5) l i
d
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- 6. PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC Page 47 RESPONSIBILITIES (13%)
ANSWER 6.14 (1.50) fJtJO
- 1. Ensure isolation between safety and not-safety systems during an emergency.
- 2. Prevent the injection of li NV pumps suctions. ( pg)%ydrogen into the safety related
- 3. Prevent the loss of FWST water via the non-safety portion of the NV system in the event of a pipe rupture. !
- 4. Prevents the dilution of NC system with VCT water during an accident.
Any three (3) [+0.5] each; max. [+1.5]
REFERENCE
- 1. McGuire: OP-MC-PS-NV, Obj. 3 & 6.
006000K606 004000G007 ..(KA's) l QUESTION 6.15 (1.00)
While at 100% power, first stage turbine impulse pressure channel II fails low. ASSUME Tavg-Tref deviation is 8 deg F. HOW will this affect the steam dump system AND WHY? (1.0)
ANSWER 6.15 (1.00)
C-7 (loss of load interlock) will actuate to permit steam dumpa[+0.5] due Tavg-Tref greater than 5 deg F [+0.5].
Uk I falafQ eps)
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.f 3 ia PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC Page 48
=6.
RESPONSIBILITIES (13%)
REFERENCE
- 1. McGuire: OP-MC-STH-IDE, " Steam Dump Control System,"
Objective F.
041000G007 ..(KA's)
QUESTION 6.16 (1.00)
STATE FOUR (4) automatic actions / alignment changes that take place in the KC system during an SI. (1.0)
ANSWER 6.16 (1.00)
- 1. all KC pumps start
- 2. auxiliary building non-essential headers isolate
- 3. isolation valves to ND HX open
- 4. ND HX control valves (faillopen S. NCDT and excess letdown isolated Any four (4) [+0.2S] each REFERENCE
- 1. MNS: OP-MC-SPS-SY-KC, Obj. 4, p. 17.
..(KA's) 4 008000A401 008000K401 QUESTION 6.17 (1.00)
STATE FOUR (4) inputs that would cause an automatic runback of the turbine generator. INCLUDE setpoints. (1.0)
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- 6. PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC RESPONSIBILITIES (13%)
ANSWER 6.17 (1.00)
- 1. OP delta-T > setpoint - 3% (reactor trip) 2.
3.
OT delta _T > setpoint -lL(reacior_1 rip)
Loss of one busline W 56% Impulse Pressure V, ,y , L A )
- 4. Loss of one FWPT> 56% Impulse Pressure
- 5. Low KG pressure (< 21 PSID> 5 sec)>10% Impulse Pressure.
Any four (4), [+0.15] for inputs; [+0.1] for setpoints; max [+1.0]
REFERENCE
- 1. McGuire: OP-MC-GEN-EHC, "DEH Turbine Control," Objective 5.
045000K412 ..(KA's)
QUESTION 6.18 (1.00)
Containment spray (NS) failed to automatically actuate during a i steam line break inside containment.
- a. WHAT conditions are necessary for automatic initiation of the NS system to occur? INCLUDE setpoints and coincidences. (0.75)
- b. WHAT pressure is the NS system designed to maintain after all of the ice in the ice condenser has melted? (0.25)
ANSWER 6.18. (1.00)
- a. Hi Hi 2/4 Containment logic: [+0.25] andPressure (Sp psig CPCS > 0.35 signal) 3 psig [+]0.25]
[+0.25
- b. < 15 psigg[+0.25]
O'I. bps:Q REFERENCE
- 1. MNS: OP-M7-ECC-NS, Objectives 1 and 3.
026000A101 026000A301 025000G004 ..(KA's)
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- 6. PLANT SYSTEMS -(30%) AND PLANT-WIDE GENERIC Page 50 RESPONSIBILITIES (13%)
3 L.
QUESTION 6.19 -(2.00)
Technical Specification 3.1.1.4 states that the minimum temperature
'for criticality.be greater than or equal to 551 deg F. . STATE the FOUR_(4) Technical Specification bases:for this temperature limit. (2.0)-
ANSWER- 6.19 (2.00)
.This limitation is required to ensure:
-1. the moderator temperature coefficient is within it analyzedtemperaturerange,[+0.5]
2.- the trip instrumentation is within its normal operating range,
[+0'5]-
- 3. the pressurizer is capable of being in an OPERABLE status with a steam bubble [+0.5], and
- 4. the reactor vessel is above its minimum RT NOT temperature [+0.5]
REFERENCE
- 1. McGuire: Technical Specifications 3.1.1.4 and Bases.
002000A103 002000G006 ..(KA's)
Q
_UESTION 6.20 (1.00)
WHICH ONE (1) of the following is the correct response of the VUL system if containment pressure increases to 0.5 psig? (1.0)
(a.) VU AHUs and RA Fans go to max. cool (b.) VL AHUs shift to hi speed (c.) VL AHUs RV flow goes to max.
(d.) PZR booster fans alternate fan auto starts
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' ANSWER- 6.20 .(1.00)L
. (b.) [+1.0]
o - REFERENCE
- 1. McGuire: OP-MC-CNT-VUL, Obj. 3' 022000K402- ..(KA's),
i 4
- QUESTION L6.21- (1.00)!
L MATCH the'. following rod bank and' mode of operation in Column.B with
, Lthe. rod. speeds in Column A.- (1.0)-
- COLUMN-A COLUMN B
- a. 8 1.. Max. speed for auto control of control banks.
. b;. ' 48'
- 2. . Manual operation of shutdown Lc. 64 banks.
- d. -72 3. Max speed for. auto withdrawl of'
, shutdown banks.
- 4. l Manual operation of control banks.
- 5. Minimum speed for auto rod movement of control banks.
ANSWER 6.21 (1.00)
- a. 5
- b. .4-
- c. 2 d.. 1
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PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC ,
- RESPONSIBILITIES-(13%)
iREFERENCE ,
I'. ;McGuire: OP-MC-IC-IRE, objective 13-121 /McGuire: OP-MC-IC-IRX, objective 3.1-001010K404' ...(KA's)-
}
4 QUESTION. 6.22 [(1.00)'
' WHAT are the .TWO (2) reasons for having NCP safety' breakers? '. (1.0) _
i, " ANSWER 6.22 :(1.00)'
1.: .To provide redundant. fault and overload protection for a feeder entering containment. [+0.5]-
- 12. ? To provide a. disconnecting device for each NCP. [+0.5]
' REFERENCE.
- 1. ' .McGuire:'OP-MC-EL-EP,Obj.'20,p.'20-
- 062000G007 .003000G007 ..(KA's) 1 l'
i l
11 l
1' 1
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- 6. PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC Pa0e 53- .
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1 Ir QUESTION 6.23 (1.00)'
Technical Specifications allows operations for a 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> period with-a Quadrant Power Tilt Ratio (QPTR) greater than'1.02. WHICHONE(I) of the following is the basis for allowing operation for this 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> time period? (1.0)
To allow time for corrective action in the event of Xenon
~
(a.)
redistribution following power changes.
j- -(b.) 'To allow time for correction of a dropped or misaligned control rod.
l (c.) To allow time for boron concentration changes to restore QPTR to less than 1.02.
(d.) To allow time for correction of NC flow imbalances.
ANSWER 6.23 (1.00)
'(b.) [+1.0]
' REFERENCE
- 1. McGuire: OP-MC-CTH-CP, Obj. 30 & 38.
001050A202 ..(KA's)
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-RESPONSIBILITIES (13%)
QUESTION. 6.24 (1.00)
WHICH ONE (1) of the following statements is the most correct' regarding the #1 seal bypass. valve? - (1.0) .
(a.) Should be opened when the pump radial bearing temperature exceeds 120 degrees.
(b.) Is used to supply adequate flow to #2 and #3 seals when
- 1 seal flow is inadequate.
(c.) Is opened when #1 seal leakoff is less than 0.2 gpm'and' its delta-p is less than 200 psid.
(d.) Can be used to provide additional cooling to the pump radial bearing below 1000 psig.
ANSWER 6.24 (1.00)
(d.) [+1.0]
REFERENCE
- 1. McGuire: OP-MC-PS-NCP, Obj. 10 003000K602 003000K404 ..(KA's)
'r
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f 62 PLANT SYSTEMS (30%) AND' PLANT. WIDE GENERIC RESPONSIBILITIES (13%)-
QUESTION - 6.25 (0.75)
MATCH the-following' tag colors with an example of their correct usage.
NOTE:~a number may or.may not be used more than once.. L(0.75)
Column I. Column II
.a.. Red Tag 1. used for material protection
- b. White Tag 2. used to identify.a ladder with loose or cracked rungs-
- c. . Yellow Tag. .
..3. used to block the closing of a breaker following a tripout
- 4. used to-indicate a flammable liquid container
- 5. used to indicate a component that could cause personnel injury
- 6. used'to physically lockout the source of power at the main disconnect switch prior.
to commencing work l
l ANSWER 6.25 (0.75) l
- a. 5 ' +0.25'-
- b. 1 '+0.25'l'
- c. 3 l+0.25.i REFERENCE
- 1. McGuice: SD 3.1.19, p. 3-4.
194001K102 ..(KA's) 7
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, 3 O '.T,;
K' >1 .QUESTIONE 16.26'.,(1.00)-
> -In regards.:to. Station Directive 3.1.19,. " Safety Tags," WHAT is the purpose of a' BLOCK TAG 0l!T7- . (1.0) ..
I L
T f. -[
- ?
? ANSWER: 6'.26 x .. (1.00). "
~
UJ u: Block portion' Ta of the goutplant ,is!the [+0.25 isol'ation andof, for;the purpose taggirig allowing[+0;25] work by of a definedL various work groups [+0.25)).to be< accomplished concurrently within-1: ithe boundary of the ' block tagout [+0.25].
m
.. Credit.will;be given for similar wording.
' ' s REFERENCE- ,
'1. . McGuire: - S.D. 3.1.19, " Safety Tags," p. 4. . .
x.
194001KIO2 ..(KA's) 5 QUESTION' 6.27 (1.50).
'The Planned Emergency Exposure limits if necessary to save. lives or. '
p(revent=1oss INCLUDE value and of units.) life and/or extensive damage to property are:
- a. whole body . (0.5) -
b '. - skin (0,5)
' c. : extremities (0.5)
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RESPONSIBILITIES (13%)
ANSWER 1 L6.27. (l'.50) ~
, :a. f 25__ Rem ! ' [+0.5] >
- b. - 150 Rem [+0.5]
s
- c. 2375 Rem [+0.5] : , .
Ed.52 f Qi po42 f A = &oS i '*"k-y .
REFERENCE. '
4
^
L1. .:
McGuire:!:OP-MC-RAD-HPM,LObjective.11.
.194001K103. .l(KA's)
QUESTION. 6.28 -(1.50)
Station Directive'3.1.8 " Access to Containment" requires the m~ ..
completion ~of DPC form f35414, " Upper / Lower Containment Authorization,"Lprior to enterina the Radiation Control area.
- An approval shall-be granted depending on the current operating mode of the-; unit.
- a. .For' Modes 1,2,3,4 (NC' temperature'200 deg F or greater)
- WHOSE _ approval is required and WHO will verify this approval? (1.0) b . .. For Modes d,6_(NC t'emperature less than 200 deg F) WHOSE approval is required? (0.5)
ANSWER '6.28 (1.50) a.: . approval by Shift engineer [+0.5]
verification Nn person'or via phone)-by Security [+0.5]
b .= Health Physics (Supervision) [+0.5]
o i
J i
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- 6. PLANT' SYSTEMS-(30%)'AND PLANT-WIDE GENERIC RESPONSIBILITIES (13%)
REFERENCE--
1; McGuire: S.D.i3.1.8, " Access to Containment," p.' 2.-
194001K105 ..(KA's)
QUESTION 6.29 (1.50),
b Per Technical Specifications 3.4.7.10 and 3.4.7.11, dealing with
" Fire Protection,"-STATE THREE. (3) circumst6 rices that registre
-establishment of a continuous fire watch. (l'.5)
-- ANSWERL 6.29' (1.50)=
/s m
- 1. - when the sprinkler 4 system for a zone is inoperable.
when the Halon system for. a zone is inoperable.(W% #*f%"
)
2..
- 3. when one or more required fire penetrations are inoperable.
h k ~ '
[+0.5] . each REFERENCE 1.- McGuire: McGuire Technical-Specifications, 3.7.10.2, 3.7.10.3, 3.7.11.
194001K116. ..(KA's) t 1
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-Page 59 6 .- PLANT SYSTEMS (30%) AND PLANT-WIDE' GENERIC RESPONSIBILITIES (13%)
QUESTION .6.30 (2.00)
ANSWER the following questions regarding fire brigade staffing.
- a. For the fire brigade, HOW MANY members must be maintained onsite at all times? (0.5) .
- b. In order to accommodate an unexpected absence, the fire brigade composition may be less than the minimum requirements for a period of time. WHAT is that time limit? (0.5)
- c. Per Technical--Specification 6.2.2, WHICH members may not be used to satisfy the fire brigade manning requirements? ' (1.0)
ANSWER 6.30 (2.00)
- a. at least 5 [+0.5]
- b. -(not to exceed) 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> [+0.5]
- c. the fire brigade shall not include the three (3) members of the minimum shift crew necessary for the safe shutdown of the unit [+0.5] or any personnel required for other
~
essential functions [during a rite emergency [+0.5]
VLS*% 5 NOTE:. Credit given if titles given
+7' w )
REFERENCE-
- 1. McGuire: Technical Specifications 6.2.2.
- 2. McGuire: OMP, 1-7 section 6.1, I and J.
194001K116 ..(KA's)
QUESTION 6.31 (1.00)
WHEN may a non-licensed person manipulate the controls which may affect the reactivity or power level of the reactor? (1.0) f L
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ANSWER- 6.31 -(1.00)-
i When under the direction and in the presei.de of a licensed. operator or licensed senior. operator [+0.5] as a f his training to
- qualify for an' operator ifcense'[+0.5] (part o under.10CFR55).
g,l REFERENCE.
11.:: McGuire: S.D. 3.'1.4,'" Conduct of Operations," Sec 1.3..
194001A103' ..'(KA's) l QUESTION- '6.32 (1.00)-
n
.WHAT is a. Restricted change to a procedure? - (1.0)
~ ANSWER- 6.32 (1.00) f(An-approved major) change to a procedure [+0.5] which is valid only for.a specified period of time or duration of.an event [+0.5].
' REFERENCE
- 1. McGuire: S.D. 4.2.1, " Handling of Station Procedures."
u 194001?.103 ..(KA's)
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'6'. PLANT SYSTEMS-(30%) AND PLANT-WIDE GENERIC-RESPONSIBILITIES-(13%)-
n QUESTION 6.33 (1.50)
Per 0-M-P-1-7, " Shift Manning and Overtime Requirements", FILL in the blanks concerning overtime. An individual shall not work more than (1)- hours straight-(excluding shift turnover time).
An individual shall not work more than (2) hours in any
- 24. hour period,' nor more than (3) in any 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period,-nor more.than (4) hours in an turnover time). A break of at'yleast 7 day (5)-periodhours (all excluding shift shall be between work periods (including shift turnover time). (1.5)
ANSWER 6.33 (1.50) 16 16 28
-72 8
[+0.3] for each part.
REFERENCE
- 1. McGuire: 0-M-P 1-7, Sec 6.2 B 194001A109 ..(KA's)
QUESTION 6.34 (1.25)
- b. Per Station Directive 3.8.2 " Station Emergency Organization,"
l STATE by title the personnel that, as a minimum, must staff the OSC. (0.75) l l
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- 6. PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC Page 62 RESPONSIBILITIES (13%)
I ANSWER 6.34 (1.25) .
- a. Alert-[+0.5]
- b. 1. [+0.25]
- 2. OSC coordinator (operating]
Plant Operations engineer)
[+0.25 (or 6 h s_m<y- h s) '
- 3. Health Physics [+0.25]
ton MS, % prnE M .
REFERENCE
'1. McGuire: Emergency Plant Notification of Unusual Event, Sec. 3.3.
- 2. McGuire: S.D. 3.8.2 ' Station Emergency Organization," p.-15.
194001A116 ..(KA's)
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