ML20153B659
| ML20153B659 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 08/25/1988 |
| From: | Jordan M, Mark King, Parrish M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20153B625 | List: |
| References | |
| 50-254-OL-88-01, 50-254-OL-88-1, NUDOCS 8808310040 | |
| Download: ML20153B659 (129) | |
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. U.S. NUCLEAR REGULATORY COMMISSION
! REGION III i l
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) Report No. 50-254/0L-88-01 '
Docket Nos. 50-254; 50-265 Licenses Nc. DPR-29, 1-30 ,
1 Licensee: Commonwealth Edison i
Post Office Box 767 1 j Chicago, IL 60690 :
Facility Name: Quad Cities Nuclear Power Station I
i Examination Administered At: Quad Cities Nuclear Power Station ;
i Examination Conducted: July'19-22, 1988 .
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) Examiners: M. King ..
I ategg
) M. Parrish -@
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1 Date 5/,rYg
! Approved By: M. J. Jordan, Chief f.. A f Operator Licensing Section 1 t'e' j /gf j l '
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Examination Surary l
i Examination administered on July 19-22, 1988 (Report No. 50 254/0L 88 01)
Written ar.d oral examinations were administered to two Reartor Operetor and !
six Senior Reactor Operator candidates. I Results: All candidates passed the written examinatione. One Reactor Operator !
and five Senior Reactor Operators passed the oral examinat'.ons. l l
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8008310040 890825 PDR ADOCK 05000254 j
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, REPORT DETAILS
- 1. Examiners M. King, INEL Examiner M. Parrish, INEL Examiner S. Stasek, NRC Observer M. Jordan, NRC Observer
- 2. ExitMeeting An exit meeting was conducted on July 22, 1988, with the following persons in attendance:
Quad Cities Nuclear Power Station R. Bax, Station Manager N. Digrindakis, Regulatory Assurance Engineer J. Wellington, Quality Assurance Superintendent R. Robey, Services Superintendent "
l T. Snares, General Instructor - SRO M. Rodts Training US NRC l
M. Jordan, Chief, Oparator Licensing Section IB '
M. King, Examiner (INE'.)
- 5. Stasek, Examiner The following items were discussed during the exit meeting
A. Concerns with Procedures and Use of Procedures l (1) QGP 1-3, 4.r.(2) states, "PLACE reactor recirculation control I into MASTER-MANUAL in accordance with QOP 202-3."
QGP 2-1, 0.2.e. states, "Continue to reduce recirculation flow !
j until the Master controller reaches minimum speed (45*4), then place the etcirculation flow controllers in tha LOCAL-MANUAL mode in accordance with 00P 202-3." j Quad Cities normally operates with the Recirculation flow control in LOCAL-MANUAL rather than KASTER-MANUAL; therefore, ,
the procedures should contain a caveat that identifies this mode of power operation.
(2) OAP 300-4, "Shift Change for Shift Engineers," C.5.e. states, "Review temporary alteration log and outstanding RWP's.
The pracedure should be revised because outstanding RWP's no longer exist.
, (3) Another example of the problem with use of procedures occurred when using QAP-16, which states that "a reason for placement or -
removal" will be stated in the "S" padlock log book. The log book did not have a space for reason during initial walkthroughs.
When the candidate questioned the shie't forecan as to why the form did not allow for recording the reason, the shift foreman [
stated that recording the reason was not necessary. The log '
book, however, was revised prior to the walkthrough the next day.
B. Concerns with Operator Training i l (1) Following event classification and initial notification on the !
, Integrated Plant Operation portion of the walkth.'oughs, L j operators failed to make second notifications when additional l
. failures or complications occurred, s
] (2) During occurrence of events, operators were reluctant to call for outside assistance.
1 i (3) Operators were weak in locating an( using eier.trical P& ids- :
available on Micro Fiche. l 1 ,
(4) When discussing placing pumps out of service, the correct
} actions were taken by isolating the pumps. However, no actions i 1
- were taken to protect the pumps, such as placing control ,
switch in Pull-to-Lock or opening and tagging out breakers. [
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, 3. Examination Review f
An informal exam review was conducted with the Examiners and Quad Cities :
I Training Staff. The facility comments and NRC resolutions are attached.
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- Writter Examination Comments and Resolutions Reactor Operator and Senior Reactor Operator Examinations Administered July 19, 1988 Docket Nos. 50-254; 50-265 i
Comment: Questions 1.07 and 5.08 Pump noise should also be an acceptable answer.
Resolution: Comment accepted. This answer was not included in the exam because the reference cited by the facility was not provided to l the examiners preparing the written exam. This information,
) pump theory, is required to be provided per Attachment 1 to l
ES-201-1 of NUREG-1021. The answer key was changed based on additional information provided.
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Comment: Questions 1.14 and 5.15 l Answer " " should also be considered correct. As the reactor coolant heats up, increasing the thermal gradient across the reactor vessel walls. This means that the heat flux through the vessel walls is greater (greater losses to ambient),
requiring a high reactor power to maintain a constant heatup rate.
Resolution: Comment accepted. Answer key was modified to also accept "c" as a correct answer.
! Comment: Question 2.01 i
Valve numbers should not be required for full credit as long as !
adequate description is provided, t
Resolution: Comment accepted. Answer key was modified to accept valve I descriptions as correct answers.
I Comment: Question 2.02 b The 3906 valve may also be manually opened locally in the crib house.
Resolution: Comment accepted. Answer key was modified to accept "manual operation of 3906 in the crib house."
Comment: Questions 2.10 a and 6.04 s i
- 1. The question does not state why the h diesel generator did !
not start. This could be construed as the \ diesel (
generator being inoperable. l Therefore, auto start signals of !
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, +2.5 psig Drywell Pressure
-59" Reactor Water Level should be accepted.
- 2. Another auto start signal is the 14 to 14-1 feed breaker open.
l Resolution: Comment partially accepted.
- 1. If the candidate stated an assumption of the diesel being inoperable then these signals will be accepted. Answer key was not changed. '
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- 2. Answer key was modified to also accept "14 to 14-1 feed l breaker open" as an acceptable answer.
L Comment: Question 2.14 Bus 13 cannot feed bus 14-1 l Bus 14 cannot feed bus 13-1 All other answers in the key are correct.
Resolution: Comment accepted. Answer key was modified to delete "Bus 14 as a feed to bus 13-1" and "Bus 13 as a feed to bus 14-1."
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Comment: Question 3.02 part 3 !
Control room ventilation "on recirc" or "on 100% recirc" is synonymous with control room ventilation isolation.
Resolution: Comment accepted. Answer key was modified to accept "on recirc" l or "on 100% recirc" in lieu of isolates.
l l Comment: Questions 3.03 and 6.03 If taken to a point beyond that described in the answer ke), '
the following arameters should also be an acceptable answer:
Throttle Press: 925 psig Rx Power: 50%
Control (governor) valves: 50% steam flow '
Bypass Valves: 0% steam flow These conditions are reached after the control (governor) and bypass valves open to pass S3% steam flow at 50% power. The reactor subsequently depressurizet until the valves close down i to control to a pressure setpoint of 910 psig, yielding the conditions above. '
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Resolution: Comment accepted. Answer key was modified to accept the following as the cc; rect answer and point values were
, redistributed accordingly:
Output from pressure summer A increases to 25 psi (.34). The HVG passes this signal to the Pressure / Flow converter (.34).
The Pressure / Flow converter output will increase to 82-83% ( .34).
The load limit will limit the signal to the governor valves to 65%(.33). Total flow is less than the maximum combined limiter
(.33) so the bypass valves will open to pass 17-18% flow (.33).
Reactor pressure decreases to control pressure with a pressure setpoint of 910 psig (.33). Bypass valves will close (.33) and control valves will maintain 50% flow due to the decrease in pressure (.33).
Comment: Question 3.07 b This answer should be NO. For two reasons:
First, IRM 12 failed upscale puts IRM 12 in the tripped <
condition (HI-HI). This does not disable the IRH 12/APRM2 companion scram.
Second, Tech Spec table 3.1-3 (p. 3.1/4.1-13) only requires two IRM/APRM (APRM downscale) trips be operable in the RUN mode.
This is satisfied by IRM 13/APRM3 and IRM 14/APRM3. ;
Resolution: Comment partially accepted. Answer key was modified to accept I NO as the correct answer. Comment concerning IRM 12 failed ,
, upscale placing it in the tripped condition was considered in '
the change to the answer key. However, without further facility interpretation of using IRM 13/APRM3 and IRM 14/APRM3 i as two operable channels for the downscale trip it cannot be '
I considered in grading of the examination.
! Comment: Questions 3.09 b and 6.01 b 4
The off gas pressuri:ed drain tank to pressurized drain pump isolation valve may also be referred to as the (50V) 5437 valve.
' F Resolution: Comment accepted. Answer key was modified ta accept 50V 5437 in lieu of the valva description as the correct answer.
Comment: Question 3.10 Main Steamline High Radiation Setpoint is 7 x NFPBG.
Resolution: Comment accepted. Answer key was modified to accept "7 x NFPBG"
- as the correct answer.
I 1 I Comment: Questions 3.12 e and 6.10 e i The Inboard Core Spray Injection Valve can also be referred to I as the "25" valve (1401-25). !
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, Resolution: Comment accepted. Answer key was modified to accept the valve ,
number in lieu of the valve name as the correct answer, i Comment: Questions 4.02 a and 7.11 a Scram timing should also be acceptable.
Resolution: Comment not accepted. Answer key was not changed because the facility's comments are not supported by the reference material.
Procedures cited do not indicate that continuous withdrawal is permissible.
P Comment: Questions 4.08 e and 7.13 e ,
Should also accept "RhM," since blocks are normally kept enabled .
above 20% power. ;
Resolution: Comment not accepted. The referenced procedura indicates that N/A should be used at greater than 20% power, ,
i Comment: Questions 4.09 b and 7.12 b The QGA lesson plan (rev.1) was in error concerning the peak ,
claddirg temperature of 1500 F. This number should be 2200 F.
Resolution: Comment accepted. The answer key was changed because the reference provided by the facility's comments is more accurate or disagrees with the reference material provided for use by the
, examiner in developing the written examination. The originally j referonced material should be corrected or destroyed.
l Comment:
Question 4.12 This question's last line could t.4 interpreted as asking for the actions required if both the 20A and 20B valves fail to the open position (i.e., fail to OPEN), thereby making those valves inocerable.
If this were the case, the LCO statement of 3.7.A.3.6. wotad be i
- exceeded. This would require placing the reactor into the HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, and in to COLD SHUTDOWN in the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless the situation is corrected per Tech Specs 3.0.A.
Resolution: Comment partially accepted. If the candidate assumes the vacuum breakers did operate as required (opened) when Suppression
, Chamber pressure decreased, the question could be interpreted to ask for actions required if the valves then failed open as 1
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suggested in the facility comment. The answer key was changed
- to also accept the following response
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, 1. Attempt to close and lock the vacuum breakers in the closed position.
- 2. Place reactor in Hot Shutdown in 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />; and Cold Shutdown -
in the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Comment: Question 4.16 a Should also accept "Group I Isolation" for credit in lieu of items:
- 2. MSIV's close
- 6. Main Steam Line drains close
- 7. Primary Sample valves close Resolution: Comment accepted. Answer key was modified to accept "Group I isolation" in lieu cf items 2, 6, and 7. .
Comment: Question 5.02 a This could also be defined as 1-keff. !
l Resolution: Comment not accepted. The equation does not fully define .
the term. !
r Comment: Question 5.03 '
Other indication' which should be acceptable include: i 1
A and B recirc loop (moderator) temperatures increasing. Period I indication going to infinity and/or negative IRM/SRM levels start to decraase. i Resolution: Comment partially accepted. Increasing Rectre loop temperatures I could be caused by other causes besides being above the POAH, i
i.e., heat due to recirc pumps, therefore this answer will not be accepted. Period indication going to infinity and/or negative ,
' IRM/SRM levels start to decrease will be accepted. Answer key !
was changed accordingly.
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i i i Comment: Question 5.09 I An answer of APLHGR/MAPLHGR limit should also be acceptable.
j Resolution: Comment accepted. Answer key was modified '.o also accept APLHGR/MAPLHGR limit as a correct answer.
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Comment: Question 5.10 a i
A statement concerning b eaking the recire oath by lowering the water level below the steam separators should also be acceptable. 1 1
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, Resolution: Comment not accepted. Answer key was not changed because the facility's comment contains misinterpretation of the reference material. The reference material is concerning operation in I shutdown cooling not at power. This reason is not cited in tha i facilities reference material concerning basis for E0P steps.
Comment: Question 6.09 a Should give full credit for "h diesel generator starts and runs unloaded."
j Resolution: Comment r.ot accepted.
Full credit was not allowed because it does not discuss the status of busses 13-1 and 23-1. ,
Com-ent: Question 6.11
- 1. Answer No. I should not be required for credit. By referring to the third reactor feed pump as the "Standby i Pump," it is inferred that the third reactor feed pump is already selectect to standby.
- 2. There is only one pressure switch for the low suction
, pressure trip. This would affect all three reactor feed pumps. Therefore, this answer should not be required for i credit.
, 3. If "low suction pressure" is required for full credit, another answer which should be acceptable is "reactor ;
water level greater than +48 inches." ;
- 4. Other acceptable answers should include
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' Running reactor feed pump was tripped with control switch.
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- Reactor feed pump discharge pressure greater than 1040 psig.
l i ' Standby reactor feed pump breaker tripped f i
- l 'Over current !
j 'Undervoitage on supply bus d
Resolution: 1. Comment not accepted. The training material uses the same
- rminology as the question. If the pump that was expected ,
i to be the standby pump failed to start then an appropriate l cause is that it is not seier,ted. j i
- 2. Comment accepted. Answer key was changed. "Low suction i pressure" is not accepted as a correct answer.
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- 3. Comment not accepted. Due to resolution it item 2, l "reactor water level greater than +48 inches" was not accepted as a correct answer.
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, 4. Comment partially accepted. Answer key was modified to accept ' Running reactor feed pump was tripped with control switch" as a correct answer.
Cannot accept "Reactor feed pump discharge pressure greater then 1040" because the reference provided was inconclusive.
Standby reactor feed pump breaker trips was not accepted.
Indications of a failure to stort are different than those for a pump which started the then tripped.
Comment. Question 7.09 c Should also accept "can cause flow induced vibration of the
,4 lower speed jet pump risers."
Resolution: Comment accepted. Answer key was mudified to also accept "can cause induced vibration of the lower speed jet remp risers."
f i Comment: Questions 4.09 b and 7.12 b '
The QGA lesson plan (rev.1) was in error concerning the peak cladding temperature of 1500 F. This number should be 2200 F.
Resolution: Comment accepted. The answer key was changed because the reference provided by the facility's comments is more accurate or disagrees with the reference materials provided for use by the examiner in developing the written examination. The
- originally referenced material should be corrected or destroyed.
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I Comment: Question 8.13 1 Tech Spec bases do not indicate elimination of core reflooding l capability as a reason taken into consideration of the DBA LOCA.
This should not be required for credit.
Resolution: Comment accepted. Answer key was modified not to require "eliminate the capability of reflooding the core." Total point value of question was changed from 1.00 to 0.50, i
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, Notes from Grading Examinations.
Two identical questions in the RO and SR0 examination, 2.10/6.06 and 4.09/7.12 were commented on in the SRO comments but were not referred to in the RO comments. The comments frot the SRO examination were applied to identical questions in the RO examination.
Changes Made During Grading Not Oue to Facility Comments. .
l Questions 1.07 and 5.08 Accepted inadequate core cooling as an answer that is the ultimate goal of maintaining NPSH to the pumps. .
i Questions 3.03 and 6.03
- Plant operating procedures regraire that load set be maintained at least 10?.
above setpoint. It was acceptable for the candidate to assume load set at 60%
- and answer accordingly.
J Question 6.12 l
Accepted "Low flow in the Primary Train" in lieu of "Failure of the Primary i l Train to start." Verified in the SBGT lesson plan.
Questions 4.09 b and 7.12 b "Adequate core cooling" was accepted in lieu of "maintain peak cladding
] temperature less than 2200 F" based on the definition of "Adequate core cooling." ;
Question 8.11 Tolerances were not required in answer because they are not stated in the
- referenced procedure, i
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% k U. S. NUCLEAR REGULATORY COMMISSION
- REAF.OR OPERATOR LICENSE EXAMINATION 6 e
- FACILITY: Dyad _Gltigs_1.6 'J
= REACTOR TYPE: @WS-QE2__________________
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. DATE ADMINSTERED: @@40ZL12_________________
EXAMINER: MGQHEE3_Qt____ __________
CANDIDATE _________________________
IUSIEUGI19US ID_GeUDIP61Et Use separate paper for the answers. Write answers on one stce orii v.
Staple question sheet on top of the answer *sh c o t s . Points for occh question are indicated in parentheses after t h t- question. The passing grade requires at least 70% in each category and a final grade of at least 80%. Examination papers will be ptered up can (c) hours after the examination startu.
% OF CATEGORY % OF CANDIDATE'S CATEGORY
__YaLUg_ _Igleb ___gGOEE___ _YBLUE__ ______________G01EQ9EY_____________
_26 t Qg__ _RQ.50 ___________ _ _ _ _ _ _ . _
- 1. FRINCIFLES OF NUCLEAR POWER PLANT OPERATION. THERMODYNAMICS, HEAT TRAN5FER AND FLUID FLOW
_2EtE9__ _2519# ___________ ________ 2. PLANT DESIGN INCLUDING SAFETY AND EMi- RGENCY SVSTEMS
_2Et99__ _SdtEZ _ _ _ _ _ _ _ _ _ _ _ ________ 3. INSTRUMENTS AND CONTROLS
?Et?E__ _EstO? ___________ _..______ 4 PROCEDURES - NORMAL. H ENORi i AL ,
EMEFGENCY AND RADIOLOGICAL CONTROL
_191t?[_ ___________ ________4 Totals Final Grade All work done on this examination is my own. I have neither oiven nor e+ceived aid.
Cancicate's Stqnature
Le. _ _ E B IN QlE L g 5,Q E _ b y Q L E @ E _ E Q W E 6_ E 60 $I _ Q E E S 611962 Pcgo .
- IdEEDORXUed1GSi_dEGI_I660SEEE_eNQ_E(Q1Q_E(QW s
OUESTION 1.01 (1.00)
Which ONE of the following defines a DELAYED neutron?
- a. A fast neutron that is born at a lower energy than a prompt neutron,
- b. A neutron born at the same kinetic energy level as the energy of the moderator atoms.
- c. A neutron with a higner r.cobability of being abucrbed by a boron atom than a thercial neutron.
- d. A neutron born within toe-14 seconds of a fission event.
l ANSWER 1.01 (1.00) a (1.03 REFERENCE Ouad Cities. LIC-lHEO Rev 2 TPO 3, P. 4 GGNS, OP-NP-10e/REV 0 LO 3.o. P. 14a
( 292001 v .102-3. 0 )
1 2920016: 102 . . (6:A n) l i
t+++++ CATEGORV 1 CONTINUED ON NEXT PAGE ****+)
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1,:. _ _ E B I NG 1EL E 5_ QE _ U UG L E 98_ E99 E 6_ t L OUI _ Q E E B BIl004 Poco ;
, l ISEEd99106d1G34 dE9I IE6N[Eg@,@UQ E(ylg,E(QW QUESTION 1.02 (1.00)
The total amount of reactivity that must be added to bring a reactor to a critical condition is anual to that
.A . Excess Reactivity <
- b. Shutdown Defect
- d. Subcritical Factor P
ANSWER 1.02 (1.00) c C1.0]
i REFERENCE
, Duad C1 tire. LIC-THED Rev 2 TP0 10, FP. 8 (292OO2Ni10-3.2) 292002K110 ..O A's)
- OUESTION 1.03 (1.50)
Regerding Manimum Cr1tical Power Ratio.
- a. STATE the fuel failure mechanism that is used to limit the MCPh t value. [
- b. (TRUE or FALSE) Operation with FLCFR greater than 1. 0 15.
acceptable.
- c. (TRUE cr FAL5E) For core flows other than rated, MCFR ;
I limit must bo DECREASED.
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(+++++ CATEGORY 1 CONTINUED ON NEAT FAGE +++++)
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,1s- EBINQlE(g5_QE_UWQbE@B_EQWEB_Eb@Ul_QE56@11QU4 Pcq3 4
- IUESdQDYU601G32 UEGI ISBUSEES 602 ELVID E609 s
ANSWER 1.03 (1.50)
- a. Fuel cladding cracking due to lack of cooling. [0.53
- b. False CC.51
- c. False [0.53 REFERENCE Ouad Cities Technical Spect+1cationc. P. 3.5/4.5-14.
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BWR Thermal Lamtts Figure 9-5. p. 9-30, 9-39 Learning Objectives 5.5, 5.12, 5. 11.
(293009K120 3.1/3.o) (273009K127 0.7/3.3) (293009K120 3.0/3.5) 293009K128 2930090.127 293009K120 ..(MA's) t OUESTION 1.04 (1.00)
SELECT t+ correct statement concerning the operation of a jet pump.
l a. The ditfuser increases the velocity of the fluid thereby I increasing att static head,
- b. The nor:lc on the Jot pump converts the static head of the
] recirculation pumps to a low velocity jet at high static pressure.
- c. The low pressurn at the no::le darcharge draws the surrounding l fluid into the jet pump throat area.
- d. The constant area 0+ the mixing section maintains the pressure constant. ,
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- 5 lt .EBINGIELE3-QE_UUGLESS E9bE8_ELGUI_9EESSI1994 Pc9e
. ,s ISESdQQ10051Gia_dE9I_IE005EES_000_ELVID_ELQW ANSWER 1.04 (1.00) c C1.03 REFERENCE Ouad Cities BWR Thermal Hydraulics p. O.34 Leatning Objective 8.2
( 2 0 2 0 0 1 F 5 0 0 3 . 1 ,' 3 . .~ > (293004L105 2.7/2.7) 09:004M105 202v01L*)02 .. aA*s)
OUESTION 1.05 (1.50)
MATCH the definition in Column 1 with the term in Column 2.
Column 1 Column 2
== ==
- a. Flow of heet through a body 1. Convection or between bodies in direct contact. 2. Radiaticn
- b. E,:chsnge of energy betwetn 3. Conduction bodisc through an intervening space by electromagnetic wavet.
- c. Transfer of heat between a fluid end a surface by circulation or mixing of the fluid.
(++v++ CATEGORY 1 CONTINUED ON NEXT PAGE +++++)
1t__E61dGIELES_QE_UWGLE66_E0 WEB _EL6UI_QEE66II9b2 Pcgo 6 ISE6dQD10ed1G34.UEGI_I660SEEB_6UD ELVID_EL9W i
ANSWER 1.05 (1.50)
I
- a. 3 Co.53
- b. 2 CO.53
- c. 1 CO.53 REFERENCE Ouad Cities: Heat Trancier p. 7-5 Learning Objectivo 1.1, 1.4 (293OO7t 101 3. '. / 3. 2 )
2%QO7h101 . . O A 's )
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l OUESTION 1.06 (2.50) l l
Answer the following outstions concerning Net Posi tive Suction Head (NP5H).
- a. LIST FOUR parameters which contribute to sVAILABLE NPSH for a recirculation pump. Limit your answer to those parameters which ere DIRECTLY indicated in the CONTROL ROOM.
- b. Consider TWO Reactor Plant conditions:
l Low Power and Low Flow M 10'4)
OR High Power and High Flow (>65'/.).
- 3. During which condition is the REOUIFED NFSH for a recirculation pumm greater" (0.5) 1 l 2. During which condition is AVAILABLE NPSH for a l
recirculation-pump greater and WHY is it greater' t1.0) 1 l l l
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l (***** CATEGORY 1 CONTINUED ON NEXT FAGE +++++)
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- Ig__E616CIELE9 QE_UWGLEGB.EQWES EL8UI_QEE60I1QU4- Pese 7 l s IbE5bQD166d1GE4_dE6I_IS6 SEELS _800_ELWID_ELQW l s - -
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ANSWER 1.06 (2.50) ,
1
- 3. RPV pressure
- 4. RPV water level [
C 4 G O.25 pts each 3 I l
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- b. 1. High flow, Hinh power CO.53 j
- 2. High flow. High power Co.503, due to the increased inlet i subcooling from the increased feedwater flow. CO.503 l REFERENCE l l
Quad Citiest LIC-0202-1 p. 24 Learning Objective 11. ,
(202001K103 3.2/3.3) (202001K105 3.4/3.4) (202001K119 3.2/3.2) l (202001K122 3.5/3.6) (702001K402 3.1/3.2) J
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200001M402 202001K122 202001K119 202001K105 20:001K103 l
..(KA's)
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QUESTION 1.07 (2.00) i i
OGA's require that the operators observe NFGH requirements for Core (
Spray and RHR pumps taking suction from the suppresston pool. LIST FOUR i effects that would result if cavstation occurred in these pumps. l i
ANSWER 1.07 (2.00)
Reduced system flow (0.5)
Reducat pump effictency (0.5) j Excess vibration (0.5) i Impeller damage (0.5) i a4= P No ss L '
T e.o d
- 4s C.o r e. t.se ( s' e,$
(+++++ CATEGORY 1 CONTINUED ON NEXT PAGE +++++) j q N oft- .E 80- .
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-_ _ _ ___ ___ _ _ _ _ ____- _ _-________-_ _ _ _______--___ __- _- _ _ -__ _ ___ _-__ -___-_-__ _ _ _ _ A
It__EB10GiELE5_QE_UWGLE66_E9WEO E6001.9EEBeI19di Pc90 0
. IbE609Q10601932 bEGI IS00SEE6_8UQ_ELW10_ELQW REFERENCE Ouad Cities: Emergency Operating Procedures (OGA's) p. 20.
(291004K101-3.2) 291004K101 ..(KA's)
OUESTION 1.08 (1.50) l l a. WHAT is the relatt enship between MAFRAT and MAPLHGR? [1.03 l
( b. If the MAFLHGR Technical Specification limit is exceeded then fuel failure may occur during what event? Co.53 l
l ANSWER 1.08 (1.50) 1 1
l l e. MAFRAT is the ratto of APLHGR TO APLHGR Limit OR I tne ratic of MAFLHGR(act) to APLHGR(LCO) l (Either answer acceptable for full credit.) [1.OJ l
l b. A DBA LOCA CO.53 l REFERENCE Ouad Cities EWR Thermal Limits figure 9-5. p. 9.24 Learning Objective 4.3.
(293009K112 2.9/3.5) (293009K111 2.8/3.e) 2COOO7K111 293009K110 ..(KA's) ,
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14 _EB10GIELE5_DE_NWGLE86_E9 WEB _ELeur_ceEseriod. re,o 9 Id E E d 9 D X U 001G 52_ d E 8I _I660 H E E 6_00 D _ E 6 W I D _ E L Q W QUESTION 1.09 (2.00)
The level /pewer control contingency in the OGA's requires that reactor water level be lowered to control power. This is done to reduce the natural circulation.
- a. Briefly DESCRIDE how recucing level reduces natural circulation.
- b. Briefly DESCRIBE how reducing natural circulation lowers power.
I ANSWER 1.09 (2.00)
- a. The driving need is dependent on height (0.53(and difference in density). Lowering lovel decreases the driving head Co.53.
- b. Increased voiding occurs (0.53 which adds negative reactivity to reduce power. Co.53 REFERENCE Duad Cities Emergency Operattnq Frocedures (OGA's) p. 125.
Learning Objective e.
EWR Thermal Hydraulics p. 8-53 and 0-54.
Learning Objective 10.5 keector Theory p. 30.
(2950376303 4.1/4.5) (295037)209 4.0/4.2) (293006K134 2.9/3.1) 297008E1:4 2750376.204 2950376303 .. O,A*s) l i
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1p__EB10GIE650_9E_UWGLE66_E9WES_E66SI_9EE86I1992 Poco 10
- - ISEEu9910001GW2_dE6I_IB6b3EES_6NQ_E(ylQ,E6QW QUESTION 1.10 (1.50)
Reactor power has been reduced to 75% power from 100% power following 5 days at 100%. Recirculation flow is then held constant and no rod ,
motion occurs.
- a. EXPLAIN why reactor power continues to decrease for the next 4-6 hours. (1.0)
I
- b. If recirculation tiew is held constant and no rod motion occurs will reactor power be HIGHER T H A N 7 5 '/. , LOWER THAN 75%, or 75% !
power in 3 days. (Assume fuel burnup is negligible) (0,5) '
t t ANSWER 1.10 (1.50)
- a. A decrease in the burnup term occurs CO.253 and todine from the 100%
concentretion decays to nonon CO.253 results in an increase in xenon concentration CO.25] which adds negative reactivity (0.253.
- b. Greater than 75%. [0.53 i
l REFERENCE Duad Cattes: Reactor Theory p. 24 I
Learning Objective 10.
1 (29200eK114 3.1/3.2) l I
4 292006U114 ..(MA's) :
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' , ISEBt9910ed1G54_dE6I_IE60 SEES _6NQ,E6Q1Q,E6QW QUESTION 1.11 (2.00)
The reactor is operating at 75% power. The reactor operator withdraws a control rod one notch.
- a. What limits the rate o+ power change (period)? (0.5)
- b. If the operator innertc the same rod to its original position (an one notch), ExFLAIN why power will decrease slower than it increased when the rod was withdrawn. (1.0)
- c. Wculd the period be '" _
^
at the BOL or at EOL for the rod W1thdrawal? .5 /.4 5 4 (0.5)
ANSWER 1.11 (2.00)
- a. Delayed neutrons. CO.53
} b. Because the power down transient is limited by decay of the long-lived d etl a y ed neuteon precursors (0.5] whereas, the power up trans1ent is dependent on prempt neutrons iO.253 and shert-11ved delav neutron precursors. Co.25)
- c. EOL Co.5)
REFERENCE I Quad Cittes: Reactor Theory p. 13-15.
Learning Objectivu 6 (29200!>.10e 3.7/3.7) (292008k119 3.1/3.2) 292Cn.&:119 292003K106 ..OA's) 1
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.l't _ _ E 61N G IE L E 3_9 E _ UWG L E B S _ E 9 E E B _ EL BUI _9E E 66I1992 Pcoo 12
, IbEBdQQXUBd1Gei_bE6I_IE605EE6_039_E6W1D_EblW OUESTION 1.12 (1.50)
Concerning control rods.
- a. A shallow control red to dettned as a control rod between notchet
_____ and _____. (0.5)
- b. E4riefly describe the citect movement of a shallow control rod has on an141 and redial tlun. (1.0)
ANSWER 1.12 (1.50)
- a. 36 (accept 32 to 40) (0.253 and 48 CO.253
- b. Due t o hiah rod dentity (0.253 (in the region of the rod) radial response is limited C0.253. Due to tho low void content (0.253 a large change in axial power will occur C0.253 i
REFERENCE i
Duad Cities: Reactor 7 tir< or y p. 20 l Learning Objective 9 (2010036502 2.ne3.3) l 20100!L502 . . O: A s) r I
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it__BBINQ1ELgg_QE_UggLg@$_EQWEB_EL9UI QEg66Ilgy, p3gn gg
. . IdEBd99100DIGei_UE0I_lB003EEB_00D_E6WID_ELQW QUESTION 1.13 (1.00)
SELECT the ONE correct answer. As a suberitical reactor nears criticality, the length of time to reach equilibrium count rate after an insertion of equal posi tive reacti vityt
- a. 15 THE SAME as the longth of time required to reach equilibrium count rate atter an ecual insertion of neDative reactivity,
- b. INCREASES, primartly because of the increased population of delayed neutron: pra*ent in the core with no increase in prompt neutrons. ,
i
- c. DECREA5ES. boteute the source neutrons are becoming less important in relation to the total neutron population.
- d. INCREASES. br: aute nt a larger number of neutron life cycles required to reach equt11trium. !
ANSWER 1.13 (1.00) d [1.03 REFERENCE Ouad Cattert GE Student Tent. LIC-THEO. REACTOR THEORV, Rev. 2 Figure 46. Learntng Object 1ve 4 (292Ov8L105 4.3/4.3) a i
292009K105 .. O.A's) i l
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1,. _ _ E 61b91 EL E 5_QE _ UVG L E 66_ EQWE 6_ EL 90 I _QEE B 01190.s Fogo 14
, .. IdEBdQQ1U651G&i_dEGI_IBOUCEE6_SUR ELVID_E69W QUESTION 1.14 (1.00)
SELECT the statement that correctly describes controlling heatup rate,
- a. If xenon concentretion tu increasing loss rod motion is requirod to maintain a ccnstant heatup rate.
- b. Once a heatup rote av established no subsequent rod motion in required to maintain the heatup rate.
- c. Reactor power muut be continuously increased in order to maintain a conttant heatup rate.
- d. An aust11ary steam loads are put in service more rod motion is required to maintain a constant heatup rate.
ANSWER 1.14 (1.00) d C1.03 ct f 50 pc 4 *p Y "d REFEPENCE Dund Cttiest Feactor lhoory p.28 (29200BL11e 3.e/7.7) 292uvet 116 . . O A 's )
OUESTION 1.15 (1.00)
Durino a reactor startup f rom cold shutdown conditions the reactor has just gone criticall )
l STATE TWO andscatione of criticality. Include the neutron monitoring l instrument on which the indications are observed. l l
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.A__EBINQlELE5_QE_UVGLE66_EQWE6_EL@UI_QEE6611QU2 Pcgo 15
.' IUEBdQDYU651G52_UEGI_I6805EEB_8UD_ELWID_EbQW ANSWER 1.15 (1.00)
With no further rod motion, period remains positive (0.053 on that source range period meter CO.053. Noutron level continues to increase Co.253 on the ERM tIRM) CO.053 REFERENCE Ouad Cities 1 Reactor Theory, t', 27. and CGP 1-1, page 4 (29008)107 3.i<7.9) (290008K106 4.O/4.O) i
] 290008K1Q6 290006: 107 .. WA's)
+
I QUESTION 1.16 (1.09) i 1
Which of the parameter changer (1, 0, or 3 eelow) would result int 4
i a. the largest insertson at reactivity' l
- b. the smalleet insertion of reactivity' Consider only tha uqttude e+ the ro+ctivity enange. Do not be ,
concernt d wi th whether t n t- change at positive or negative. l L
j PARAMETER CHANGES l
l 1.
- 1 F change in fuel temperature i i !
! 2. a 1 F change in mot arator temperaturo I
- 3. a 1 */. change i n v o . <,r. . t I
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(+N5WER 1.16 (1.00) ,
- a. Co.53
- b. 1 CO.53 i
i REFERENCE l
l Ouad Citiest Reactor Theory ,tgure 46.
l Learning Objective 7.
42920046114 3.5/3.3) 292004K114 ..(VA's)
DUESTION 1.17 (1.00)
Why doet a 1ces of an "A fetdweter heater" require addit 1onal and more dece t t e operator response than a loss of a " E4 , C. or D"
+ eedwat er heater' I
f4N5WER 1.17 (1.00) i Loss of an A " heater will cause a large feedwater temp.
excurston C.333 and ns 116ely to cause a large power increasot.333 that may result in a htch AFRM sc r ain i f the act t ens are not taken.C.?4J l l
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REFERENCE l l
l Ouad Cstiest Feedwater heatres LIC-3200-2 revi TF0 #5 pq1. COA !500-1 rev 4 Sec C.2 pq2 C5 WotA200 3.1/3.5) C54 001 G015 3. 6 / 3. 8) C9500e6 00o 4.2/4.3)
'9500M 20n 259001G015 259001A202 ..tFA's) 1 1
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. 3 , -- 7 -- -- - ,
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l* IbESO9RXU0dlG%2_bE01_I660sEE6_000_EbWID_EL9W QUESTION 1.10 (2.00)
LIST 4 means (causes) by which reactivity changes occur (positive or negative) in the power rango.
l ANSWER 1.19 (2.00)
'1. Con t r ol rod moveirento
'O. Rectrculaton flow etienne -
- 3. Fuel teTperature chancos. j 4 Fission product poison encnges J
- 5. Void content changes.
REFERENCE .
i Oued C1ttest Feactory Thre r v . ic1F O k s - 2 4 t (2920096113 3. O e . . ES ) <242OO8k114 .1/3.Di (292008L122 3.5/3.6) 1 1
29200EL122 29 2tA e) .1 14 24200EL11a . . ( F(4 's ) l I
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2t. ELGUI_ dei 100_10CLUR102_56E6li_s00_EDE69EUG1 .ga le EXEIEbH DUESTION 2.01 (1.50)
For eeth of the f oll ows na optrations, identity the suction val ve (t )
lino-op required to satisfy FHR pump start i n t er l oc k.s .
(NOTE: Only the valvec M OUlhED to satifly the start interlock is requested, GT Ccepletc +10w path.)
- a. LFCI a n Jc;t t oi, L O. M
- b. Supprossion pcol cooling 40.5) l l c. I n )oc t i can to t he react rr s c. t E e l + rom the CCsT (0,5) l ANSWER 2.01 t 1. 6.0 )
- a. v.= l e 1601-7tA. F. C. D> opern (0.53
$gppesShi h 700( SA Lb
- h, v.tve p:iot-7<a, e, c. Di ap4n t0.5) s, o pp e . s s'. ew yeol sue _f d v.,1 s . p 1 - 4. . ... , F. (, in een tv w ce w me.h's I sy yyncy Ace *f+ va lu e d e s c e',p 4 5 l
Duod Cetart i n i- TIC-iv00-1 rev 2 .
T F'O at 4 pg 1, Sec II.D pg 10 to la t' pe7i n iq ano ? i.ft.5) t:1;v0aa414 3.7f -.5) t;t%>vQa401 3 . 6 e '. 7 )
(;v50003401 ! . 7 / 3. 7 ) (CO';Ov0a402 3.o r3.bi
.m O 5 . .;.i . , , .. ; _ ; c =.. ices A4 01 2150 >O, 401
, 21 g yecc,414 ,:v;OOO6 K3 l ..OA si l
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-. SYSIEd5 h
'OUESTION 2.02 -(1.00) ;
A fire is reported in Unit 2. Both diesel. driven Mire pumps. ',
fail t cc start. Identify the followings
- a. What is the backup water supply for the fire protection '
system ? (0.50)
- b. HOW and WHERE is tno backup water supply activated? (0.50) t j
ANSWER 2.02 (1.00)
.j ,
i
- a. Service water CO.53
- b. By opening valve MD-1/2-3906 (service water to fire main x-tie) '
from panel 912-1. L0.53 ,
i Also REFERENCE
%.ec,7P * " Mwd o p era.4 s % of 59 0 6 ! O e. er'eb ,
I Duad Citir.n: Service Water LIC-3900 rev 3 i TFO i$1 !< 3 pg 1, Sec II.2.E.1 pg 10 t j (286000k401 3.4/3.6) (286000k403 3.3/3.4) (286000a205 3.1/3.3) '
1 4 !
) 286000A205 286000K403 286000K401 ..(KA's) I, j ,
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25._ _E66bI_ Rg g10N_1bG6u91gg_seEgIy _.eU D_g dg3gg NQX Page 2v
- SyEIgde QUESTION 2.03 (1.00)
Which ONE of the f ol l owi ng OFF-GAS al arms i s an indication of a possible OFF-GA5 explosion'?
- a. Recombiner Catalvst Temperature of 875 F.
- b. After Filter High Flow of 180 SCFM.
- c. Prefi1ter Differential Pressure High cif 8" H20.
- d. High Temperature in Oft-Gas Holdup Volume of 140 F.
ANSWER 7.03 (1.00) d C1.0)
REFERENCE Dead Ci t t en: GFF-GAE t.IC 5450 r ev 1 TFO #5 pg 1, Sec IV.A.5.o pq 241 t2710000008 3.4/3.4) (271000a20e 3.5/3.9) 2/1000A20e 27100vGo08 ..(KA's)
OUESTION 2.04 (1.00) bwitches in the 125 VDC distribution panels are color coded green, vellow, or red. What 12 t h t) FUNCTION of this color codel I
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Pcga 21 2n-_E609I_ des 199_IUCLUDIU9_5GEEIY_00D_EdEEGEUCX SYSIEd5 ANSWER 2.04 (1.00)
The color code identities the level of permission / notification prior to opening of a color coded switch.
CEFERENCE Ouad Citiocs 00P 6700-4. re, S.
Sec C, prerequiuitos, pg 1 (263000G001 2.3/3.6) (2e y 'uoG013 3. 3/3. 5s 263000GO13 26300nG001 .. WA's)
OUESTION 2.05 t3.001 Answer the +~ollowing questions concerning the HFCI system.
- a. List FIVE HFCI turbine trips with setpoints.
(2.00) b Which ONE of the following occurs atter all HPCI turbine trips? (1.0)
- 1. Valve HPCI injection valve (2301-8) closes.
- 2. Valves HPCI Steam supply inboard and outboard valves (2301-4 6 -5) close.
- 3. HPCI stop valve . loses.
- 4. Valve Suction from CCST (2301-6) closes
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E66UI_DE51QU_INQLUQ1GQ_g@Egll_@dp_@UE8QEUQY Fage 22 2cp_SXEIEUS ANSWER 2.05 (3.00)
- a. (Any 5 of the folowino @ 0.25 for signal and 0.15 for setpoint each.)
- 1. Hi vessel level @ 48"
- 2. High turb exhaust pressure @ 100 psic
- 3. Low booster pump suction pressure 0 -15 in Hg.
- 4. Remote elec. trip, pushbutton
- 5. Remote overspeed tr2p, pushbutton
- 6. Mechanical overspoed O 5050 rpm
- 7. Local manual trip, lever
- b. 3 C1.03 REFERENCE Ouad Cities: HPCI, LIC-2300-1 rev 0 TPO #7 pai. Sec 2.a L b pg 31 L 32 (206000k401 3.8/3.9) (.106000A201 4.0/4.0) 206000A201 206000L401 ..(KA's)
DUESTION 2.06 (1.00)
LIST FOUR of the conditions that must ei: i s t for a reactor feedwater pump to start as a standby reactor feedwater pump?
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2'y _ELONI_ DESIGN _JUgLyp1Ng_S@Egly_6UQ_EbEBQEdgy Pago 20
. EX3IEd3 ANSWER 2.06 (1.00)
Any 4 of the following G 0.25 each;
- 1. Supply bkr on running pump trips.
- 2. The pump is selected to standby
- 3. Suction pressure adequate (>l20 psig)
- 4. One ventilation fan cperating
- 5. Oil pressure ade~uate (>10 psig)
- 6. Reactor vessel 4evel in spec. (< 48")
REFERENCE Ouad Cities: Feed & Concensa+ e. LIC 3200 t< 3300 rev 2 TPO #4 pgi, Sec I.5.3 pg 24 (259001k401 3.8/4.0) (259001A301 3.3/3.5) 259001A301 259001K40t ..(LA's)
OUESTION 2.07 (1.50)
Edri ef l y expl ai n how the fire detector Pr ot ec t o wi r e" functions. Include in your explanation how the location of the + 1re is determined.
ANSWER 2.07 (1.50)
The protectowire is a two wire system. The wiret are covered with a heat sensitive covering that melts (at 280 F). When the cover is melted the treo wires thort tegether(0.5]. Pr ot ec t owi r e f eedes a computer that can determine the dintanco along the wire to the short. Frocedure 004 4100-T2 provides a map to determine the location of the f i e re with relation to the location (in feet) of the short [1.03.
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'2, . PLANT DESl@U_lNGLQDIUQ SAFETY AND EMERGENGY. Page 24
,,. :SY5IEd5 REFERENCE Ouad Cities:' Fire Protection systems LIC 4100-1 rev 2 TPO #2 4< 4 pg 1 ~, Sec. II.F.1 pg 24 (286000A401 3.3/3.2) (286000 GOO 8 3.7/3.6) 286000GOOO 286000A401 ..(KA's)
OUESTION 2.08 '1.00)
Concerning the instrumeet ai r system (IA), which ONE of the following correctly completes the sentence?
The service air to instrument air backup (crosstie) ...
- a. opens if the IA compressor low suction alarm (7.6" Hg.)
actuasc;.
- b. is fully open at 85 psig and fully closed at 105 psig.
- c. is operated manually.
- d. closes on service air low pressure of 85 psig.
ANSWER 2.09 (1.00) b (1.03 REFERENCE Quad Cities Inst. Air, drywell pneumatic air, LIC 4700-1 rev O TPO #4 pgi, Sec. III.B.1 pg 10 (295019A101 3.5/3.3) (295019K301 3.3/3.4) 295019K301 295019A101 ..(MA's) i 1 ;
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QUESTION 2.09 (1.50)
Due to control room abandonment it is desired to operate the Safe Shutdown System outside the control room.
ANSWER each of the fol1owing TRUE or FALSE:
- a. Control of the Make-up Pump must be transferred to the safe shutdown room prior to leaving the conteal room. (0.5)
- b. Hn interlock prevents the centrifuaal Make-up Pu np from starting without a dincharge path. (0.5)
- c. Closure of the Flow Control Valve (MO 1/2-2901-6) will cause the Mal:e-up Fump to trip. (0.5)
ANSWER 2.09 (1.50)
A*7~
- a. False CO.51 (It is transferred w the safe shutdown room)
- b. True (0.53
- c. True CO.51 REFERENCE Ouad Cities: Safe Shutdown System L. I C-2900 pp . 4 and e.
TPO-4.
(2950166201 4.4/4.5) (2950316006 4.1/3.9) (295009G006 3.9/3.9)
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2:__Eb6UI_DE@lGU_1NQ69Q1NQ_@@Egly_6NQ_gdEEQEugy Pcge 26 EXHIEDs QUESTION 2.10 (3.00)
Unit 1 Diesel Generator auto starts. After running for two minutes the diesel trips. Unit 1/2 Diesel Generator did not start.
- a. List FOUR possibla causen fer Unit 1 Diesel Generator auto tarting. (2.0)
- b. List TWO possible causes for thri Diesel Generator tripping. (1.G)
ANSWER 2.10 (3.00)
- a. Undervoltage on Eus 14-1 Co.53 Backup undervoltage on Dus 14-1 CO.53 Undervoltage on bun 14 CO.53 Both feed brealers open to Bus 14 CO.53
/4 -to l 'l- I ~{f ed beeaIt t ofn
- b. Overspeed E0.53 Differential Overcurrent CO.53 REFERENCE Ouad Cities: Diesel Gen. LIC-6e00 p. 44 and 4e.
TPC-4 an ci S.
(264000K4u2 4.0/4.2) (264000K408 . 8/3.7) 264000L408 264000K402 ..(KA's>
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2s__ELONI_QEg1QU_10GLUQ1NG SAFETY AND @dg6@ENQY Page 27 l SXEIEd5' J
QUESTION 2.11 (2.00)
Concerning operation of the Automatic Depressuri:ation System ( ADS ) .'
- a. Reactor water level is -59 inches and slowly lowering. Drywell pressure is 2.5 psig and slowly increasing. RHR and CS pumps 4
are running with discharge pressure > 100 psig. ADS valves should -
(HOW LONG7) open in _____________. (0.5)
- b. Reactor water level is -59 inches'and slowly l o wer i n g '. Drywell !
- pressure is 1.5 poig anc constant.- One RHR pump is operating with a discharge pressure et >100 psi g . ADS valves will should open in
____________. (HOW LONG?) (0.5) 1 .
l c. (TRUE or FALSE)An ADS blowdown is in progress. Placing the ;
- a. Auto Blowdown Inhibit switch to Inhibit will stop the blowdown. :
(0.5) ;
r
- d. (TRUE or FALSE) An ADS blowdown is in progress. Operating the {
DRYWELL PRESS RESET switen will stop the blowdown.- (0.5) .
E i
ANSWER 2.11 (2.00) 4 .
l a. 110 r.ec CO.51 l 1
L
- b. 8.5 minutes Co.53 i 4
- c. True Co.53 !
4 L i d. False Co.53 "
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- REFERF.NCE l
t I
r l Ouad Cities: Automatic Pressure Relief System Figure 1. l
- p. 3 and 5.
l TPO-5 and 6. !'
- (218000k403 3.8/4.0) i >
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.. - SYSIEUS QUESTION 2.12 (2.00)
Concerning operation of Drywell Sprays.
- a. (Fill in the blanks) Initiate drywell sprays only if drywell pressure i s above ____ (1) _______ and drywell temperature i s below
______( 2) __ _= (l 0)
- 6. (True or False) If de vwel l spray is required then both loops of RHR should be used in order to cbtain maximum cooling possible. (0.5)
- c. (Fi11 in the blank > Do not st ar t drywel1 sp"ays i f suppression pool level is above ___________,._. (0.5)
ANSWER 2.12 (2.00)
- a. 1. 5 psig (Accept 5 to 6 psig) CO.53
- 2. 340 F (Accept 310 to 340 F) CO.53
- b. False CO.53
- c. 16 ieet. (Accept 16 to 18 ft.) LO 53 REFERENCE Quad Cities, FHR LIC 1000-1 TPO #5, PP. 46 & 48 (22er O1G010 3.2/3.4) 22eOO1G010 ..O A'e) i 0*++++ CATEGORY 2 CONTINUED ON NEXT PAGE +++++)
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Ot__E60UI DESIGU IUCLU9100 SSEEI1_6UD_EdEE@shg'1 Page 29
,..' 5YSTEM5
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QUESTION 2.13 (1.00)
Assume a LOCA and loss of offsite power has occured on Unit 2.
Due to the design of the DG system, what action must the operator perform to insure Unit 2 has priority for the 1/2 DG7 ANSWER 2.13 (1.00)
The operator must place the Unit-2 1/2 DG output breaker keylock control switch in the OM position. [1.03 REFERENCE Quad Cities Diesel Gen L1C 6600 rev 4 TPO #6 pg 1, Sec IV.C.5 pg 48 (264000 GOC 1 3.7/4.2) (264000K101 4.1/4.2) 264000L101 26400uGool ..(KA's)
DUESTION 2.14 (1.75)
What are the power sources available to buses 13-1 and 14-1?
(+++++ CATEGORY 2 CONTINUED ON NEXT PAGE +*+++)
- a. .
3 PLANT DESIGN INCLUDING _@@ Eely _@UD_EdgBQEUCy hoge 20
. . . @YSIEd5 ANSWER 2.14 (1.75) sus 13-1 Bus 14-1 13 (normal) 14 (normal) 1/2 DG 1 DG 24-1 crosstie C7 6 0.25 ea.1 REFERENCE Ouad Cities Elec. Di s t . LIC 6000-1 rev 0 TPO #2 pg 1, Sec II.B pg 10 (2620014302 3.2/3.0) (262OO1K406 3.6/3.9) 262OO1K406 262001A302 ..(KA's)
QUESTION 2.15 (1.00)
Which ONE of the following correctly completen the sentrence.
An en er g i r. ed blue light in each tour light display indicates:
- a. the scram pilot solenoids for that control rod are deenergined.
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32__EL8UI_ DES 10N_1UGLYDING_58EElf_GUQ_gdE6@gGQ1 Pcgp 31 SYSIE05 ANSWER 2.15 (1.00) d C1.03 REFERENCE Quad Cities RMCS and RPIS l.IC-0281-1 TPO # 6 pa 1. Sec. E4.1.C pg 4 (214000a301 3.4/3.3) 214000A301 ..(KA's)
OUESTION 2.16 (1.25)
Expl ain why the OFF-GAS radiation monitor detectors are located "2 minutes" into the 30 minute holdup line.
ANSWER 2.16 (1.25)
The location was selected to allow time for short lived radioactive nuclot, principally 0-19 and N-16CO.51 to have sufficient time to decay (0.25] and theref or e contribute minimally to the gross radioactivityCO.5].
REFERENCE Quad Cities: Process Radiation LIC 1700 rev 1 TPO #2 pg 1, Sec. b . 3 . 7. pg 10 (272OOOklO2 3.2/3.5) 272OOOK102 .. WA's)
(+++++ CATEGORY 2 CONTINUED ON NEXT PAGE +++++)
- 2. PLANT DESIGN _ldCLyflNg_g6Egly_6UD_g[EBQgNGy y Pcgo 32
,. . SYSIE05 QUESTION 2.17 (1.00)
Identify the 2 rod insertion interlocks NOT bypassed by the "Emergency In" position of the Red Out Notch Override Switch.
ANSWER 2.17 (1.00)
- 1. Rod Worth Minimizer tnuert block [0.53
- 2. Select blocks CO.5]
REFERENCE Quad Cities RMCS t< RFIS LIC 0281 rev 1 TPO #7 t< 8 p g 1 Sec B.2.4.b.4 pg 10 (201002k406 3. 5,' 0. D )
201002K406 ..(KA's)
(+++++ END OF CATEGORY 2 +++++)
I'.__1USIBWbENIS_8Np_CQUIBg63 Page 33 QUESTION 3.01 (1.50)
The operator has three difterent types of indication to determine if an Electromatic relief valve is open.
LIST the THREE typec of indication and STATE what parameter is sented to provide each position indication.
ANSWER 3.01 (1.50)
- 1. Valve solenoid - Energt:ed <3 tate
- 2. Acoustic monitor - Menitors + low noise through the valve
- 3. Tail Pipe Temperaturn - Monitors torperature in the relief valve discharge piping.
C3 '~f 0.5 ea.3 (1.5)
PEFEPENCE Guad C i t i e e.: L OC-02SO-1 f F. 12 & 14 Lesson Obyoctive 5
( 2 N .10 3 50 3 ~; . 7 / 3. 8 ) (239002KSO4 '3. 3 / 3. 5 )
23900'S504 234002k503 ..(KA's)
OUESTION 3.n2 (1.50)
STATE THREE automatic actions which occur if both channels of reacter building refueling floor radiation monitors naceed their trip rot point.
(+++++ CATEGORi 3 CONTINUED ON NEA*. '
2A INSTRUMENTS AND_GQNIRQL5 Page 34
.+
ANSWER 3.02 (1.50)
- 1. The Reactor Building Ventilation System is i sol at ed.
- 2. Standby Gas Treatment System starts.
- 3. Control Room Ventilation System isolates.
E3 G v..S ea.] (1.5) 4/+6 sec.p+oe,4./ /e m YM. f 8b Miks 1e s 8
- # #~
REFERENCE Ouad Cities: LIC-1700 P. 24 Lesson Objective 5 (272000K106 3.2/3.3) (271000K110 3.2/3.3) (288000K105 3.3/3.6)
, (261000K401 3.7/3.8) 261000K401, 288000K105 271000K110 272000K106 ..(KA's)
OUESTION 3.03 (3.00)
The reactor is at 50% power with the load limit set at 65% and Mattimum combined flow limiter at 1 16 */. . Recirc Master Controller is in Manual. An electrical failure occuru that causes the pressure set signal to decreaGe 10 PGi.
DETERMINE the final control valve flow rate (in percent of reted flow) and bypass valve flow rate. Refer to the attached drawing of the Electro-Hydraulic Control Logic (Figure 1). DESCRIBE how you determined your answer.
(+++++ CATEGORY 3 CONTINUED ON NEXT PAGE +++++)
- . Page 3b 2 __IUsIEUUENIS,,6ND_COUISA@
9 ANSWER 3.03 (3.00) c .
Output from pressure summer A increases to 25 psi (. . The HVG passes this signal to the Pressure / Flow converter * . The Presejge/Fl ow converter output will increase to 02-03% (Accept 75-90%)
3
(./f/.7 T g* 1oad 1imit wt11 1imit the signal to the governor valven tg65%so (.7/. Total flow is less than the maximum combined limiter
( ,.,A the bypass valves will open to pass 17-18% (Accept 10-25%)
Q"g' I'P R*de r pra ssa r e ee,-u se s 4 euk / pressure REFERENCE w;it
- f'' "
8IT (' M s ef f
- l d }* A 9to
- c. fg [ val J e g d///
g (.sfs 51s8 pas s salves gg; g)
W d u <- 4 L ec e eas e h pre ssure[c.ss) , gk Duad Cities: EHC FRecture Corit t ol &c Logic LIC-5650 pp. 6, 7, 8, 9, 17,
- 18. Figure 6. TFO 5, 7, 14 (241000h305 3.7/ ~ 7) (241000K306 4.1/4.1) (241000K308 3.7/3.7) 241000K308 241000)306 241000K305 ..(KA's)
OUESTION 3.04 (1.00)
Followina an automatic initiation of HPCI witn flow stable at 5600 gpm. the 125 Volt C motor associated with the Motor Gear Unit (MGU) selrec due to bearing t' e i l u r e .
Chooce the ONE correct rtstement which describec the effect this failure wi11 hase on the HFCI ny3 tom.
- a. H5CI t tir ni ne wil: trip on overspeed
- b. HFCI turbine speed will lock up and not automatically respond to t. tiet r oa s e in reactor pressure and over feed the reactor.
- d. HPCI speed control will be assumed by the Motor Speed Changer (MSC) via a hydraulic low value gate.
]
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24..._idsIEWdEUIS_6UD_CoulEOLS eage se ANSWER 3.04 (1.00) d C1.03 REFERENCE Quad Cities: LIC-2300-1 P. HPCI 10, Figure 8 Lesson Objective 3 (206000K400 3.8/3.9) (206000k411 3.4/3.5) 206000K411 206000K409 ..(KA*c)
OUESTION 3.05 (1.00)
The reactor ~ in operating at 75% rated power with Channel A Main Steam Line Radiation Monitor in the trip condition due to a failed power supply. The Main Control Room Operator in the process of performing a system lineup check, inadvertently turns the B In-Board MSIV test switch to the TEST position Chooco the ONE correct statement which descrit en the ef f ect this action wt11 have on plant operstion.
- a. The reactor will screm on a MSIV closure signal tensed in 3 steam lines.
- b. H full reactor scram and Group 1 isolation signal will result.
- d. The reactor will scram on a high flow sional sonned in the other ' steam lines.
ANSWER 3.05 (1.00) c [1.0]
(+++++ CATEGORY 3 CONTINUED ON NEAT FAGE +++++)
7 Psge 37
....t__INjl8pMgNI5_@UD_GOUI6965 REFERENCE -
Dund Cities: LIC-0250-1 P. 24 & Figure 11 Lesson Objective 12 (239001K401 3.8/3.8) (239001K127 4.0/4.1) (239001M117 3.1/3.2) 239001K117 239001K127 239001M401 ..(KA's)
CUESTION 3.06 (1.50)
STATE what equipment is operated (effected) by both an automatic and manual actuation of ONLY ONE CHANNEL of the Anticipated Transient Without Scram (ATWS) trip circuitry.
ANSWER 3.06 (1.50)
- a. Aut omat i c s Trips Both Rectre Pump Field Breakers CO.53 Enerq1:en one half (respective channel) of the Alternate Rod Insertion (ARI) Valves. [0.53
- b. Manual Energines one half (respectivo channel) of the ARI Velvet. CO.U]
REFERENCE Ouad Citieu: L I C-0 30i i-3 P.14 Lesson Objoctive 3 (202OO1K127 4.1/4.3) (212OOOA416 4.4/4.4) 212000A416 202OO1L127 ..(k4's)
(+++++ CATEGORY 3 CONTINUED ON NEXT PAGE *****)
Pa9e ea
.,23 _1U51BWDEUI5_6UD_C9 DIS 965 OUESTION 3.07 (1.00)
The Reactor is operating at 100'<. rated power with the following conditions: IRM Channel 11 in bypass APRM Channel 1 in bypans.
With those conditiens present IRM Channel 12 fatIs upscale.
Answer the following (YES cr Not concerning expected automatic actions and required operator rerponse.
- a. Will any automatic protecttve action, cuch as rod block or scram be received?
- b. Is any additional operater inserted trip actions necessary to comply with Technical Spectfications for APRM/IRM operability requirements?
ANSWER 3.07 (1.00)
- a. NO CO.53 No
- b. e [G.53 REFERENCE Ouad Citince LIC-0700-2 P. 14 Lennon Objectivos 4 6 10 LIC-700-4 P. 8 Lesson Objective 8 (215003F606 3.2/3.4) (21500D:305 3.7/3.8) 21500!L305 21S00!K606 ..(EA's)
OUESTION 3.08 (1.00)
~
Descrit e the trip logic associated with the unit Rint.w pumps.
l (Include applicable setpoints)
(+++++ CATEGORY 3 CONTINUEl' DN NEAT PAGF +++++)
24__IN318gdgyIS_SUQ_QgUIBQ63 pago 39 ANSWER 3.08 (1.00)
Undervoltage on BUS 13, 14, 23, or 24 [0.253 and one of the following: 2.5 peig drywell pressure CO.253.
-59" vessel l evel and 325 psig vessel press C0.25].
-59" vessel for ; 8.5 minutes [0.253.
(NOTE: specific pump / bus combinations not required.) (1.0)
REFERENCE Ouad Cities: RBCCW LIC J,700-1 rev i TPO #7 pg 1. Sec. II.B.5.6 pg 4, lI.B.5 pg 5 (295018a203 3.2/3.5) 295018A203 .. WA's)
OUESTION 3.09 (2.00)
Concerning the off-gas radi;< tion monitoring system.
- a. If one channel is failed ocwnscale, state TWO conditions required for an s col ation to occur'>
- b. STATE THREE AUTOMATIC actions which will occur en an isolation?
ANSWER . 09 (2.00)
- a. An uptc+1e on the other channel [U.5] end the 15 minute timer t i me$d out. CO.52
- b. The off-gas chimney i sol ation val ve closes (5406) [0.53 The off-gas line drato valve closes (5408) CO.25]
The off-gar tant is iso ated from the prensurtrod draan pumph'per.rtyrared
- *NKV.253 drain I
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(+++++ CATEGORY 3 CON 1INUED ON NEAT PAGE +++++)
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. REFERENCE Ouad Cities: Process Radiation LIC-1700 p. 12.
TPO-5 (272OOOk402 3.7/4/1) 272OOOK402 ..(KA's)
DUESTION 3.10 (2.50)
Concerning the MSIVs
- a. The mode switch is in st.<rtup with reactor pressure equal to 800 psig when an automatic MSIV is71ation occurs. LIST the possible signals that could have caused the isolation.
(Include netpoints) (2.0)
- b. (TRUE or FALSE) Reactor power is 30% when a MSIV isolation occurn.
AVscram will occur if NSIVs close in only two Main Steam lines.
pj/ (0.5)
ANSWdR 3.10 (2.50)
- a. Htqh Steam Line flow 140% of rated in a steam Itne Low reactor vessel level -59 inches Steam Tunnel High temperature 200 F MSL High Radtation / .: NFPE4G 9
(.25 for each signal and .25 tor each setpoint)
- b. False LO.5]
(+++++ CA1FGOR( 3 CONTINUED ON NEAT PAGE +++++)
21__IUSIBUMEUIS_6dp_q0NIBQLS Pcga 41
' REFERENCE Ouad Cities: Main Steam Line System LIC-0250-1 p. 28 TPO-8 Reactor Protection System LIC-0500-1 p. 24 TPO-7 KA 4.1 3.8 (239001K127 4.0/4.1) (239001K401 3.8/3.8) 239001K401 239001K127 ..(KA's)
OUESTION 3.11 (3.00)
For each condition licted in column I below SELECT the action (s) listed in Column II that will occur.
(NOTE: More then one act s on may be expected.)
STATE if no action will occur.
Column 1 Column !!
=========u======== ============
range 2. The operator wit! . wino GRM detectern 2. A -cram signal will be als : IRM i -
A cenerated.
detector selected. g we/ 3. A rod block is generated.
- b. T het operetor adjusts rectre flow such that there is r 4. No actions occurs 15% mismatch between loopn.
- c. Reacter is in the RUN modo and an AFPM falls downscale.
All IRM are withdrawn and indicatino 25 on range 3.
- d. Reactor at in startup mode and excessive feedwater flow causes power to increase to ;
15%.
- e. An approach t o c r i t i r. a l i t v begins with IkN C on rance 2.
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a* .
I:__10SIEUdgNIS_GdD_GQU16969 F a g r> "J
- e ANSWER 3.11 (3.00)
- a. 3 CO.5]
- b. 4 CO.5]
- c. 3 CO.5]
- d. 2 CO.5] and 3 CO.53
- e. 3 CO.53 (6 6 0.5 ea.)
REFERENCE .
Quad Cities: Intermediate Rance Monitor System LIC-0700-2 p. 13.
TFO-4.
Average Power Range Monitor System LIC-0700-4 p. O and 9.
TPO-o.
LA 3.7 3.7 4.2 (915n03k401 3.7/3.7) (215005K401 3.7/3.7) (215005t402 4.1/4.2) i 215005t402 215005F .401 21500?K401 . . O: A ' 5)
OUESTION 3.12 (1.50) en leak develops which results in dnpressurl:ation of the r ef ac tor at a rate of 30 psi por minute. HFCI maintains reactor water level but drywell pressure increases to 3.2 pn2g.
- a. At wrat reactor pressure will the core spray inboerd in;oction valve open? l
- b. At what flow rate will the core tpray minimum flow valve close' i c. Decer it e how the operat or can control the amount of Core Spray flew to the vnsuol.
I.
(+++++ CATEGORY 7.'. CONTINLIED ON NEXT PAGE ++**+) ;
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. 2d__INSIEUdEUI6_6UQ_CQUI6QL5 ANSWER 3.12 (1.50)
- a. 325 psig (Accept 300 to 350 psig) CO.5]
- b. 700 gpm (fnec ep t 650 to 7S0 gpm) CO.51
- c. By throttling the I nb oar ci Injection Valve (th C O. 5]
REFERENCE Ouad Cities: Core Spray t. l C- 1400 p. 5 and 6. TPO-7 LA 4.0 3.6
( 209001 K408 ;,. 8 / 4. ui (2090014411 3.7/3.6) 209001A411 209001K408 ..(KA's)
OUESTION 3.13 (2.00)
Concern 3no the Recirculation Fump Seals, PIATCH tP.e expected indications in part A with the mechanism of failure in part B. Refer to the attached figure 2, Recircul at i en Fump Seals.
Port A Indications Part b bochanism of Failure
- c. No. 2 seal precture would 1. Gross failure of No. 2 teal go toward :: er o . only.
- b. No. 2 seal pressure woulc 2. Plugging ut No. 1 Internal approach No. j seal pressure, o r i f i c e3.
l.eAlage th u No. 2 crifico i will go to 1.1 gpm. 3. Pluggina of No. 2 internal orifice. j
- c. NO. 2 seal pressure would i approach No. 1 seal prcmsure. 4. br o s.s failure of No. 1 c.c a l Controlled leakage would only. j approach zero.
- d. No. 2 soal cavtty pressure would drop to zero, t+++++ CATEGORY 3 CONTINUEI' ON NE)T PAGE +++++) l l
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Dc__1U316UMENI@_80Q_CQUI69LS pcgo 44 ANSWER 3.13 (2.00) a-2 CO.53 b -4 CO.53 e-3 CO.53 '
d -
1 CO.53 REFERENCE Ouad Cition LIC-0202-1 P. Rect r e - 5 Lesson Objective 6 (202001a109 3.3/3.3) 202001A109 ..O'A'*)
OUESTION 3.14 (2.50) l Concerninq the Rod Worth Minimarer (RWM) answer each of the followinq a TRUE or FALSE i
- n. A withdraw block will not occur until the second rod in a rst e p is withdrawn one notch past its withdraw limit.
- b. With t he RWM enf or cino a wi thdrew block , rods with insert e r r o r t; {
o<1 sting may be withdrawn to their correct position.
- c. An insert block will occur when any rod is inserted one notch pant i
its limit. !
(
- d. Both total cteam t'l o w and feed flow munt drop belew 207, to activata l the RWM rod blocks.
- o. When the RWM detecto a rod drift it automatically i n t er t ta a withdraw block i
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Pege 45 sf.__IUSIEUdEUIS_6UD_G9 BIB 965 ANSWER 3.14 (2.50)
- a. False CO.33
- b. True CO.5)
- c. True CO.53
- d. False CO.53
- e. False CO.53 REFERENCE Ouad Cities: LIC-207 FF.25 !> 40 Lesson Objectives e tc 10 (201006K401 3.4/3.5) (20100et:402 3. 5/3. 5) (201006K404 3.4/3.5)
(216006U409 3.2<?. 2) 21600AK409 20100ef:404 20!OO6K402 201006F401 ..(MA's) l r
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4
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h.s.__E60GEDW6ES - NORMAL 3 _AE' NORMA 61_ EMERGENCY Fage %c
. 6BD_E6D196991G66_G9BIEQ6
=
QUESTION 4.01 (2.00)
List FOUR methods of monitoring to assure actual Standby Liquid Control System injection following its initiation.
ANSWER 4.01 (2.00)
Any 4 of the follcwing at 0.5 eacht
- 1. Amber pilot 11 t 'it et equib firing continuity circuit not lit.
- 2. Flow indicating pilnt light lit.
- 3. Reactor water ciranup system i sol at i on.
- 4. Decreaning level et standby liquid storage tank.
- 5. Standoy liquid equib valve circuit tail annunciator light lit.
- 6. Reactor flux lovel instrumentation indicate power reduction.
REFERENCE Ouad C1 ties OUP 1100-2.
4
.110v0 A 191 -3. e- ) ( 211009 A 192-3. 9 ) , t .21100n A 10t - 5. 8 ) . ( .' t 1700A l o7-4. :)
( 21100n A 110- 3. 7 >
211000A110 211000Alv7 '?l1000(4106
. 211010A102 21100nA101
. . W A ' s .'
OUESTION 4 . 0.7 (2.00) i
! According to DOP 280-1. " hoec t or Manual Control." a cbution in Stop 4.a.
otaten that continuous red w i t h dr a w e,1 nhould be used with cautien and
, lists the primary uses for this mode of rod movetient.
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- a. STATE THREE condittens when u rs o IS PERMITTED. ( 1. "$ )
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- b. STATF ONE c ondi tion when tis e 17, specifically F ROH I t< ! T E D . (v.5) 4
)
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req 3 47
- * $t'__PBgggpuSgg_ _UgeMAL,,,egugEMeLi_gMEEggggy o . 600 609106001GsL_G991696
+o ANSWER 4.02 (2.00)
- a. Any 3 0 C.5 pts eacht
- 1. During startup
- 2. Timing CRDs
- 3. (CRD Friction Testing)
- 4. Emergency situations
- b. One of the following at 0.5 pts
- 1. Shutdown margin demonstration
- 2. Edetween notchee 04 f< 12 on arrays 394
- 3. Notch 00 to 24 boyond 50% rod density, until one bypass valve is open.
REFERENCE Quad Citi es: DOP 280-1, page 3 and OGP 1-1, page 4 (201002G007-3.e) (20100;G010-3.9) l 201o02Gelo 2010o2s007 . . ou c > ,
OUESTION 4 . 0 ". ( 2. 0".i )
1 +~ eperat2no 1n @utdown cooling and both recirculation pumps are lost, OOP 1000-5 SHUTDOWN COOLING START-UP AND OFERATION, requires the operator to monitor tor temporeture stratificotton,
- a. List the tr'e a s u r e d parameters (1), (2), and (3) which correctly c omp l e*t e the f ol l owi ng sentence.
Stratification tu indicated by incroning (1) , , _ . , _ , , _ _ _
without a corresponding (2) ______ or (3) , , _ _ _ , _ change, (0.75)
- b. List FIVE of the nucgo<sted actions to minimi:'e strati +1 cation
. 1f both rer t r c pumps are off. (1.25) r
(+++++ CATEGORY 4 CONilNUED ON NEXT PAGE +++++)
- a. .
S._ E60GEQUEES_:_U960eLi_eEU96 deli _EdEBGENGI Pa9c 4e
- - ~ ANQ,BApig(QQ1 GAL _QQNT6QL ANSWER 4.03 (2.00)
- a. 1. Reactor metal temperature ( . 25
- 2. Vessel level (.0b
- 3. Water temperature ( . 25
- b. 1. Increase chutdown cooling flow
- 2. Raise veccel water level
- 3. Une head uprav 4 Startup the RWCLI system
- 5. Startup both CAD pumpn
- c. Fleed through cleanup system and feed through feedwater system.
- 7. Flood the maan s t e a.? lines, and drain thrc, ugh the main steam lino drains if the cleanup system is not available.
i n
(5 required G O.25 each3 (1.25)
REFEF.ENCE
- Ouad C1tiet, OOP 1000-5 Rev 13 nn 2 1 ( 2 05000K-'.0 3 - 3. 9 ) (205000G010-3.21 i
20S0000010 JOSv006;03 . . O :(, s >
i CUESTION 4.04 (1.00)
STATE TWO cont 11 tions requir ed by OAP 300-2 CONDUCT OF 5HIFT OPERATIONS, to use the PULL-TO-LOC) switch position for testing.
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ft__889CEDV665_r.UQ8dSLA_9BU980664_gdgBQgNQX Pcgo 49
- eUD_E99196901G96_G90I696 ANSWER 4.04 (1.00)
Any 2 of the f ollowing 4 0.5 eachl
- 1. It is impractical to modify the equipment or procedure to allow testing in a normal alignment.
- 2. The tett is per a recular procedure.
2
- 3. An operator is evailable to return the switch immediately when the test is completed or af interrupted.
REFERENCE Oued Cattes, OAP 300-2 Rev. 17, pg. b.
(294001K106-3.2) 294001K106 ..(KA's)
DUE3 TION 4.05 (1.00's ,
Ref er t c) t h e- attached Figure 3 the Suppresci -) Chamber Level
- Operattnq Range Curve OAP ~OO-Te to aricwer the following questions.
- a. If Drywell to Suppre=sion Chamber di f f er er.t t al pressure tc 1.0 PSID and Suppressten Chamber level is +1.0 inches, would the Normal Operating Upper Limit be exceeded by normal drywell to torua dp fluctuations? '
- b. If Supprecsson Chamber water level is at +1.0 inches, can Drywell to Torun dp be increased to 1.3 PS!b without e:ceeding the normal operating upper limit?
AN3WER 4.05 (1.00) i
- a. Nc Co.53 l
- b. No (0.53 l l
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.o da__EB9GEDV6ES_:_NQ$d663,@huQEd662_gdh6QEUQ'I Pcgo $v GUD_B69196901G66_G9dIB96 REFERENCE Quad Cities, OAP 300-2 Rev 18, P. 17 (223OO1A211-3.6) (223001G010 -3.2) 223001G010 223001A011 ..(KA's)
OUESTION 4.0o (1.50)
Concerning OOP 207-1, Nem Rod Worth Minimi:er Operations
- a. WHAT indication do,*e the operator have that the RWM computer has . t malfun troned? (0.6)
- b. STATE the TWO possible actions that the operator should take af the l RWM has moliuncti oned. (1.0)
AN5WER 4.06 (1.30)
- e. The tino display it not updatano. [0.53
- b. Trantter to the other RWM CO.53 Feinattalt:o the ttalled kWM to.53
}
REFERENCE Ouad Cittect OOP 207-1 p. 1.
(201006G010-3.1) a 20100eG010 ..(LA*s)
OUESTION 4.07 (1.00)
If the N50 must be relieved for a shert period ot time during hat shift, what intermvtton is he REQUIRED by OAP 300-7, Shift Change for Nuclear Station Operators, to turn over to hit reliet ? l l
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I
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da,_BBQGEQWEEE_ _UQ606LA 6EUQ8d6bi_gdg6Ggggy Page 51
.. .- 6NQ_68Q1QLQ@lGO(_QOUlBQL 1 s l
l ANSWER 4.07 (1.00) 1 1
- 1. Current operational ctatus of the unit. Co.53
- 2. Any information on aeneral plant operations or major events which are anticipated while the N50 is gone. CO.53 l
REFERENCE ,
l Ouad Cities, OAP 300-7 Rev 7 P. 3 (294001 A105-3. 4 ) (294001 A111-3. 3) 294001A111 294001A105 ..tKA*c)
OUESTION 4.08 (1.50)
In accordance wi th OGP 4-1 what specific entry is required in the VERIFIER column of the Centrol Rod Sequence Sheet under each of the following plant conditionce I
- a. Reactor power is less than 2 "'. o f rated an: the Rod Worth Mi ni mi : er is in NOAMAL.
- 6. Reacter peiwer i r- less than 20*4 of rated and the Rod Worth Minimt:er is bypassed.
- c. Reactor power it greater than 20*4 of rated.
l l
AN5WER 4.09 s1.50)
- a. "bwM" C0.53
- b. Independent verifier's initiale Co.53
- c. "NW* Lv.53 l
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1 L___________
de _66QGEQW6E5_ _U9Bd861_0EU9Bd664_Ed560EU91 Pc90 52 ,
+*- 600.60Q1QLQ91G06_G901696 l
REFERENCE i
i i
Quad Cities, QGP 4-1 Rev 4 P. 6 'I' l (294001 A106-3. 4) (20100!G001-3. 6) l 1 294001A106 201003G001 ..(KA's)
{
1 QUESTION 4.09 (2.00) [
i OGA 500-2 prescribes that if fewer than 3 AD3 valves are open l and RPV pressure is at least 50 psig above suppression chamber ,
pressure then rapidly depressurire the RPV using one or more of several systems (e.g., main turbine bypass valves, main steam line I drains, HPCI tu-itne, RCIC turbine, RPV head vent , steam jet air {
ejectors, RWCU). i i
- a. EXPLAIN why RFV pressure is required to be at least 50 psig above suppression chamber preusure prior to performing this !
step. (INCLUDE the significance of this 50 psig value) . ?
I
- b. EXPLAIN why three (3) ADS values are the minimum number required !
for Emergency Depresturication. !
b l
?
t AN5WER 4.09 (0.00) f i
- a. At least 50 psig is needer to keep the relici valves open. I (Emergency depressurination can be considered complete below :
this value). [1.003 l
- b. This is the minimum number required to attain the l depressurination rate needed to maintain peak cladding >
temperature lens than jyed'vegrees F. C1.003 f t ase
- r l k e <
295025A205 2:t900D 4v7 ..(VA*n)
OUESTION 4.10 (2.25)
I For each of the following conditions, determine whether or not emergency l procedure entry is required. If entry in required, STATE WHICH procedure (s) to enter. 1+ NO entry is required, state NONE. (Consider each item separately and assume no additional conditions)
- a. RPV level is 10 incnne l
- b. Roactor powccr is 1.'*4 STARTUP MODE i
j c. ' octor power t r 4 T. ene minute atter load reject
- d. Supprencion pool l e vel is -; inches i l
] +. Lirywell pretsure ic c.5 psig 4 Suppression poci level 1a 13.7 feet I
- g. Reactor building vent exhaust 3.2 mR/hr l h. Renctor shutdown, reactor peousure 10GO psty
- i. Drywell temperature is leu degrees F I
t
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a .
l l ~h._ _ E 69G E QU E E 5_: _U950064_8 E 006066 i _ E d E SQ E UQ 1 Pege 54
- OUD_6991QLQO1Geb_G901696 ANSWER 4.10 (2.25) '
- a. NONE l b. NONE i
- c. OGA 100-1, 100-2, 100-3 (RPV Level , Pressur e, and Power Control Simultaneously)
- d. OGA 200-1, 200-2. 200-T. 200-4 (SP Temp, DW Temp, Pri. Cont. Pruss, and SP 1 t, v e l Simultaneous!y) l
- e. OGA 100-1, 100-2, 100-!. 200-1, 200-2, 200-3, 200-4 (as above Simultaneously) l
- f. OGA 200 block
- g. OGA 300-1, 300-2, 300-T t' S e e Cont. Temp, Rad level, and Water level Simultaneously)
- h. OGA 100-1, 100-2. luo-3 (as aoove Simultaneously)
- i. NONE l (O.25 pts each. al1 pr oc.e-dtir et that require b1multaneous entry must be stated for full credit. +,y ta ta stated as 100 t l oc k , 200 block, etc.)
REFERENCE i
Ottad Citses: OGos. Fntry Con d i t i en ts (295024G011-4.7+) (29502 5G011 -,4. 2 + ) ( 295020G011 -4. 3 + ) ( 295037G011 -4. 4. )
1 l 295037G011 275030GA11 295025G011 295024G011 ..(>Aa) l OUESTION 4.11 (1.00)
As deternbod by CGt. Genrerel Latit i on #5 EAPLAIN when t'ar wa y indicated levelu ar e NOT rel1ablo and WHICH 1ovel i n st r urr en t should be used 1n its place 7
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l l
l
du__EEQcERWEE3_:_U9Bde64_skb960662_EUE59EUGY Paco 55
. edD_809196991G06_G96I696 ANSWER 4.11 (1.00) ;
Yarway level indicated levels are not reliable during rapid RPV depressurizatin below 500 psig CO.$3. For these. conditions, utilize the GEMAC instruments CO.53 to monitor RPV water level.
REFERENCE Ouad Cities, OGA-00 Rev ~. Caution #3 pg 2, and Caution #5 pg 3 (295020G007 3.4)
L 29502BG007 .. u:A*c) l i
I OUESTION 4.12 (1.00) !
The Post Accident C on t ai n ct ent spray procedure. DOP 1000-8, contains a ;
precaution which etates the vacuum breal:ers AO 1601-20A. -20B, -31A, '
end ~31B will open if suppreceion Chamber prersure drops to 0.5 psag below reactor buildir.g atmour.heric pressure. Wnat TWO l al ternati ve- acti ons are r equired i4 noth AD 1."il-20A and -2013 fai1 to cpen? l l
r r
l ANSWER 4.1 :' (1.00) ,
L 1
- 1. Fall instrument air to the valvec. E v . '5 3 r
- 2. 1+ volves do not open after step 1. line up vent path from ;
Suppression Chac,ber through SBGT suction to reactor bu11dino.
c,.53 :
Acon P m n al4yfe.h* gwa s. : Y,' l
- t. & H wp + sa lose. ,,d I,e.k +4a sa.m b ees hus n l c /, s, A ,4 5; 6, . .(.tr ) l 2 . P l a. e
- ecodae N H=4 s ku.4 Aeh ' . . I t_ m, f' f
- c. a a . a . u a, n .y u ~ ,.c. 4 ;
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.~
do__E69GEDWBE3_:_U9606L2_6 hug 606Li_EdESQEUQ1 Pcgo Go
...- BUD _669196901G6L_G90I696 REFERENCE Quad Cities, OOP 1000-8 Rev 5, P.1 (223001G010-3.2)(226001A219-3.5) 226001A219 223001G010 ..OLA'c)
DUESTION 4.13 (1.00)
If drywell pressure (secede 40 prig, the containment is required to be vented in accordance utth CDP 1600-13 Post Accident Venting of Frimary Containment. Why is vtanting the Supprescion Chamber the preferred path for the primary containment vient instead of venting the drywell?
ANSWER 4.13 (1.00)
Venting the contai nmerit through the s up p r ess c i on chamber water provider a decentaminetten factor of up to four ( v e n t i n ,) gassen through the suppret t,i on pool water will result in ci nni f i c. 4ntl y lower r el ear,e raten) (1.03 l
REFEFENCE Ouad Cattes. 00P 1600-13 Rev S. P. 12 t22:001G010-3.2)(295024k307-0.5) 295024>307 22 001G010 . . W4 r) l l
l l
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1
t_ 669GEEVSE5_:_UQBU6b A 6@UQSU66 t EUE6QEUG).' Pago G7
- 6UE_60D196001G06_GQUI696 QUESTION 4.14 (1.50)
Answer the following quettions concerning the Heat Copacity Temperature Limit (HCTL) Graph, OGA 100-F1. See attached Fiqure 4.
- a. Explain the E4asit +or the Heat Capacity Temperature Limit. (1.0)
- b. What action tu required bv the OGAs if Supprension Fool f
temperature cannot tw maintained below the HCTL7 (0,5) r AN5WER 4.14 (1.50) s, . The line on the graph represents the maximum suppression pool temperature at which blowdown of the RPV to the Shutdown Cooling i nt er l ot b: pressure (actuation of ADS)[0.53 w121 not result in unstablu steam condensation at or near the SRV discharge devices. '
CO.53
- b. RFV pretsur+= must be iriaintained below the HCTL. CO.53 REFERENCE Ouad Cities, OGA Lesson Plan LO 7 P. 22 te 37
- (2950
- 3G0L2-3.e+)
1 i
29*<cSG01: ..()A e)
OUESTION 4.15 (1.50)
According t o Procedure UGP 1-2, Unit Startup to Hot Standbv. e couplanc chec) is performed each time a rod reaches position 45. What are T HF;EE acticns you must perform af uncoupling 15 detected during this chect' l
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a* .
.,dt__EEQGEDUEE5_:_U9EdeLi_6EU25066t EdEEEEUGX Pago 59
. GUD_E69106991G66_GQUIEQL oa ANSWER 4.15 (1.50)
Any 3 0 0.5 ea.
- 1. Stop rod withdrawals.
- 2. Notify the shift engineer.
- 3. Refer to the abnormel procedurer.
4 Insert the drive to ita FULL IN position S. Electrically disarm trio dri ve sol enoids.
REFERENCE Duad Cities, Procedure OGP 1-2. PP. 16 (201003A202 0.7)
OUESTION 4.16 (2.00)
Answer the followino quert2ont scroroino to COA 1700-0, Main Steam Line High Radiation, immediate operitor action stec a for High Radiation on both channelt.
- a. What are sin at the automatsc Actiont t o be veritted by "Veri 4y Automstic Actionc ... .
(1.5)
- b. Step 1.c. har the operator place the Off-Gas isolation valve AO-5406 control switch to close. EXPLAIN the BASIS for taking thi s ac ti ori? (0,5) 1 l
4
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4' .
,'Sl__E69GEDUEE5_:_UQSdG6t_GEUQEd8Lx_EUESOEUGY Pcco 07 ONQ_B891QLgG1G86_GQUIBQL ANSWER 4.16 (2.00)
- a. Any 6 0 0.25 ea.I
- 1. Reactor S c r a. '*Ol"4'"*
- 2. MSIV's close h c. ex-p b PdH"P I
- 3. Off-Gas icolation velves cloce ) l; g f f ./.m g (,j
- 4. Air ojector suction valaes c1ose
- b. Mechanical vacuum pump trips 9,
- 6. Main steam Line drains close
- 7. Frimary sample valves close
- b. This will prevent re-opening of the Off-Gas isolation valves CO.25) when the high radiation condition th recet [0.253.
REFERENCE Ouad Cities DOA-1700-5 M51V High Rad Rev 4 pg 1 (270000F101-7.6) (272000K102-3.2)(272000kl08-2. 6) 272000t106 2 7 20006. t u: 27200url01 . 0;A*s)
OUESTION 4.1 '
- 1. m.O 004 201-lu, Reactor Presture Control Using Manual Relief Valve Actuation, prchtbits Octuation of env single relief valve within 10 Hecondt o f t. e r that valve has been closed. Explain why this.
restrictico is imposed (why an actuation inhibit utqnal is generated).
ANSWER 4.17 (1.00)
Wat er it drawn up into the rellei valve discharge line itOm the suppressicn pool as a vacuum in f orir,ed from steam condensation follornrm r el l ei valve clocure. Opening a relief valve shortly after a prestous operation would thus send a slug of water into the s,uppr eew t on pool, resulting in porsible structural damaqe. (1.0) i
(+++++ CATEGORY 4 CONTINUED ON NExT PAGE +++++)
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3- Pcoo oo
1_ES9CEDVEES_:_U960064_0EU9EDOLi_EDEBOEUGY OUD_B89196901G66_G901696 a ,-
, e 7
PEFERENCE Ouad Cities OOA 201-10, p. 2.
(239002K403 3.1) 239002K403 ..(KA's) i l
1 1
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(+++++ END OF CATEGORN 4 +++++)
(**+++++++* END OF EXAMINATION ***+++++++)
.c
, 1 ', .
U. S. NUCLEAR REGULATORY COMMISSION
- SENIOR REACTOR OPERATOR LICENSE EXAMINATION FACILITY: Quad Cities 1&2 REACTOR TYPE: B'dB-QE 3 _
DATE ADMINSTERED: E8/07/19 EXAMINER: EABBISH d u __
CANDIDATE __
LEEIBQCIlQuS_T.Q_CaunlD&IEL Use separate paper for the answers. Write answers on one side only.
Staple question sheet on top of the answer sheets. Points for each question are indicated in parentheses after the question. The passing grade requiA'es at least 70% in each entegory and a final grads of at 1 cast 80%. Examination papers will be picked up six (6) hours after the examination starts.
% OF CATEGORY % OF CANDIDATE'S CATEGORY VALUE_ TOT 6L SCORE VALUE__ CATEGORY
_25.2L__ _25 QD 5. THEORY OF NUCLEAR FOWER FLANT OFERATION, FLUIDS.AND THERMODYNAMICS
_2E 50 _21.2E ___ __
- 6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION
_2hu15 _REuqq _ _
- 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL 2 4.50
_Ci_03 _21&lk _ 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS 100 S'
_ Mire __ _
% Tota 1s Final Grade All work done on this examination is my own. I have neither given nor received aid.
~
Candidate's Signature i
o 5 ,
L_ IBEGELQF NUCLEAR POWER _EL&ELQEEB&Ilh Pcgo 2
, ,ELulREdER_IHEBMQRIEAMLQE QUESTION 5.01 (1.00)
- a. During a rod withdrawal the operator will observe a sudden increase in reactor period initially. This sudden increase is referred to as .
- b. If the reactor were critical on prompt neutrons alone power would increase uncontrollably. This condition is called ANSUER 5.01 (1.00)
- a. Prompt Jump. (.5)
- b. Prompt Criticality. (.5)
REFERENCE Quad Cities: Reactor Theory p. 15
QUESTION 5.02 (1.25)
- a. DEFINE Shutdown Margin. (0.75) i
- b. Insertion of control rods will (Increase / Decrease) the SDM. (0.5)
I ANSWER 5.02 (1.25)
- a. A measure of how suberitical the core is. (0.75)
- b. Increase (0,5) 4
(***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)
,~. .. . _ . . ._ -.
,a.
6m! TtlEQRY OF NUCLEAR POWER _ PLANT OEEBAT.lQtL. Pcco 3 ,
EldllMdllD._IllEBtjQDYNAMIM l
4 REFERENCE Quad Cities: Reactor Theory p. 8, 18.
KA 3.5 3.5 -
201003K508 292002K110 ..(KA's) !
QUESTION 5.03 (1.00)
You have just taken the reactor critical from a cold condition and are I increasing power on an 80 second period. Utilizing control room instrumentation, STATE TWO methods which will tell you the heating range has been reached? Rod position and recirculation flow have l been held constant.
I ANSWER 5.03 (1.00) ;
- 1. Period indication becomes lon r. (0,5) h .**'p*** . .
A se s p+ yerted indies. ee g e l o.9
- 2. Indicated power on SRMs/IRMs is leveling off. (0.5)
Aee<p+ .: Des /sem levet , w +> h / e , ,, , , s , , l REFERENCE Quad Cities: Reactor Theory p. 28. f KA 3.7 3.9 '
l 292008K113 292008K112 ..(KA's) {
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1 I
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a
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f
A. THE0DF NUCLEAR POWER PLANT OPERATION. Pcgo 4
-FLUIDS.AND THERMODYNAMICS QUESTION 5.04 (1.50)
Regarding Minimum Critical Power Ratio,
- a. STATE the fuel failure mechanism that is used to limit 4.he MCPR value,
- b. (TRUE or FALSE) Operation with FLCPR greater than 1.0 is acceptable,
- c. (TRUE or FALSE) For core flows other than rated. MCPR limit must be decreased.
ANSWER 5.04 (1.50)
- a. Fuel cladding cracking due to lack of cooling. (0,5)
- b. False (0,5)
- c. False (0,5)
I.
REFERENCE I
! Quad Cities Technical Specifications. P. 3.5/4.5-14.
1 BWR Thermal Limits Figare 9-5. p. 9-38. 9-39.
j Learning Objectives 5.5. 5.12. 5, 11.
KA 3.6 3.3 3.5 1
i 293009K128 293009K127 293009K120 ..(KA's) !
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3 I i I
) !
i 1
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, . o- . .. . . .
- e Pcge 5
- 5. l THEQBLQE_MQLEAR POWER PLANT __OEEBAT1Qlb.
,,ELMIDS J D_IllEBMQD1BAdl.CS j
i 9
- QUESTION 5.05 (1.00) \
I i, j SELECT the correct statement concerning the operation of a jet pump.
i s l \
! a. The diffuser increases the velocity of the fluid thereby 1
increasing its static head, t i
J b. The nozzle on the jet pump converts the static head of the i i
recirculation pumps to a low velocity jet at high static pressure.
i
- c. The low pressure at the nozzle discharge draws the surrounding i fluid into the jet pump thrsat area.
- d. The constant area of the mixing section maintains the pressure ;
3 Constant. ,
i l
i I
ANSWER 5.05 (1.00) i i
l c (1.0) l t
REFERENCE t Quad Cities: BWR Thermal Hydraulics p. 8.34 I f Learning Objective 8.2 ;
i KA 3.2 2.7 l t
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293004K105 202001K502 ..(KA's) [
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_ . _ _--. _ _ _ _,_ __ . _ , _ _ _ _ _ _ . , _ . _ _ , _ _, .____.__,,,j _
- ' 5 _. THEQRY OF NUCfEAR PO]{ER PLANT QEEBATICL Pego 6
, ELMIDS.AND_.IBEEMQDYNAdlCS d
1 j QUEGTION 5.06 (1.50)
MATCH the definition in Column I with the term in Column 2. [
Column I Column 2 .
- ======== ======== ;
l c. Flow of heat through a body 1. Convection 4 or between bodies in direct .
- 2. Radiation !
contact.
I
- b. Exchange of energy between 3. Conduction ;
bodies through an intervening '
space by electromagnetic waves. t i
- c. Transfer of heat between a :
fluid and a surface by I circulation or mixing of the !
i fluid. t 1
?
ANSWER 5.06 (1.50) I L
i [
s
- c. 3 (0,5)
j b. 2 (0.5) i l
! c. 1 (0.5)
}
i oREFERNCE i
- Quad Cities: Heat Transfer p. 7-5 l i Learning Objective 1.1 1.4. t KA 3.2 [
l !
i i REFERENCE l 233007K101 ..(KA's) ;
i i a i
- i i
. I i !
, I
- i h
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5 TIiEQBLQE _ N UC LEAB_EQ'lEB_Ek&ELQEEB&HQ1L.
Pcgo 7
. ,EkulRLAND THEBMQQHAMIQS QUESTION 5.07 (2.50)
Answer the following concerning Net Positive Suction Head (NPSH)
- a. LIST FOUR parameters which CONTRIBUTE to AVAILABLE NPSH for a recirculation pump. Limit your answer to those parameters which are DIRECTLY indicated in the CONTROL ROOM. (1.0) b Consider TWO Reactor Plant conditions:
Low Power and Low Flow (<10%)
OR High Power and High Flow (>85%).
- 1. During which condition is the REQUIRED NPSH for a recirculation pump greater? (0.5)
- 2. During which condition is AVAILABLE NPSH for a recirculation pump greater and WHY is it creater? (1.0)
ANSWER 5.07 (2.50)
- b. 1. High flow, High power (0.5)
- 2. High flow, High power (0.50), due to the increased inlet subcooling from the increased feedwater flow. [0.50) (1.0)
REFERENCE Quad Cities: LIC-0202-1 p. 24 Learning Objective 11.
KA 3.3 3.4 3.2 3.6 3.2 202001K402 202001K122 202001K119 202001K105 202001K103
..(KA's)
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- - -- - - - - - - - - - - - - - - - ~ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
. n -- -
! 51, Pego 8 TBEQRLQE_HUQLEAR_ POWER _ELMT OPERATIOHu :
, ,ELVIDEdHE_IEEBt10DXHMLCE
- t QUESTION 5.08 (2.00) .
QGA's require that the operators observe NPSH requirements for pumps i
- taking suction from the suppression pool (RHR, Core Spray, HPCI, and -
- RCIC). LIST FOUR effects that would result if cavitation occurred in ,
these pumps.
l !
)
i ;
ANSWER 5.08 (2.00)
I Reduced system flow (0.5) CooC'3 Ine,J . d e. sa c e.
Reduced pump efficiency (0,5)
! Excess vibration (0,5) r
] Impeller damage (0,5) j bp ne's s e i A &c e.p i-h3 N >$* .7 es a .
j REFERENCE Quad Cities: Emergency Operating Procedures (QGA's) p. 00. I j KA 3.2 l i !
i 291004K101 ..(KA's) ;
i i 4
j QUESTION 5.09 (1.50) !
r l With regard to MAPRAT:
a) WHAT is the relationship between MAPRAT and MAPLHGR7 (1.0)
~ {
b) If the MAPLHGR Technical Specification limit is exceeded then fuel '
- failure may occur during WHAT event? (0,5)
(
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.g, Pcgo 9 L. TEQRY. OE_EDLEAB_EQEB_ELANT..OPEBAI1OL ELMDSED_IHEBM2MUAMICS ANS"F.R 5.09 (1.50)
- c. F PRAT is the ratio of APLHGR TO APLHGR Limit OR the ratio of FLHGR(act) to AFLHGR(LCO) (Either answer acceptable for full (1,0) credit.) o /2. re f
- e d Apt p G(t.h gpt pg , .
REFERENCE Quad Cities: BWR Thermal Limits figure 9-5. p. 9.24 Learning Objective 4.3.
KA 3.6 3.5 293009K111 293009K112 ..(KA's)
QUESTION 5.10 (2.00)
The level / power control contingency in the QGA's requires that reactor water level be lowered to control power. This is done to reduce the natural circulation,
- a. Briefly DESCRIEE how reducing level reduces natural circulation.
- b. Briefly DESCRISE how reducing natural circulation lowers power.
AMSWER 5.10 (2.00)
- a. The driving head is dependent on height (0.5)(and difference in density). Lowering the level decreases the driving head (0,5).
- b. Increased voiding occurs (0,5) which adds negative reactivity to reduce reactor power (0.5)
(***** CATEGORY 5 CONTINUEL ON NEXT FAGE *****)
. +. .
- s
- 5. THEQRLQF NUCLEAR POWER _ELANT OPERATIQL Pcco 10 !
- ELillDS AND THEMQD1HMiqE ;
REFERENCE l l
5 Quad Cities: Emergency Operating Procedures (QGA's) p. 125. j Learning Objective 6. i Quad Cities: BWR Thermal Hydraulics p. 8-53 and 8-54.
i Learning Objective 10.5
! Quad Cities: Reactor Theory p. 30. !
! KA 4.5 3.1 3.1 l E
l 293008K134 295037K209 295037K303 ..(KA's) {
! QUESTION 5.11 (1.50) (
i '
] Reactor power has been reduced to 75% power from 100% power following :
1 5 days at 100%. Recirculation flow is then held constant and no rod i 2 motion occurs. !
- a. EXPLAIN why reactor power continues to decrease for the next 4-6 hours. (1,0) t I
- b. If recirculation flow is held constant and no rod motion occurs ,
j will reactor power be HIGHER THAN 75%, LOWER THAN 75%, or 75% power l
< in 3 days? (Assume fuel burnup is negligible) (0.5) t
! i ANSWER 5.11 (1.50) (
) .
I a. A decrease in the burnup term occurs ( 25) and iodine from the 100% !
concentration decays to xenon (.25) results in an increase in xenon l
! concentration (.25) which adds negative reactivity (.25). l, t
f b. Greater than 75%. (.5) 1 I
1 1
I !
I 1 l J
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5 __ THEQRl_QE_HUCLEAB_EQWER_ELAELQEERATIONu Fcga 11
, ,ELulDadt!E_IHERtiQRYHatiLCE REFERENCE Quad Cities: Reactor Theory p. 24 Learning Objective 10.
QUESTION 5.12 (2.00)
The reactor is operating at 75% power. The reactor operator withdraws o control rod one notch,
- c. WHAT limits the rate of power change (period)? (0,5)
- b. If the operator inserts the same rod to its original position (in one notch). EXPLAIN why power will decrease slower than it increased when the rod was withdrawn. (1.0)
S HoRT ER.
- c. WOULD the period be CEEATEh at the BOL or at EOL for the rod withdrawal? (0,5) 1 ANSWER 5.12 (2.00)
- o. Delayed neutrons (0.5) ,
- b. Because the power cown transient is limited by decay of the long-lived delayed neutron precursors (.5) whereas, the power up l transient is dependent on prompt neutrons (.25) and short-lived i delay neutron precursors. (,25)
- c. EOL (0,5) :
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t
.s ' .' Pogo 12 S.. THEORY 0F NQCLEAR POWER PLANT OPERATION, l l
, ,ELQIDS. AND THEStjQQDiAtiLCE i REFERENCE !
Quad Cities: Reactor Theory p. 13-15.
Learning Objective 6 ;
KA 3.7 3.2 1 r
I 292008K119 292003K106 ..(KA's) {
i t
QUESTION 5.13 (1.50)
Concerning control rods. . j
- a. A shallow control rod is defined as a control rod between notches I and _. (0.5) {
- b. Briefly DESCRIBE the effect movement of a shallow control rod has ;
on axial and radial power. (1,0) ;
i I
1 ANSWER 5.13 (1.50) f
- a. 36 (accept 32 to 40) (.25) and 48 (.25)
- b. Due to high rod density (.25) (in the region of the rod) radial response is limited ( 25). Due to the low void content (.25) a i larse change in axial power will occur ( 25) I t
I REFERENCE l Quad Cities: Reactor Theory p. 20 '
Learning Objective 9.
l KA 3.3 ,
l l
20100$K502 ..(KA's) l I
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.v 1- -
Pcgo 13 L.__IBERRLQE_EME68_EQEEB_ELAELQEEBAIl08u
, ,ELEIDSdND_IllEBt10Dniat11CS QUESTION 5.14 (1.00)
SELECT the ONE correct answer. As a suberitical reactor nears criticality, the length of time to reach equilibrium count rate after an insertion of equal positive reactivity:
- a. IS THE SAME as the length of time required to reach equilibrium count rate after an equal insertion of negative reactivity,
- b. INCREASES, primarily because of the increased population of delayed neutrons present in the core with no increase in prompt neutrons.
- c. DECREASES, because the source neutrons are becoming less important in relation to the total neutron population.
- d. INCREASES. because of a larger number of neutron life cycler required to reach equilibrium.
ANSWER 5.14 (1.00)
- d. (1.0)
REFERENCE GE Student Text, LIC-THEO, REACTOR THEORY, Rev. 2 Figure 46.
Learning Objective 4.
KA 4.3 292008K105 ..(KA's) l i
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L _'1HEQBY_ OF_ NUCLE &B EQMER_Ek&ELQEEB&T1Qth. Poco 14
, ELQLDSdtID THERMQQXH&tilCS QUESTION 5.15 (1.00)
SELECT the statenent that correctly describes controlling heatup rate,
- c. If xenon c>ncentration is increasing less rod motion is required '
to maintain a constant hoatup rate. l l
- b. Once a heatup rate is established no subsequent rod motion is ;
required to maintain the heatup rate.
I
- c. Reactor power must be continuously increased in order to [
maintain a constant heatup rate. ;
- d. As auxiliary steam loads are put in service more rod motion is )
l required to maintain a constant heatup rate.
l ANSUER 5.15 (1.00) f I
d (1.0) l Als o ac c ep + e os ac.etree) new l i
REFERENCE Quad Cities: Reactor Theory ) 28 KA 3.7 i
I 292008K116 ..(KA's)
QUESTION 5.16 (1.00) ,
During a rea' tor startup from cold ahutdown conditions the reactor has just gons critical; STATE TWO indications of criticality. INCLUDE the neutron monttoring instrumonts on which the indications are observed.
1 P
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E d liEQBY OF NUCLE 68_EQHEB PLANT QEERATION. Pega 15 ELulDEdHD_IHEEtiQDYNAMLCE ANS!?ER 5.16 (1.00)
With m; further rod motion, period remains positive (0.25) on the source range pe: -i meter (0.25). Neutron level continues to increase (0.25) on 1 SRM (IRM) (0.25).
REFERENCE Quad Cities: Reactor Theory, P. 27. and QGP 1-1, page 4 KA 3.9 4.2 292008K106 29008K107 ..(KA's)
QUESTION 5.17 (1.00) i Which one of the followinu Parameter changes. (1, 2, or 3 below) would result in:
- a. The LARGEST insertion of reactivity.
)
- b. The SMALLEST insertion of reactivity.
Consider only the magnitude of the change. Do not be concerned with whether the change is positive or negative.
PARAMETER CHANGES
- 1. a 1 F change in fuel temperature.
- 2. a 1 F change in moderator temperature.
- 3. a 1 % change in voids, i
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- 6. THEQBY OF NUCLEAR POWEB PLANT OPERATION. Pega 16
- , , FLUIDS. AND THEBMQQYNAMM ANSWER 5.17 (1.00)
- a. 3 (.5)
- b. 1 (.5)
REFERENCE l Quad Cities: Reactor Theory figure 46.
Learning Objective 7.
- KA 3.3 I
292004K114 ..(KA's) i J
QUESTION 5.18 (1.00)
LIST TWO reasons for adding a burnable poison to the core.
1 ANSWER 5.18 (1.00) ,
Allow more fuel to be loaded without increasing the number of control rods. (0.5) 4 ,
, Facilitate axial power shape control. (0.5) (Accept limits flux peaking and simiplifies control rod pattern at .25 each) l REFERENCE Quad Cities: Reactor Theory p. 25. :
KA 3.1 .
i l 1 292007K101 ..(KA's) '
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8.. PLANT SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION Pego 17 QUESTION 6.01 (2.00)
Concerning the off-gas radiation monitoring system.
- o. If one channel is failed downscale, STATE TWO condition (s) required for an isolation to occur?
- b. STATE THREE automatic actions that will occur on an isolation?
ANSWER 6.01 (2.00)
- a. An upscale on the other channel (.5) and the 15 minute timer timed out. (.5)
- b. The off-gas chimney isolation valve closes (5406) (.5)
The off-gas line drain valve closes (5408) (.25)
The off-gas pressurized drain tank is isolated from the pressurized drain pump. (,25)
(%CV S434) 1 REFERENCE 1
Quad Cities: Process Radiation LIC-1700 p. 12.
TPO-5 '
)
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o .
Pago 18 LANI._EXEIEME_QEEIGN. CONTROL. AHD_lREIRQHENTATION QUESTION 6.02 (1.50)
Due to control room abandonment, it is desired to operate the Safe Shutdown System outside the control room. ANSWER each to the following 2estions as either TRUE or FALSE,
- a. Control of the Make-up Pump must be transferred to the Safe Shutdown Room prior to leav).g the control room.
- b. An interlock prevents the centrifugal Make-up Pump from starting without a discharge path,
- c. Closure of the Flow Control Valve (MO 1/2-2901-6) will cause the make-up pump to trip.
ANSWER 6.02 (1.50)
- a. False (0.5) (It is transferred in the safe shutdown room)
- b. True (0,5)
- c. True (0.5)
REFERENCE Quad Cities: Safe Shutdown System LIC-2900 pp. 4 and 6.
TPO-4.
KA 4.5 3.9 3.9 3.4 1
295009G007 295009G006 295031G006 295016K201 ..(KA's) l i
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- 8. PLANT SYSIEMS. DESIGN. CONTROL . AND._IBS.IBIldENTATION Paga 19 QUESTION 6.03 (3.00)
The reactor is at 50% power with the load limit set at 65% and Maximum combined flow limiter at 115%. Recirculation Master Controller '.s in Manual. An electrical failure occurs that causes the pressure set signal to decrease 10 psi.
DETERMINE the final control valve flow rate and bypass valve flow rate in percent of rated. Refer to the attached Figure 1, Electro-Hydraulic Control Logic, DESCRIBE how you determined your answer.
/.NSWER 6.03 (3.00)
Output from pressure summer A increases to 25 psi (. )s. The HVG passes this signal to the Pressure / Flow converter (.7)'T p e Pressure / Flow converter output will increase to 82-83% (T. . ) (Accept 75 to 90%).y The load limit will limit the signal to the governor valves t 65% (, ). Total flow is less than the maximum combined limiter
( '. ) so t o by ass valves will open to pass 17-18% flow (.g,),(Accept e s g u ,. g_, gae,,,g,, .),
"# ' go 2 5% ) . I r a. c. k .
10 ,, s s a , ,
S e f M ai e 4 fr /0 f r 3* (. 33) , 13 , g.gs,, , g, p/v,g g J //
f /f ' 5 5 "' #- 7 / da b e 5 W// / Ma IA /4,'4 g 84 Wa A , 4 REFERENCE & htH *Af t is ,o y e s u ,~ g (,5 Q ,
Quad Cities: EHC Pressure Control & Logic LIC-5650 pp. 6, 7, 8, 9, 17, l
- 18. Figure 6. TPO 5, 7, 14.
KA 3.7 4.1 3.7 1
241000K308 241000/.306 241000K305 ..(KA's) ;
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Page 20 6.. l PLANT SYSTEMS DESIGN, CONTROL, AND INSidUMENTATION QUESTION 6.04 (3.00)
Unit 1 Diesel Generator auto starts. After running for two minutes the diesel trips. Unit 1/2 Diesel Generator did not start.
- a. LIST FOUR possible causes for Unit 1 Diesel Generator auto starting. (2.0)
- b. LIST TWO possible causes for the Diesel Generator tripping. (1.0)
ANSWER 6.04 (3.00)
- a. Undervoltage on Bus 14-1 (.5)
Backup undervoltage on Bus 14-1 (.5)
Undervoltage on Bus 14 (.5) 9/ ,jt 'g ,, ,/f, 4
Both ty hfeed Il f{br<.akers
< d b e copen to Bus a be r- ep w14. (.5) Ace tf j **$
- b. Overspeed (.5)
Differential Overcurrent (.5)
REFEREtiCE Quad Cities: Diesel Gen. LIC-6600 p. 44 and 46.
TFO-4 and 5.
KA 4.2 3.7 264000K408 264000K402 ..(KA's)
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- 8. PLABI_SYSIEMS DESIGN. CONTBQL2_AND_ INSTRUMENTATION Page 21 '
a QUESTION 6.05 (1.00)
DESCRIBE the response of the 1A Reactor Recirculation pump and MG set for the condition stated below. INCLUDE the cause for the response.
The Recirculation Master controller is in manual at minimum. 1B Reactor Recirculation pump is at 45% with its MA Transfer i i station in manual. The 1A Reactor Recirculation pump is then started with its MA Transfer station in Automatic.
1 ANSWER 6.05 (1.00)
The pump will speed up to 45% (0.5) when its discharge valve goes >
90% open. (0.5) ,
REFERENCE Quad Cities: Recirculation Flow Control System LIC-0202-2 p. 4.
Figure 5.
TPO-4, 8.
KA 3.0 202002K402 ..(KA's) 3 l QUESTION 6.06 (2.50) t 1
- a. The mode switch is in startup with reactor pressure equal to 800 psig when an automatic MSIV isolation occurs. LIST the i possible signals that could have caused the isolation. 1 (Include setpoints) (2.0)
- b. flRUE or FALSE) Reactor power is 30% when a MSIV isolation occurs.
- a scram will occur if MSIVs close in only two Main Steam lines.
(0.5) 4 j (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
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- k. PLANT SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION _ Pcgo 22 ANSWER 6.06 (2.50)
- c. High Steam Line flow 140% of rated in a steam line Low reactor vessel level -59 inches Steam Tunnel High temperature 200 F MSL High Radiation )1/x NFPBG (2.0)(.25 for each signal and .25 for each setpoint)
- b. False (0.5)
REFERENCE Quad Cities: Main Steam Line System LIC-0250-1 p. 28 TPO-8 Quad Cities: Reactor Protection System LIC-0500-1 p. 24 TPO-7 l
KA 4.1 3.8 239001K401 239001K127 ..(KA's)
QUESTION 6.07 (2.00)
Concerning operat$on of the Automatic Depressurisation System (ADS),
- a. Reactor water level is -59 inches and slowly lowering. Drywell pressure is 2.5 psig and slowly increasing. RHR and CS pumps '
are running with discharge pressure > 100 psig. ADS valves should open in ___.
- b. Reactor water level is -59 incites and slowly lowering. Drywell pressure is 1.5 psig and constant. One RHR pump is operating with a discharge pressure of >100 psig. ADS valves will should open in
- c. (TRUE or FALSE) An ADS blowcown is in progress. Placing the ;
Auto Blowdown Inhibit switch to Inhibit will stop the blowdown. ;
i
- d. (TRUE or FALSE) An ADS blowdown is in progress. Operating the DRYWELL PRESS RESET switch will stop the blowdown. .
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i 1
N. ?LANT SYSTEMS DEEIGN. CONTROL. AND INSIBUMENTATI0tl Peso 23 ANSWER 6.07 (2.00) c.:110 see (0.5) ,
- b. 8.5 minutes (0.5) I
- c. True (0.5) ,
- d. False-(0,5)
REFERENCE I'
Quad Cities: Automatic Pressure Relief System p. 3 and 5. Figure 1.
TPO-5 and 6. .
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218000K403 ..(KA's) 1 l
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l 8. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION Pega 24 1
l QUESTION 6.08 (3.00) l For each condition listed in column I below SELECT the action (s) listed in Column II that will occur.
STATE if no action will occur.
Column I Column II i
================== ============
- 1. IRM 'A' Detector will
- a. A reactor startup is in progress with IRMs on not withdraw, range 2. The operator withdrawing SRM detectors 2. A scram signal will be also has IRM channel A generated.
detector selected.
- 3. A rod block is generated,
- b. The operator adjusts recire flow such that there is a 4. No action occurs.
[ 15% mismatch between loops.
l l c. Reactor is in the RUN mode and an APRM fails downscale.
All IRM are withdrawn and indicating 25 on range 3.
- d. Reactor is in startup mode and excessive feedwater flow causes power to increase to 15%.
- o. An approach to criticality begins with IRM C on range 2.
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'6. PLANT _SYSIEUS DESIGN. CONTROL. AND INSTRUMENTATIOH- Pcga 25 l ANSWER 6.08 (3.00)
- e. 3 (.5)
- b. 4 (.5)
- c. 3 (.5) ,
- d. 2 (.5) and 3 (.5) l
- o. 3 05)
( ( @ .5 each)
REFERENCE Quad Cities: Intermediate Range Monitor System LIC-0700-2 p. 13.
TPO-4.
Quad Cities: Average Power Range Monitor System LIC-0700-4 p. 8 and 9.
TPO-6.
]
KA 3.7 3.7 4.2 215005K402 215005K401 215003K401 ..(KA's)
! QUESTION 6.09 (1.00)
With the 1/2 Diesel Generator Keylock switch in the following positions,
, DESCRIBE what happens if an ECCS initiation occurs in both units simultaneously, (i.e., what breakers change position and what will the D/G output do if a loss of normal power occurs?)
i a. Unit 1 - OFF and Unit 2 - OFF I ;
- b. Unit 1 - ON and Unit 2 - ON l
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E. PLANT SYSTEMS DEElGHu_ CONTROL. AND INSTRUMEHI&IIQH Pegs 26 ANSWER 6.09 (1.00)
- s. Both buses (13-1) and (23-1) deenergize. (0,5) (will give 1/2 credit for diesels start and run unloaded)
- b. The first unit to experience LNP energizes. (0.5)
REFERENCE Quad Cities: Diesel Generator LIC-6600, TPO 7 KA 4.1 3.5 264000K506 264000K101 ..(KA's) l QUESTION 6.10 (1.50)
A leak develops which results in depressurization of the reactor at a rate of 30 psi per minute. HPCI maintains reactor water level but drywell pressure increases to 3.2 psig.
- a. At WHAT reactor pressure will the Core Spray inboard injection valve open. ,
t
- b. At WHAT flow rate will the Core Spray minimum flow valve close.
- c. DESCRIBE how the operator can control the amount of Core Spray flow to the vessel. !
ANSWER 6.10 (1.50)
- a. 325 psig (0.5) (Accept 300 to 350) l 1 b. 700 gpm (0.5) (Accept 650 to 750) l l
- c. By throttling the Inboard Injection Valve (if) (0.5) l 1
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. - - - s . . . . , ,
C'..-[P,L'ANTSYSTEMSDESIGN, CONTROL,ANDINSTRUMENTATION Pcgo 27 REFERENCE Quad Cities: Core Spray LIC-1400 p. 5 and 6. TPO-7.
KA 4.0 3.6 209001A411 209001K408 ..(KA's)
QUESTION 6.11 (2.00)
One of two operating reactor feedwater pumps trip but the standby pump fails to start. LIST FOUR possible causes for the standby pump failing to start. Setpoints are not required.
ANSWER 6.11 (2.00)
- 1. The standby pump is not selected to standby.
2.
CacLh prc ; r; _ m..l_,2 te.
- 3. No ventilation fans running.
- 4. Lube oil pressure. (Also accept the auxiliary lube oil pump fails Yub e se.e Nor~ Sted punt was +r
- ppd a, M m fn ( s w oYe$ .
(2.0) (0, each)
REFERENCE Quad Cities: Feed and Condensate LIC-3200, 3300 p. 24. TFO-4.
KA 4.0 3.5 1
259001A301 259001K401 ..(KA's)
QUESTION 6.12 (3.00)
- a. LIST FIVE signals that will cause an automatic start of the SBGT train that is selected to_ PRIMARY. (Include Setpoints) (2.5)
- b. WHAT will cause an automatic start of the the SBGT train that is selected to STANDBY. (Include Setpoints) (0,5) ;
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Pego 28 bNLAHI_EYEIEMS_DEELQN. COEIROL. AND_ IEEIBUMENTAT10E ANSWER 6.12' (3.00)
- c. Low Reactor kater Level (+ 8 inches)
High Drywell Pressure (+2.5 psig)
High Reactor Building Ventilation Exhaust Radiation (3 mr/hr)
High Refuel Floor Radiation (100 mr/hr) '
High Drywell Radiation (100 R/hr)
(.25 each signal and .25 for each setpoint) (2.5)
- b. Failure of the Primary Train to start (.25) within 25 seconds (.25)
A c. c. +p f
- Low 4 low ' n & T r's %<
i Te c k "
REFERENCE Quad Cities: SBGT LIC-7500 p. 10 and 12. TPO 9, 10.
KA 3.8 261000K401 ..(KA's) l l
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1 1
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b 'NBQ M D M E - NOBti&L. ABRQBli&L. EMERGENCY Paco 29'
&HD RADIOLOGICAL CONTROL QUESTION 7.01 (1.50)
Concerning operation of Drywell Sprays.
- a. (Fill in the blanks) Initiate drywell sprays only if drywell pressure is above (1) and drywell temperature is below (2) . (1.0)
- b. (TRUE or FALSE) If drywell spray is required then both loops of RHR should be used in order to obtain maximum cooling possible. (0,5) ,
i.
ANSWER 7.01 (1.50)
- a. 1, 5 psig (0,5) (Accept 5 to 6 psig)
- 2. 340 F (0.5) (Accept 310 to 340 F)
- b. False (0,5)
REFERENCE -
Quad Cities: QOP-1000-8 pg. 2 KA 3.4 l
l 226001G010 ..(KA's) l
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- 7. NRQCEDUBES-NORMAL. AREQBtialu._EtiERGENCY- Pass 30
, ,ARD_.B6DIOLOGICAk CONTRQL QUESTION 7.02 (1.50)
Concerning operation of the RWCU system,
- c. If reactor water temperature is less than or equal to 212 F, then the maximum flow rate for a clean-up recire pump is _ .
(0.5)
- b. If the reactor water temperature is greater than 212 F, then the maximum flow rate for a clean-up recirc pump is .
(0.5)
- c. Clean-up recirc pump discharge must be at least' greater than reactor pressure. (0.5)
ANSWER 7.02 (1.50)
- a. 130 gpm (0,5) (Accept 120 to 130 gpm)
- b. 200 gpm (0.5) (Accept 180 to 200 gpm)
- c. 140 psi (0.5) (Accept 140 to 155 psi)
REFERENCE Quad Cities: QOP 1200-12 pg 1 and 2.
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- t. ESQCEDUEES_ . NORMAL d HEQBli&L EMERGENCY Page 31 l 1 AMD RADIQLQGLCAL_QQHIRQL 1
i QUESTION 7.03 (1.75) i Ground detection of 125 V DC system requires that switches be !
operated. For each color of switch listel in Column I SELECT the !
person (s) in Column II who must grant permission in order to operate .
the switch. !
f Column 1 Column II
================== =============================== t i
.! a. Yellow switch 1. Operating Engineer
! b. Green switch 2. Shift Engineer i 1
.\
1 c. Red switch 3. Chicago Load Dispatcher i
! 4. Rockford Load Dispatcher i
i' ANSWER 7.03 (1.75) {
] a. 1. Operating Engineer (.25' 1 2. Snift Engineer ( 25) l
- b. 2. Shift Engineer (.25) !
I 1
- c. 1. Operating Engineer (.25)
- 2. Shift Engineer (.25) !
- 3. Chicago Load Dispatcher (.25) !
- 4. Rockford Load Dispatcher (.25) !
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! REFERENCE f i Quad Cities: QOP-6900-6 p. 1 :
KA 3.6 3.5 3.2 i
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.I' Y. PROCEDUEES - NORMAL. ABBQElML. EMEE9EEGY Pega 32
,ABD_ BAD 1QLQGIEAL_COBIEDL QUESTION 7.04 (2.50)
! Reactor power is 90%. The operator notices that power is increasing cnd feedwater temperature is decreasing due to loss of multiple feedwater heaters,
- n. Reactor recirculation flow thould be reduced by at least
. (0.5)
- b. (TRUE or FALSE) Control rods that are inserted should only be inserted to their insert limit as specified in the sequence. (0,5) i c. Insertion of control rods should continue until what condition is met. (0.5)
- d. DESCRIBE why a scram due to Hi Hi APRM may occur if power is reduced only by reduction of recire flow and is NOT reduced by insertion of control rods. (1.0) l ANSWER 7.04 (2.50) l
,' a. 20% speed (0.5) (Accept 20 to 25% speed)
- b. False (0,5)
- c. Power is below the 100% FCL. (0.5)
- d. Distance between the power line and APRM scram line increases only slightly as flow is decreased (1.0)
REFERENCE Quad Cities: QGP 3-1 pg. 5 and 6.
Quad Cities: QGA 3500-1 p 2.
KA 3.9 4.1 3.9 3.7 3.5 l;
292008K127 292008K126 295014G010 295014K301 295014K207
..(KA's) s I
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o f,' 'ESQQEQQBES .NQBMAL. ABEQBtMLuEtiERGEdg1 Pcga 33 AND_.BAQIOLOGICAL CONTRQL l QUESTION 7.05 (3.00)
For each set of conditions below STATE which QGA'(s) would be entered.
STATE if NO QGA would be entered.
- a. A loss of drywell cooling occurs. Operators are able to maintain
! drywell pressure less than 2.0 psig by venting. Drywell temperature has increased to 170 F.
l
- b. A turbine trip occurs and the bypass valves fail to open. SRV's open to control reactor pressure. Suppression pool temperature increases to 100 F.
I c. A steam leak has occurred in the drywell which cause drywell pressure to increase to 3.2 psig.
- d. A HPCI surveillance causes suppression pool temperature to increase I to 98 F.
I
- e. A scram occurs due to improper testing by Instrumentation Technicians. Level decreases to -10 inches but is recovered to 35 inches by RFPs.
- f. An isolation of Reactor Building ventilation has occurred due to Reactor Building Exhaust high radiation.
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- 1. YROCEDURES - HQRMAL AREQBMAL, EMERGENQ1 Pcss 34 AND RADlQLOGICAL CONTROk ANSWER 7.05 (3.00)
- e. None (0,5) ,
- b. QGA 100 (Reactor Pressure Vessel) (0.25) :
QGA 200 (Primary Containment) (0.25)
- c. QGA 100 (Reactor _ Pressure Vessel) (0.25)
QGA 200 (Primary Containment) (0.25) ,
- d. QGA 200 (Primary Containment) (0,5) ;
l o. QGA 100 (Reactor Pressure Vessel) (0,5) jl f. QGA 300 (Secondary Containment Control) (0.5)
Note: If the candidates list an individual section, i.e. QGA 100-1, then all sections of that QGA block must be listed, i.e. QGA 100-1, QGA 100-2, QGA 100-3.
i REFERENCE I Quad Cities: QGA 100-1 p. 1, QGA 200-1 p. 1, QGA 300-1 p. 1.
j KA 4.5 4.3 4.6 4.4 4.6 4.3 4.5 4.3 I
i 295007G011 295006G011 295034G011 295031G011 295028G011 295026G011 295025G011 295024G011 ..(KA's) i 1 !
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- 7. ESQCEDEBEE - NORhiALu_AREQ8tiAL. EMERGEEGY Pcgo 35
..AHD RADIQLOGICAL..CONTRQL-QUESTION 7.06 (3.00)
For each statement listed below from the QGA's DESCRIBE the basis for i the SUPPRESSION POOL LEVEL that is listed in the statement.
INCLUDE both the negative effect of failing to comply with the instruction and why the suppression pool level that is stated is limiting.
- n. From Emergency Depressurication QGA "IF suppression pool level is above 5.0 feet, then open all ADS valves."
l i
- b. From Suppression Pool Level Control "If Suppression Pool level is above 18.0 feet, Then (1) If Drywell Sprays are not operating, then do not initiate drywell sprays."
- c. From Suppression Pool Level Control "When Suppression Pool water level exceeds 30.0 feet, then irrespective of whether adequate .
core cooling is assured, terminate injection into the RPV from sources external to the primary containment."
I <
l l ANSWER 7.06 (3.00)
- a. Assure steam will not be discharged directly in to airspace. (0.5)
ADS discharges are uncovered below 5.0 feet. (0.5)
{
i b. May result in a breach of primary containment integrity. (0.5) 18 feet is the level of the vacuum breakers. (0,5)
- c. Maintain structural integrity of the containment due to the ,
unknown head of water when > 30 feet. (0.5) ,
30 feet is the maximum instrumented Suppression Pool water level.
(0.5)
REFERENCE ,
I Quad Cities: Emergency Operating Procedures p. 67, 68, 69, 96, 97 i Learning Objective 6. i KA 3.7 3.3 3.5 3.9 4.1 3.8 4.1 3.9 !
295030G007 295030K301 295030K207 295030K103 295029G007 i 295029K206 295029K205 295029K101 ..(KA's) !
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PROQEDUBES - NORMAL. ABBDBMAIu_EMEBGENCY Pege 36 1
. .ABILEADl9 LOGICAL CONTBQL QUESTION 7.07 (1.00) ,
l
.<ef er to the attached Figure 2 The Suppression Chamber Level ,
Operating Curve QAP 300-T6 to answer the following questions,
- s. If Drywell to Suppression Chamber differential pressure is 1.0 paid ;
and Suppression Chamber level is +1.0 inches, would the Normal !
Operating Upper Limit be exceed by normal drywell to torus dp !
fluctuations? ,
- b. If Suppression Chamber water level is at + 1.0 inches, can Drywell t to Torus dp be increased to 1.3 psid without exceeding the normal operating upper limit? s t
ANSL'ER 7.07 (1.00) i l
- a. No (0.5)
- b. No (0.5)
REFERENCE 1
Quad Cities: QAP 300-2 p. 17.
1 KA 2.8 3.6 l
223001G010 223001A211 ..(KA's) !
l QUESTION 7.08 (1.50) j l
l Concerning QOP 207-1. New Rod Worth Minimizer Operation: i l
4 a. WHAT indication does the operator have that the RWM computer has !
malfunctioned? (0.5) '
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- b. STATE the TWO possible actions that the operator should take if the !
RWM has malfunctioned. (1.0) !
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17'...PR'CEDURESL-O NORMAL, ABNORMAL, EMERGENCY Pega 37 i
AND RADIOLOGICAL CONTROL ANSWER 7.08 (1.50)
- a. The time display is not updating. (0.5)
- b. Transfer to the other RWM (0.5)
Reinitialice the stalled RWM (0,5)
REFERENCE Quad Cities: QOP 207-1 p. 1.
QUESTION 7.09 (2.00)
A single recirculation flow controller has failed high,
- s. The operator is required to adjust the pump speed to insure that speed mismatch requirements are met. STATE the speed mismatch requirements. (1.0) j b. If the mismatch requirements cannot be complied with WHAT action (s) i are required to be taken? (0.5)
! c. WHAT is the basis for the pump speed misinatch limits? (0,5)
I
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ANSUER 7.09 (2.00)
- a. > 80% - 10% speed (0,5)
< 80% - 15% speed (0.5)
- b. Trip the malfunctioning pump (0.5)
- c. Prevent incorrect selection of a loop by LPCI loop selection. (0.5)
- Also o uer+ n % es s. .g.1,a ', d used. eiyeski n e+ d e. loat.n j 5 Pud a=A Tu-p rines "
! (***** CATEGORY 7 CONTINUED ON NEXT PAGE *****)
4
7, EBQGEDMS . . NQBt1AL. ABNORMAL. _EMEGENCY Poca 38 At!D_BADIOLOGICAL CONTROL l I REFERENCE Quad Cities: QOA 202-2 p. 1. Technical Specifications 3.6/4.6-24.
KA 3.2 3.3 3.7 3.5 202002G014 202002G006 202002G010 202002A204 ..(KA's) i QUESTION 7.10 (1.50)
. Concerning operation of safety valves:
- a. A relief valve should NOT be reopened for at least _ >
after it has been closed. (0,5) l b. EXPLAIN the basis for time restriction that is imposed on
- reopenning the relief valve. < (1.0)
ANSWER 7.10 (1.50) !
1 i
- a. 10 seconds (0.5)
- b. Water is drawn up into the relief valve discharge line from the suppression pool as a vacuum is formed from steam condensation following relief valve closure. Opening a relief valve shortly after a previous operation would thus send a slug of water into
, the suppression pool, resulting in possible structural damage. (1.0) ,
l REFERENCE I
Quad Cities: QOA 201-2 p. 2. QOA 201-10, p. 2. )
1 KA 3.4 i
> \
j 239002G010 ..(KA's) !
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Pago 39 7 .- EBEE MBES - NOBUAL__6HEQBM&b._EMEBGE G1
,ARD_BADIOLOGICAL CONTRQL QUESTION 7.11 (2.50) ,
Continuous rod withdrawal should only be used under certain conditions, f i
- a. STATE THREE conditions when use IS PERMITTED. (1.5) ,
- b. STATE TWO conditions when use is specifically PROHIBITED. (1.0) ;
ANS'JER 7.11 (2.50)
- a. 1. During startup ;
- 2. Timing CRDs
- 3. (CRD Friction Testing)
- 4. Emergency situations '
(Any 3 0 0.5 pts each) (1.5)
- b. Shutdown margin demonstration between notches 04 & 12 on arrays 3 & 4 00 to 24 beyond 50% rod density, until one bypass valve is open. t (Alternate wording accepted)
I (Any 2 G .5 pts each) (1.0) t REFERENCE P
Quad Cities: QOP 280-1, page 3 and QGP 1-1, page 4 KA 3.8 3.9 t 201002G010 201002G001 ..(KA's) i l
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F. EBOCEDUBES - NOBMAL... ABNORMAL. EMEEGEHGX Page 40
. ,AND RAD 10 LOGICAL _.CDEIEQL F
i QUESTION 7.12 (2.00)
QGA 500-2 prescribes that if fewer than 3 ADS valves are open and RPV pressure is at least 50 psig above suppression chamber pressure then ,
rapidly depressurise the RPV using one or more of several systems
- (e.g., main turbine bypass valves, main steam line drains, HPCI turbine, RCIC turbine, RPV head vent , steam jet air ejectors, RWCU).
- a. EXPLAIN why RPV pressure is required to be at least 50 psig i above suppression chamber pressure prior to performing this step. (INCLUDE the significance of this 50 p>2ig value).
1 b. EXPLAIN why THREE ADS values are the minimum number required 4
for Emergency Depressurization. {
l 1
ANSWER 7.12 (2.00) ,
l I
- a. At least 50 psig is needeo *,o keep the relief valves open.
(Emergency depressuricatie- can be considered complete below this value). (1.0)
I b. This is the minimum number sequired to attain the 1
depressurization rate needed so maintain peak cladding j temperature less than LL&7 degrees F. (1.0) i Esco o '
REFERENCE Ace *ft oJa de core c e c hq 'n
, l 'a e w e4 Ni^N ,
p a s k. ,,\ m &h',5 9 %p ,, ,y ,, g,,, 4. .pgoo o p ", [
QGA 500-2 EMERGENCY REACTOR PRESSURE VESSEL (RPV) DEPRESSURIZATION. '
Rev. 1, pg. 3. !
J Emergency Operating Procedures (QGAs) Lesson Plan, pg. 97. .
I KA 3.9 4.6 3.6 !
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295025A205 218000K302 218000G007 ..(KA's) l i
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1 7, PROCEDUBES - NORMAL. ABNORMAL. EMERGENCY Paga 41
, ,MD RADIOLQGEAL CONTROL ;
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QUESTION 7.13 (1.50) t
' l
! In accordance with QGP 4-1, what entry is made in the VERIFIER column t of the Control Rod Sequence Sheet under each of the following plant j conditions; -
- a. Reactor power is less than 20% of rated and the Rod Worth Minimiser is in NORMAL.
- b. Reactor power is less than 20% of rated and the Rod Worth ,
Minimiser is bypassed.
i ;
- c. Reactor power is greater than 20% of rated, :
i i
I ANSWER 7.13 (1.50) t i
i
- a. "RWM" [0.5) ;
- b. Independent verifier's initials [0.5) !
- c. "NA" [0.5) i 1 REFERENCE i
i
! Quad Cities, QGP 4-1 Rev 4, P. 6 KA 3.4 3.6 4
l 201003G001 294001A106 ..(KA's) l i l l
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' l h DMINISTRAT1YE PROCEDURES.,_ CONDITIONS. Pega 42 i
, ,A@_ LIMITATIONS QUESTION 8.01 (1.50) ll
- In each of the following cases, IDENTIFY the minimum spproval level [
required (Position Title) to receive the whole sody dose.'. (Assume no 4 prior exposure.) (If no special approval required, state "none.")
- c. 2000 mrem in a quarter. -
- b. 75 mrem in one week. .,t I
- c. 400 mrem in one week. ;
I i ,
] ANSWER 8.01 (1.50) :
t i l a. Administrative and Support Services Assistant Superintendent. :
(Assistant Superintendent of Technical Services) [
i b. None.
- c. Rad-Chem Supervisor er designee.
I 1 (0.5 pts each)
REFERENCE :
I
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l Quad Cities: Radiation Protection, LIC-RAD PRO, page 54 :
) '
KA 3.8 l i
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I l 294001K103 ..(KA's) l QUESTION 8.02 (1.50) i 1
! LIST THREE items of safety equipment that must be worn while working on any 4160 V circuit breaker. (1.5) l l
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2 1
- . - . . - .-----,--,---,,.--------------------r--,-, -------;
\
I. '6DMitilSIB&TIVE PBQQEQQBES. CONDITIONS. Pcgo 43
,.AND_LLMII6110EE ANSWER 8.02 (1.50)
- 1. Protective c.loak. (0.5) -
- 2. Helmet with face shield. (0,5)
- 3. Rubber gloves with leather protector. (0.5)
REFERENCE Quad Cities: QOP 6500-4 p.1 KA 3.0 $
'/
294001K107 ..(KA's) o l
QUESTION 8.03 (1.50) l Concerning notifications of emergency classifications.
- c. Responsible state and local government agencies are to be notified
.:athin after declaring the GSEP condition.
- b. Red Phone notifications must be made within once the condition is officially declared,
- c. NARO Phone notifications must be made within .
ANSWER 8.03 (1.50) <
- c. 15 minutes (0,5)
- b. I hour (0,5)
- c. 15 minutes (0.5) b
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ln CATEGORY
r...,
B, Pego 44 ADMINISTRAIl1E PROCEQQBES. CONQlTIONS._
, .AHD LIMlIATIONS REFERENCE Quad Cities: QEP-110-2 p. 2.
QUESTION 8.04 (3.00)
Concerning tagging of equipment. QAP 300-13.
- c. DESCRIBE how equipment control switches that are temporarily placed in an off-normal position is to be designated. INCLUDE how designation is performed for both 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or less and longer than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. (1.0)
- b. LIST the FOUR persons, by title, who are considered to be supervisors in charge of equipment. (1.0)
- c. (TRUE or FALSE) The Shift Engineer can authorize other persons designated as supervisors in charge of equipment to perform tasks that are specificnlly assigned to the Shift Engineer. (0.5)
- d. All saf ety-related out-of-services a:. return-to-services sha).1 be independently verified. STATE the criteria, concerning personnel classification, that the individual who performs the verification must meet. (0.5)
ANSWER 8.04 (3.00)
- a. 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or less - place an orange ring over the switch. (0,5) more than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> - Caution card system. (0.5)
- b. Shitt Engineer (0.25)
Shift Foreman (0.25)
Station Control Room Engineer (0.25)
Radwaste Foreman (0.25)
- c. True (0.5)
- d. Must be of equal (0.25) or higher classification (0.25).
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Bi.IkDMINISTRATIVE_PROSEDURES. CONDITIONS 2 Pcgo 45 AND LIMIIMIDLS REFERENCE Quad Cities: QAP 300-13 p. 4. QAP 300-14 p. 1 and 3.
QUESTION 8.05 (1.00)
Answer the following concerning shift manning, QAP 300-3.
- c. (TRUE or FALSE) An operator works an additional shift thereby !
1 working from 0300-2400 on Tuesday. The operator can work the '
same hours on Wednesday.
- b. (TRUE or FALSE) An operator is called in to work from 0400-0800. !
The operator cast report to work that same day at 1600. >
I i
ANSWER 8.05 (1.00) i
- c. False (0.5) l
- b. True (0.5)
REFERENCE Quad Cities: QAP 300-3 p. 1 and 2. !
KA 3.7 l
[
l 294001A103 ..(KA's) -
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a_______--__-_________-____.__
B, Pego 46 l AQMlHIEIRAIIVE PBQQEQQREEdQHQlIlQHL
..AHD.LIMIIAIlQHE l i
i QUESTlvN 8.06 (1.50)
Concerning QAP 300-22. Water Chemistry Control, l
- c. An orderly shutdown shall be initiated immediately with reduction in coolant temperature to less than 212 F if WHICH action !
level is declered. (0.5) l
- b. DESCRIBE the objective for completing the action described in part
- a. (1.0) l l
ANSWER 8.06 (1.50) i
- a. Action level 3. (0,5) .
I
- b. Correct a condition which may result in rapid reactor coolant system damage during continued operation. (0.33) Plant shutdown ,
will avoid ingress (0.33) and reduce further concentration of i harmful impurities. (0.33) i REFERENCE l Quad Cities: QAP 300-22 p. 4.
- l KA 3.4 !
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294001A114 ..(KA's) !
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Pcge 47 E. . ADMLHIEIBAILYE_EBQCEDLIBEEi._CONDL1 IONS.
..AHR_klMllallOEE I
QUESTION 8.07 (1.50)
- n. All temporary procedures and temporary changes to permanent 2
procedures terminate from the approval date unless 3
indicated.
- b. (TRUE or FALSE) Making a temporary change to a procedure to require l more conservative actions, concerning Technical Specification requirements, changes the intent of procedure because it may j restrict plant' operations.
j c. STATE the individual, by title, who is responsible to initiate training for shift personnel on temporary changes to procedures, i
j 1
) ANSWER 8.07 (1.50) 5
) a. 30 days (0.5)
- b. False (0.5)
- c. SCRE (0.5) t
) REFERENCE b
Quad Cities: QAP 1100-5 pp. 2 and 3. QAP 1100-7 p. 1.
- KA 4.2 i
i 294001A102 ..(KA's) a i
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- CONTINUED ON NEXT PAGE *****)
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- 8. ADMINISTRATIVE PROCEDURES. CONDITIONS. Peso 48 .
,.aHR.k1M1IAIl0HE ,
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l QUESTION 8.08 (2.50) [
I i
In accordance with QEP 340-5, Station Fire Fighting and Technical !
Specifications:
- a. STATE, by title, who is the Fire Chief in the Fire Brigade. (0,5)
I b. WHAT are the duties of the SCRE during a fire. (1.0) l c. WHO is responsible for arranging access for outside fire fighting' i
! equipment? (0,5) 4 I
! d. A fire brigade of persons is required to be on-site at !
1 all times. (0.5) [
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]
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1 ANSWER 8.08 (2.50) 1 a. Shift Foreman (0.5) ;
)
a
- b. (Using Fire Hasards Analysis), determine if fire affects any safe I shutdown equipment (0.5) and advise Shift Engineer (0,5). l i
- c. Shift Engineer (0.5)
- d. 5 (0,5)
{
' L l !
REFERENCE
. i Quad Cities: QEP 340-5 p. 2, 4 and 5.
Technical Specifications 6.1.C l KA 3.8 294001K116 ..(KA's) ,
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l B.. ADB1HIEIBAUYLEBOCEDURES. COHQlILQHEu Pogo 49 i
, ,&HQ_LIMITATIONE i
QUESTION 8.09 (1.00)
Concerning Vital Lock Control. QAP 300-16. !
- c. STATE. by titlu, the individual that controls the issuance of 'S' keys. ;
- b. (TRUE or FALSE) A valve outside the drywell that is normally locked with an 'S' lock is unlocked and opened. The lock should be .-
maintained at the valve while it is unlocked. l I
i ANSWER 8.09 (1.00)
[
- c. SCRE (0,5)
- b. False (0.5) (It is maintained in the 'S' lock box)
REFERENCE r I
Quad Cities: QAP 300-16 p. 1 and 2. j KA 4.2 j r
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211000G001 ..(KA's) I l
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Pcgo 50 L __AQMidlEIRATIVE PROCEDU M E d QHDITIONSm
..&HE_ LIM 11AllRHE QUESTION 8.10 (1.00)
During a review the Shift Engineer realises that the Core Spray monthly flow operability surveillance was not completed on the previous shift. Further review determines that it has been 33 days .
since the surveillance was completed. l
- c. IS Core Spray operable?
- b. The surveillance met the . required flow rates from technical specifications, but the Shift Supervisor has requested that Technical Staff review other problems with the surveillance that cause the Shift Engineer to doubt the operability of the system.
Is Core Spray operable while the review by Technical Staff is being l conducted? e i
i ANS'JER 8.10 (1.00)
- a. Yes (0,5) ,
- b. No (0.5) l r
REFERENCE i
Quad Cities: QAP 300-2 p 18. Technical Specifications 1.0. !
KA 4.2 4.1 F o
f 209001G001 209001G005 ..(KA's) l r
i.
QUESTION 8.11 (1.00) r FILL in each blank with the correct answer. QAP 300-19. Review of ;
Active Out-of-Services, requires; !
"Monthly, at least __(1) percent of those out of services f older than __(2) days and not in a high radiation area shall be physically reviewed."
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- 8. ADtildlSIB&TIVE_EBOCEDUBES, . COHQlllQEL Pcgo 51
. ,AND_LIMLIAT10HE ANSWER 8.11 (1.00)
- 1. ;9 +/- 5 % (0.5)
- 2. 30 +/- 5 days (0,5)
REFERENCE Q~& m w Y M'IMvY .
QAP 300-19. REVIEW OF ACTIVE OUT-OF-SERVICES, pg. 1.
KA 4.5 j 294001K102 ..(KA's) 4 QUESTION 8.12 (2.00) ,
The Technical Specifications SAFETY LIMIT on Power Transients implies that an AFRM SCRAM on a power excursion will terminate the transient before a significant increase in surface heat flux occurs. '
- o. DESCRIBE the inherent characteristic of the fuel that makes this possible. (1.0) i i
- b. HOW LONG can an AFRM SETPOINT be exceeded WITHOUT SCRAM before
- violation of a Safety Limit MUST be assumed
- 1) WITH the process computer in operation? (0,5) i l 2) WITHOUT the process computer in operation? (0,5) i i
ANSWER 8.12 (2.00)
(
, a. The heat transfer time constant (8-9s) (0,5) is such that the ,
neutron flux will be se<sn at detectors and terminate the transient ;
before peak centerline temperature can be transferred to the i cladding surface. (0.5) (Accept any correct discussion of l relationship between time constant and neutron flux.) t
- b. 1) 1.5s (0.5) j
- 2) Immediately upon exceeding the setpoint w/o scram. (0.5) :
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- 8. ADdlHISIBAIIVE PBQCEDUBES,_ CONDITIONS. Pego 52
, AND LIMIIATIONS t
REFERENCE Quad Cities: Technical Specifications, Safety Limit 1.1.C and Basis KA 3.8 4.0 4.2 295037G004 295015G003 215005G006 ..(KA's) 0.6 QUESTION 8.13 (bree)
Technical Specifications (TSs) require the reactor to be shutdown. if it is determined that a jet pump is inoperable. STATE TWO reasons, which cre taken into consideration by the design base accident (DBA) for loss of 4 coolant accident (LOCA), for this requirement.
O,5 ANSUER 8.13 (4-M) the blowdown area would increase. (0,5)
- el!-i-ste th: ::::bilit; ef ref1::di .. J.. . ;;.2. 40 ,64
- i REFERENCE Unit i TS BASIS 3.6.G, no Amendment No. listed, pg. 3.6/4.6-23.
QUESTION 8.14 (2.50)
- a. LIST SIX of items listed in QEP 310-1 Initial Notifications, that t are required to be transmitted when making an initial notification.
(2.0) :
- b. If an outside agency requests a method to verify the authenticity of a notification WHAT method should be suggested? (0,5)
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' . . '.L- Pcgo 53 1 AMlHJSIBATIVE_EBQCEDURES. CONDITIONS 1 ;
,AND LIMITATIQMS t
ANSWER 8.14 (2.50) ,
a a. Name of the reporting person.
Title of the reporting person.
Location of incident Type of incident Date of incident Time of incident Whether a release of radioactive material is taking place ;
j Potentially affected population [
Potentially affected areas i i Whether protective may be necessary !
j i (Any 6 @ .33 each) (2.0) l b. Call back using outside phone lines (0,5)
REFERENCE 1
j Quad Cities: QEP 310-1 p 2.
] KA 4.7 j t
i 294001A116 ..(KA's) i i
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- QUESTION 8.15 (1.50) ;
f 10CFR55 allows one exception to allow persons other than licensed !
l operators and senior operators to manipulate the controls ,
a that directly affect the reactivity or power level of the reactor. i 1 f
- a. WHO may manipulate the controls other than licensed operators and j
senior operators? (0.5) 1
- b. WHAT condition (s) must be met to allow manipulations by persons !
- other than licensed operators and senior operators. (1.0) i i
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8[ "ADMINISTBAIIVE_PEOCEDURES. CONDITIONS. Peas 54.
AND LIMITATIONS ANSWER 8.15 (1.50)
- a. Person in the license training program. (0.5)
- b. Must be under the direction (0,5) and presence of a licensed operator (0.5).
REFERENCE Quad Cities: QAP 300-2 p. 18.
10CFR55.13 KA 3.7 201001G001 ..(KA's)
QUESTION 8.16 (1.00)
STATE TWO exceptions to when blocks and jumpers are required to be performed in accordance with QAP 300-12 "System Temporary Alterations."
ANSWER 8.16 (1.00)
When alteration is part of an out-of-service request When alteration is part of an approved procedure.
Required to meet a Technical Specification Action Requirement (Any 2 6 .5 each) (1.0)
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1
...J- CONDITIONS < Peso 55
~'8. " ADMINLEIB&11YE_E8QQEDURES -
, AHQ_LitilIAllQHE REFERENCE Quad Cities: QAP 300-12 p. 1 and 2.
KA 4.5 4.2 294001A102 294001K102 ..(KA's) t I
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(********** END OF EXAMINATION **********) !
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' .. . J. -
't . EQUATION SMItf f = as y - s/t w = as s=vt+o at Cycle efficiency = N't Work (out) -
Energy (in) 2 E = aC -
a = (vg - y,)/t KI = huv v f=ya +g A = AN A=Aeo -At FE = msh w = g/g 1 = la 2/tg = 0.693/tg Ag = 93ta. ,
eq(aff) = (t,;)(ts) 6=[sC,AT , .Ix '
- UAAT g , g ,-VF *
- 8
- Pvr = W'g m" ,
, g.x/TYL N 8I- Tyt,= g,3/g P = P,10 P = P, e'N HYL
- 0.693/u SUR = 26.06/7 T = 1.44 DT SCR = S/(1 - E,gg)
I1'gg a,3 -
sv1 = 26 3,, CR, - s/(1 - r,gg,)
T = '(t*/o ) + [(i - ' o ) /1,,,o] CR g (1 - K,gg)g = C3 II ~ Ieff)'2 2
~~
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T,= 1*/ (o - i) M - 1/(1 - x,gg) - CR g/Can l
T = (I - o)/ A*ffa M = (1 - K,gg)CIII ~ Eeff)1 p = (K,gg-1)/K,gg = AK,gg/K,gg ]
SDM , (l - K.fi)/x.fi 8* (1*/TK,'gg 3 + 9/(1 + 1,ggt )] ,
t* = 1 x 10 ~3 seconds F = I(V/(3 x 1010) l ggA,o l seconds"I E=k .
Idgg=1d22 VATIR_PARAMETIRI Id2,gd g 2 1 gal. = s.343 1hm R/hr = (0.5 CE)/d 2 g,,,,,,)
1 gal. = 3.78 liters R/hr = 6 CE/dt gg,,c) ,
1 ft = 7.44 gal.
Nf 5Ctt1Mt005 CONVER$10NS .
Density = 62.4 lbs/f t 3 1 Curie = 3.7 x 1010 dys Density = 1 ge/cm 3 1 ks = 2.21 lbu Heat of va;orization = 970 ftu/iba 1hF = 2.54 s 103 ITV/hr Heat of fusica = 144 8tu/lba 1 N = 3.41 x 106 Stu/hr 1 Ata = 14.7 psi = 29.9 in. 13 1 Itu = 778 ft-lbf 1 ft. H 2O = 0.4333 lbf/in 1' inch = 2.34 cm F = 9/3'C + 32
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