ML20245E804
| ML20245E804 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 01/05/1989 |
| From: | Burdick T, Damon D, Hare S, Shepard D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20245E802 | List: |
| References | |
| 50-456-OL-88-02, 50-456-OL-88-2, NUDOCS 8901170371 | |
| Download: ML20245E804 (121) | |
Text
J.;
.1.
U.S. NUCLEAR REGULATORY COMMISSION REGION III k
Report No. 50-456/0LS-88-02 Docket Nos. 50-456; 50-457-Licenses No. NPF-72; NPF-77 Licensee:
Commonwealth Edison Company Post Office Box 767-Chicago, IL 60690 Facility Name:
Braidwood Station
. Examination Administereri At: Braidwood Station and Production Training Center Examination Conducted:
December 5-8, 1988 i/F/64 RIII Examiners:
T. M., b
- 5. M. Hare Date Allh IMr7 Date D. L. 5hhpard l/6/8'l Chief Examiner: M Date D.(. Damon f/
7 Approved By:-
t Date T. M. Burdick Examination Summary Examination administered on December 5-8, 1988 (Report No. 50-456/0LS-88-02)),
to five Reactor Operator Candidates (1 retake) and six Senior Reactor Operator Candidates (1 retake).
Results: All Reactor Operator Candidates passed the examinations. One Senior Reactor Operator candidate failed the examinations.
i I
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' REPORT DETAILS 11.
-Examiners h
.),,
- D. J. Damon S. M. Hare-J L
D. L. Shepard
- Chief. Examiner V
-- 2. -
Exit Meeting l
On December 9,1988, the examiners met with members of the facility staffe to discuss the examination.
The following persons attended.the meeting:
R. E. Querio,. Station Manager, Ceco
.K. L. Kofron,.' Production Superintendent, Ceco G. N. Masters', Assistant Superintendent _ Operations, Ceco W. McGee, Training Supervisor, CECO.
M.: Takaki, Regulatory Assurance, Ceco.
G. Vanderheyden,.0perations.Traini'g Supervisor, CECO n
D. Hustun, Licensed Operator Training Group Leader, CECO '
'K.-Gerling,:PWR Licensing Supervisor, CECO-PTC
. T. ; Chasensky, Group Training Supervisor, Ceco-PTC -
R.-. Coon, Instructor, CECO-PTC T. M. Tongue, Senior Resident Inspector, NRC
.D. J. Damon,. Examiner, NRC D. Shepard, Examiner, NRC The following comments were detailed during the meeting:
Strength During some~ simulator scenarios, RO candidates were required to stand-in
~
for the SRO position.
The R0 candidates displayed ~ strong skills and -
knowledge in this position.
Weaknesses 1.
During simulator scenarios with an inadvertent Phase A isolation, candidates displayed inconsistencies in verifying proper actuation of the Phase A_ signal response and in recovering from this malfunction.
(
' 2.
SRO. candidate control board skills were generally weaker than R0 candidate board skills.
7 2
3
General Comments.
1.
Yellow and blue " dots" that were used during the pre-operational phase are sill attached to controls c9d indications throughout the facility. These dots no longer serve a function in the facility and served to confuse candidates that were questioned concerning their use.
2.
Bw0A Elec-3 (Local Emergency Start of a Diesel Generator), Step 4 refers to the day tank gage-glass.
No gage glass is installed on the day tank.
Facility Comments Following are facility comments on the written examinations and their respective NRC resolutions:
W O
4 3
k 1
_ _ _ _ _ _ _ _ =
h r:i ',
.=
l Question 2.07
.(1.50)
List two. indications from the Liquid Radwaste Panel or the Control Room that
. an NSO can use to determine when a -liquid radioactive water release was automatically terminated.
Answer 2,07 (1.50)
(Any 2 at 0.75 each) 1.
Loss of flow on Release Tank Flow Recorder or Release Tank Flow Integrator.
L 2.
Liquid Radwaste Control Panel Trouble Alarm.
3.
Radioactive liquid release valve (WX 353) and bypass valve (WX 896) indicate shut.
Braidwood Contention:
2.07 An additional' acceptable answer s ould be the RM-11 alarming'due to an h
" Operate ' Fail ure. " Since when the release secures-automatically due to low levelthereleasetankgumpwilltripandalossofsampleflowwillresult in an " Operate Failure.
Reference:
. System Description, Chapter 49, Pages 49-66.
NRC Resolution:
Concur. Answer key expanded.
Question 2.17 (1.50)
BwEP-1, " Loss of Reactor or Secondary Coolant," directs the operator to place the. steam dumps in the STEAM PRESSURE mode of operation after the RCPs are tripped. Why? (Give TWO reasons)
Answer 2.17 (1.50)
(0.75each) 1.
Tave signal is in error because of little flow through the bypass manifolds.
2.
Steam pressure mode provides finer control.
Y 1:
4
-l a
Braidwood Contention:
2.17 An additional correct answer should be to allow cooldown below 550*F, since the steam pressure mode is the only mode with an adjustable setpoint.
Reference:
Lesson Plan, BwEP-1, Page 71.
NRC Resolution:
Concur.
Answer key expanded.
Question 3.17 (2.00) a.
What TWO signals cause C-8 (turbine trip) to actuate? (Setpoints and coincidences not required for full credit)
(0.5) b.
What function does C-8 se~rv~e in the steam dump system?
-(0.5) c.
If Unit 1 tripped from 65% power, WHAT would be the position of all the steam dump valves with Tavg at 575 F?
(Assume all systems responded normally to the trip)
(1.00)
Answer 3.17 (2.00) a.
1.
Stop valves closed (0.25) 2.
Low emergency trip header pressure (0.25) b.
Arms turbine trip controller of steam dumps in Tave mode (0.5) c.
1.
6 valves (tripped) open (0.5) 2.
3 valves modulating (0.25) 3.
3 valves shut (0.25)
Braidwood Contention:
3.17.b Due to a modification to the steam dump /SSPS systems, C-8 no longer arms the turbine trip controller.
Recommend that the answer key be changed to nothing.
Reference:
1.
Station Field Engineering letter (SFE/BWD No. 2178-1) to Station Manager.
2.
System Description Drawing 24-7.
5 l
J.
o..
NRC Resolution:
Concur.
Answer key modified.
It is requested that the facility ensure that the System Description text is revised and updated to reflect plant modifications prior to the next NRC exam.
Question 3.30 (2.00) a.
What are the' quarterly-legal MAXIMUH permissible doses for:
1.
Lens.of the eye
(.25) 2.
Ankles
(.25) 3.
Skin
(.25) 4.
Abdomen
(.25) b.
What is the limit for accumulative occupational dose for a 27 year old person with a Form NRC-4 on file?
(0.5)
What kind of area would you expect an area to be posted as if you could c.
expect a dose of greater than 100mR in five working days?
(0:5)
Answer 3.30 (2.00) a.
- 1.
3 rem (0.25) 2.
18.75 rem (0.25) 3.
7.5 rem (0.25) 4.
3 rem (0.25) b.
~45 rem (0.5) c.
Radiation Area (0.5)
Braidwood Contention:
a.1 and 4 Due to ALARA considerations and the emphasis placed on reduction of personnel exposure at Braidwood Station, the, correct answer should be 1.25 rem unless the student specifically states that all conditions of an extension (Form NRC-4 and Lifetime dose less 5(N-18)) are met.
Reference:
BwRP 1000-A1, Page 24.
I NRC Resolution:
Do not concur.
The question clearly asked for the legal maximum (emphasis added) doses.
Answer key remains unchanged.
6
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ =
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- Question 4.09
' (1.25);
For;th'e'fo11owing. changes:in' plant' status,' indicate whether.the DNBR.in the
'j coreLwill: INCREASE,; DECREASE, or REMAINLTHE SAME.. Consider each change.
separately, and assume all other parameters remain unchanged.
The reactor l k
'is initially,at 50% power.
F a.-
Increase reactor power.
i b.
-Increase:CVCS charging and letdown.
c.: ': Control rod insertion..
f
.. d.
-; Increase pressurizer Pressure.
e..
- Increase core inlet temperature.
Answer 4.09 (1.25).
a..
Decreasei
(.25) 1 b.
' Remain the same:
(.25)
P c.
Increaso
(.25)
E d.-
Increase
(.25) e..
Decrease
(.25)
Braidwood Contention:~
1 4.09.c' This'part..should be' deleted since no explanation is required, and may go
.either way, depending on assumptions.
If it.is assumed that Tave.goes down then DNBR will increase as stated on your answer key..But~if you assume Tave' remained constant (since. question states all other parameteri remain o
funchanged),'then the subsequent flux redistribution will cause-the actual F
local-heat flux to increase.at some portion of the core and lower DNBA.
Reference:
Power Distribution-Limits, Chapter 3, Pages 3-23.
NRC Resolution:
Part-c deleted and point value adjusted according. Note that since Question 1.09 is a duplicate of this question, the same changes are made to Question 1.09.
Question 4.11 (1.00)
When starting up-the condensate system, the discharge valve of the FIRST E
condensate pump is' THROTTLED open slightly prior.to starting the. pump.
Why?
(Your answer should address mechanical rather then electrical concerns).
7
-.-..-_---__---_______.___~_?__-_____
Answer 4.11 (L 00)
To prevent water h:immer (from damaging the system).
Braidwood Contention:
4.11 1
The concept being tested is good, but with our system design, the Operating Procedures specify that it is the discharge of the Condensate Booster Pump that
{
is throttled.
Additional acceptable answers should be to prevent pump runout or to ensure that the Condensate Booster Pump has an adequate suction supply.
Reference:
1 Bw0P CD/CB-1, Page 4.
NRC Resolution:
Questiondeleted.
Note that since Question 1.11 was a duplicate of this question, Question 1.11 is also deleted.
Question 4.14 (2.50)
Answer each of the following regarding temperature detection circuits:
a.
If an RTO fails OPEN, what happens to indicated temperature?
b.
If an RTD fails due to a SHORT-CIRCUIT, what happens to indicated temperature?
If a thermocouple fails OPEN, what happens to indicated temperature?
c.
d.
If a thermocouple fails due to a SHORT CIRCUIT, what happens to indicated temperature?
Which of the two temperature detection elements, RTD or thermocouple, e.
has the faster response time?
f.
Which of the two temperature detection elements, RTD or thermocouple, develops its own electrical output?
Answer 4.14 (2.50) a.
Indicated T fails high (0.5) b.
Indicated T fails low (0.5)
)
8
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h!
I p./ l y
a c.
Indicated T fails' low (0.5) n-d.
Indicated T fails' low.
(0.5) e.
T/C.
(0.25):
f.
~T/C (0.25).
~ Braidwood Contention:
'4.14.c
.T' is,questionLshould be deleted since it does not'specify whether it is h
h
-referring to a basic temperature indicator or our Core Exit Thermocouple.
In the Core Exit' Thermocouple System, an open circuit would fail the
~
-indicated temperature high.
f
Reference:
System Description, Chapter 34b, Page 21.
NRC Resolution:
Part c deleted and point value' adjusted accordingly.
L
' Question 4.21 (1.00)
Concerning the'" Generator Field Forcing" annunciator:
List or describe a probable cause for this alarm.
(Annunciator test a.
is not considered a valid response.)
(0.5) b.
Explain what immediate action you should take as the' BOP if this alare
- is-received..
(0.5)
Answer 4.21 '
(1.00)
_ F1uctuations in grid conditions causing)~ voltage regulator increase
(
a.
in exciter field current (to maintain generator voltage).
(0.5)
T b.' - ' Slightly reduce exciter field current by lowering the voltage(0.5) i adjuster.
Braidwood Contention:
3
~4.21.b An additional acceptable answer would be to reduce exciter current.using o
l the Base Adjuster.
9
[
Reference:
System Description, Chapter 6, Page 23.
NRC Resolution:
Partially concur.
If the candidate states that the voltage regulator is placed in manual, reducing field current by.using the Base Adjuster will be accepted for full credit.
Question 5.05 (1.50)
Concerning the Emergency Procedur :, explain why each of the following statements are FALSE:
In general, a required task as stated in a procedural step.MUST be a.
completed prior to proceeding to the next step.
(0.5) b.
The procedures are applicable only in modes 1 through 3.
(0.5)
The only entry points into the BwEP's are through BwEP-0', BwCA 0.0 c.
and BwFR-S.I.
(0.5)
' Answer 5'.05 (1.50) a.
Simply starting the step is sufficient.
b.
Some procedures are applicable in modes 4 and 5.
c.
Entry is not allowed directly into BwFR-S.I.
Braidwood Contention:
5.05.c An alternate acceptable answer would be that if at the Remote Shutdown Panel any BwEP can be entered direct'ly per note.
Reference:
Bw0A PRI-5, Page 3.
NRC Resolution:
Partially concur.
If the candidate states that he is in Bw0A PRI-5 at the remote Shutdown Panel, entry into any BwEP will be accepted.
10
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,3 L
-SIMULATION FACILITY REFORT l
Facility Licensee:.Braidwood l
Facility Licensee Docket No. 50-456/457
. Operating Tests Administered At: Braidwood (Production. Training Center) ibring the conduct of the simulator portion of the operating tests, the
' following items were observed:
~
ITEM DESCRIPTION
- 1.
Malfunction Aux-1 (Loss of Instrument Air) does not work.
2.
S/G blowdown valve override titles do.not correspond to the correct valve numbers.
3.
-S/G WR._iconics reference setpoint is incorrect.
4.
Two main turbine reheat stop valve indication lights do not work.-
5.
IPM12J (post accident monitor panel) recorders do not work.
-6.
Annunciator horns on the simulator are different from horns on the actual unit.
7.
While running NRC simulator scenarios on 12/8/88,.the simulator halted twice for no apparent reason.
8.
While running two different tube leak scenarios (100 gpm and 450 gpm) no RM-11 alarms or alerts were received.
4AB222 ten minute trend bar graph actually decreased.
e t
=
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S.
NUCLEAR REGULATORY COMMI55ZON EENIOR REACTOR OPERATOR-LICENSE EXAMINATION REGION C
FACILITY:
graidwggd 1_k_2__________
REACTOR TYPE:
PWB-WEQS_________________
@8Z1_/95________;________
2 DATE ADMIN 5TERED:
?NSIEUC11995_19_L6NDID8IE1 Use servar at e paper for the answers.
Write answer s on one side only.
Staole cuestion sheet on top of the answer sheets.
Points for each ouest i en are ind2 cated in par entheses after the ouestion.
The passing grade requires at least 70% in each categorv and a final grade of at i
1 E a y.t Eu)%.
EXBm} nation papers will be Dicked up si;: (6) hours atter the c: smination starts.
% OF CATEGORv
% OF CANDI DATE' S CATEGORY
__YeLYE_ _IQIe6
___EGOBE___
_YBLUE__ ______________G81gGQBY_____._________
_32t20__ _22sp5
________ 4.
REACTOR PRINCIPLES ~(7%)
THERMODYNAMICS (7%) AND COMPONENTS (10%) (FUNDAMENTAL EXAM) 5.
EMERGENCY AND APNORM4L PLANT
_209,_ ...?s, 5? EVOLUTIONS (33%) 6. PLANT SYSTEMS (30%) AND _d2:09-_ _dJt2Z PLANT-WIDE GENERIC RESPONSIBILITIES (13%) _ 9 8. _. 2_ 5_ _ _ TOTALS FINAL GRADE All werk done on this examination is my own. I have neither given nor received aid. i Candidate's Signature i NASTm CO?3 - - - - - - - - - - - - - - - - _ - _ _. - - - - - -, - - - - - - - - - - - - ~ _ - ~ _ - - -_--__-J
10, m 474 t NRC RULES AND GUIDELINES FOR LICENSE-EXAMINATIONS s.. LDuring~the administration.cf this ei< amination the ' f ollowing rules apply: 1 [ ri.i' ' Cheat i no - on the examinati on means an automatic duntal of your app 12 cat 2en L and. c oul d. resul t in more severe penal, ties. 2.'. Rest r'oom tr 2 ps ar e. to be. li mi ted and only one candidate at a time mav E leave. You must avoid all contacts with anyone outside the examination r oor-to' avoid even the appearance'or poss2bility of cheating. i D 3. Use' black ink or dark pencil only: to f acilitate legible reproductions. .[4 '. ~. P r i n +- your name in the blank provided on the cover sheet of the . e::ami n at i on. L5. Fall 2n the date on the cover sheet of the examination (if necessarv). -6. _Use only the paaer provided for answers. 7; PrintLvour name in the' upper right-hand corner of the first.page of eacn secti on - of the answer sheet. 8. Consecutively number each answer sheet, write "End of-Category __" as appropriate, start each category on a new page, write only on one side of'the paper,.and write "Last Page" on the last answer sheet. 9. Number each answer as to category and number, for ex amp l e. 1.4. 6.3.
- 10. Skip at least three lines between each answer.
-11. Separate answer sheets from pad and place finished answer sheets face down-on yo'ur desk or table.
- 12. Use abbreviations only if they are com:nonly uped in facility literature.
- 13. The point value for each question is indicated in parentheses after the question and can be used as a guide f or the depth of answer required.
- 14. Show all calculations, methods. or assumptions used to obtain an answer to mathematical problems whether indicated in the question or not.
- 15. Partial credit may be.given.
Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLANK. If parts of the examination are not clear as to intent, ask questions of-
- 16... the examiner onl y.
417. You must sign the statement on the cover sheet that indicates tnat tne and *you have not received or been given assistance in work is your own comoleting the examination. This must be done after the examinat2on has been comcleted. ___.__._____________________=__._____m.__________
p
- 30. When vou complete-your examination, you shall:
a.- Assemble your examination as follows: s1) Exam ouestions on top. t '/ Exam aids - figuros. tables. etc. ' 3 '. Answer pages including figures which are part of the answer. l b. Turn in your copy of the examination and al l pages used to answer t he examinat2 on cuest i ons, c. T ur n in all screo paper and the balonce of-the paper that.you dad not use f or answering the questions. d. teave the enam2 nation area. as defined by the examiner. If citur leaving. vou are found in 'this area while the examination is still in prooress. vour license may be denied or revoked. O l i j j 1 ____________:_______L-
sg, Pcg3-1 of 5 e' 4 peIe_geggI. E. ' BEBCIQB_IdEQBLEQBtlukBS: ~ SUR(t). P. p.t/T p,p gn 1 I. 5 V th SUR = 26.06/T P = -------- 73-fissions /sec 3.12 x-10 7f ~# ~ ~~ .,-(B Lth y 14-Av - ______2 p 2-th 1+ (B L 3 th ~I -(B L ) p = ----- P =e f f K K b"*1-- 00 = I n p_,,-CN3CI,,4 3/lI, initial 9 ,4g C (1-K,,f3) =,C ' ~ eff2
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3 2 I 1 Cfina;~ y = -- = m = -- 1~ initial 1.Af 1 Ap OL 2 + oL 2 th 2 (~~~f ~~~~~3 a ~~# ~ ~~ ~ 0 ~ T
- f. At p At.
At at eff ~ @O P = P ~~~~~~~~~ =6P pP f F) 3 O K,,, 4 th eff P 1 4 i 4. h'
- p. e.
- 9 .
+ Pcg3 2 cf 5 '~ Dele _EMEEI L-e . IBEBdQQ'ISBu1CS_8ND_ELUID_DECUBUICS EQBuuLBS: r 2 w LaT Q = ~ A oh G = ----------------------- i 1 In R /R In R /R 2 3 3 2 t- - + -------- + -------- ,Q = U A (AT )* K K K . 1 2 3 Q=mc (AT)' 4 P b = cc d A R I n. _Le_:_Q_eut n. __Le___h_est_) tral __ (h G (h -ho t) ideal Q g in. actual 1 1 22 1 2 supplied Av & = pAV pAV =-p2 2 2 g g g 3 A = KA E = KA AT M = KA op J oP A = KA 4 A P p nc Q x E AT (in) - AT (out) G=f th AT AT (in) 8.Sx10 In (~-------) AT (out) 2 kA6T Gr G = ----- T -T = - -. C1 Ps 4k ox O tot al ,G = gg--- gg-- AX a b n ___ + ___ +, + K K K a b n },- 4 -* w m
,3. m.. :.. %y,.. Pcgo 3 cf 5, g[;; 4 Del 8_SHEEI ' :e [ CEWIB1EUG8L_EU:32_LGWS:. (N d P LN d H N g g g g _ _1. __1 f1 .N '"2 2 2 - (N P (N } H 2 2 2 89DieIIQW_eWQ.CUEdISIBY_EQBdWL958 R/hr = 6CE/d y ,y ,-mx CV =Cv 2 g g 2 2-G'= DildtLgn_Batt I=1 Il 0' ~ 0 Volume 10 A = AN A=AOe GQNYEBEIQWE - 62.4 lbm/ft Density of water (20 C) = 62.4 lbm/ft 1 gm/cm = 1 gal = 0.345 1.bm ~ 1 ft = 7.48 gal Avogadro's Number = 6.023 x 10 1 = gal ~ = 3.78 liters Heat-of Vapor'(H O) = 970 Btu /lbm-2 144 Btu /lbm Heat of Fusion (ICE) = 1 l'bm = 454 grams -24 1 AMU = 1.66 x.10 97,,, e = 2.72 w = 3.14159 Mass of Neutron = 1.008665 AMU '1 KW =-738 ft-lbf/sec Mass of Proton = 1.007277 AMU 1 KW.= 3413 Btu /hr Mass of Electron = 0.000549 AMU One atmosphere = 14.7 psia = 29.92 in. Hg 1 HP = 550 ft-lbf/sec 1 HP =.746 KW 'F = 9/5 *C + 32 1 HP = 2545 Btu /hr
- C = 5/9 (*F - 32)
'1 Btu = 778 ft-lbf 'R = *F + 460 -6 1 NEV = 1.54 x 10 Btu
- K = *C + 273 I
~ h = 4.13 x 10 M-sec 10 1 W = 3.12 x 10 fissions /sec c = 931 MEV/ AMU = 32. 2 l b m'-f t /l b f-sec gg 1 inch = 2.54 cm C=3x 10 m/sec ~ r = 0.1714 x 10 Btu /hr ft R I I 9 .__._.____...__.____1____._m_._____.m_
i Pcg3 4 cf 5 ~'
- DOIe_SBEEI GVE88GE_IBE80GL_CONDUCI1Y1IY_1K1
~ datettet E O.025 Cork Fiber Insulating Board 0.028 0.096 Maple or Oak _ Wood O.4 Building Brick O.45 Window Glass 0.79 ' Concrete 25.00 1*/. Carbon Steel 1% Chrome Steel 35.00 118.00 Aluminum 223.00 Copper 235.00 Silver Water (20 psia, 200 degrees F) 0.392 Steam-(1000 psia, 550 degrees F) 0.046 1.15 Uranium Dioxide O.135 Herl i um 10.0 Zircaloy ~ 515CELLONEQUS_1NEQBd8Il0N: ~ 2 E = mc 2 KE'= 1/2 mv PE = mgh V, = VO + at Area Volume Geometric Object A = 1/2 bh ///////////////// Tri angl e A = S* ///////////////// Square 'A=LxW ///////////////// Rectangl e A = wr* /////////ill///// Circle Rectangular Solid A = 2(LxW + LxH + WxH) V,= L x W x H 2 2 2 l Right* Circular Cylinder A= (2 wr )h + 2(wr ) V = wr h l 2 V = 4/3 (wr*) A=4wr Sphere ///////////////////////////// V*5 Cube t 4 i lY L ____________________._______1
y < 4.a ; Pago 5 of 5 41 dei 8_EWEEI ' oISCELL8WEQUS_INEQBd8Il0N_1coattauedi 10 CFR 20 Appendix B Table I ' Table II Gamma Energy Col I Col II Col I Col II MEV per Air Water Air Water Material Half-Life Disintegration uc/ml uc/ml uc/ml uc/ml Ar-41 1.84 h 1.3 Sub 2x10
- 4x10 "
~ ~ ~3 Co-60 5.27 y 2.5 5 3x10"# 1x10 1x10 " 5x10 ~# ~ ~3 -lU ~#~ I-131
- 8. 04 ' d 0.36 S
9x10 ' 6x10 1x10 3x10 ~ ~# -Kr-85 10.72 y 0.04 Sub 1x10 ' ~ 3x10 Ni-65 2.52 h 0.59 S 9x10"# 4x10 3x10 " 1x10
- f
~ ~3 ~ Pu-239 2.41x10*_ y 0.608 5 2x10 1x10
- 6x10 5x10 " l
-l# ~ -l* ~ ~Y ~3 -Al ~7 S 1x10 1x10 3x10 3x10 Sr-90 29 y ~# Xe-135 9.09 h 0.25 Sub 4x10 * ~ 1x10 2>2he 3x10 ' 9x10 1x10 3x10 Any single radionucli.de with T -5 -10 which does not decay by alpha br ~ spontaneous fission 2 Neutron Energy (MEV) Neutrons per cm Average flux to deliver equivalent to 1 rem 100 mrem in 40 hours 970x10' 670 thermal 0 280 (neutrons) O.02' 400x10 0.5 43x10 30 -- g x--see 6 10 24x10 17 cm Linear Absorption Coef ficients p (ca~l) Energy (MEV) Water Concrete Iron Lead 0.5 0.090 0.21 0.63 1.7 1.0 0.067 0.15 0.44 0.77 1.5 0.057 0.13 0.40 0.57 2.0 0.048 0.11 0.33 0.51 2.5 0.042 0.097 0.31 0.49 3.0 0.038 0.088 0.30 0.47
m Fogo 4 ix __ bee? IGE _ES1991ELES_JZEl_ISEBDgDyO601Q@ 12's:.6U0 E9dP99ENIE_11931_1EuggergN1@65_gh8d1 OUEET?ON 4.01 (1.00) Per 1.'w D.e Roc-4. " Dropped Rod Recovery", what is the maximum fuel preconcationed limit definec as? (Assume this is during the initial oower a sc ermi on after e refueling outage.) DLIESTION 4.02 (1.00) Will the shutdown margin INCREASE. DECREA5E. or REMAIN THE SAME for the f ol l owi n;3 condations? (Consider each case seperstelv> s. Load rejection from 100% to CO% power, control rod position lowers and T-avg equalra programmed T-avg. b. The reactor is steady state at 50% power when a small dilution occurs-with control rods in automatic. c. The reactor is steadv state at 50% power when a small dilution occurs with control rods are in manual, d. Fle e c t esr power holdang at 50% during a startup. <enon is : ncreasing. C' S ST IL N '4.03 (1.00) For two equivalent positive reactivity additions to a critical reector, will the SUR be the same, l ar ger, or smaller at EOL as comoared to BOL7 E::al ai n your choice. Use of appropriate f ormul as is acceptable. QUESTION 4.04 (1.00) One reason for hav2ng Rod Insertion Limits (RIL) is to ensure that the potential effects of rod misalignment on accident analyses are limitec. EXPLAIN bc,w Ells reduce the severity of an accident. (Include in your answer which accident is considered.) k I ! 1 (***** CATEGORY 4 CONTINUED ON NEXT PAGE *****) l 1 j i
6 ~ ' ~ ~ ~ ~ ~ ~ - ~ ~ ~ ~ ~ ~ i Fage 5 4 REAC TOR FRJNCIE%EE_f?h1_TH5609pyN6Digg IZh n 9UD_G9dEQUENIg f M31_f[yNDSDEU1965 E16D1 DUES 1105. 4.05 (1.50) The curve of critical boron concentration vs. burnup has an initial steep droc, f ollGwed by a relatively constant concentration until approximately 2000 EFFH. after which concentration d r oo f. 31nearl y with burnup. l Explain the reason for the initial steep drop AND for the level concen ration out to 2000 EFPH. QUEST!ON 4.06 (1.50) 1. As thr-reactor cor e ages, Differential Boron Worth (DBW) changes, Explain TWO effects which occur over core life, and a. b. HOW each changes (i e. more negative, 1ess negative,...) Excl ain what the overall effect on DBW is as the core ages (ie. more 2. negative, l ess negative,... ) DUdETIO*! 4.07 ( 2. 00) the f e,llowa rio r revents DND f rcm occurrir.g during normal pitnt Which GNE oi caer st a co rs? a. Minimum temperature f or criticality (550 degrees F) b. Heat Flux Hot Channel Factor RCE pressure saf ety limit (2738 psig) c. d. En th al p,- Rise Hot Channel Factor 8 1 i, (***** CATEGORY 4 CONTINUED ON NEXT PAGE 4****)
e; i 4. Rg6?IOB_EBJUGIELES_1Z31_Id5ED99196 DIES Page. 6 JZ31.M49_GRMEONEUI5_J1931_fELIUp6DENf 665_Ef 6DL OUESTION 4.08 (1.00) Which'ONE of the f oll owing is NOT character 2stic of tast neutron irradiation on re+ctor vessel me t al s? a. Increased strenoth b. Decreased duct 21 s tv c. Nil-duct)Jitv Temperature (NDT) decreases, d. A c.ance 2 r. tna lattice structure of the met al. DUES 1 ION 4.09 (1.00 Fcr the f oll owing changes 2 n pl a'nt status. 2ndicate whether.the.DNBR 2n the core ws;1 INCREASE. DECREASE, or REMAIN THE SAME. Consider each change senarately, and ossume all other parameters remaan unchanged. The reactt-as inst: ally at 50% power. a. Increase reector power ,b. Increase CVCS charoing and letdown. c. DELETED d. Increase pressurizer pressure o. Increase core inlet temperature DUESTION 4.10 (1.00) I 'If Impulse Pressure to the rod control rystem was calibrated so that Tree was reading five degrees higher than it normall y would read, what effect woul d this have on secondary plant efficiencv? Whv? (Assuma no operator actzen.) OUESTION 4.11 (O.00) QUESTION DELETEQ (***** CATEGORY 4 CONTINUED ON NEXT F ASE * * * * * )
i ) ~,... ~ 4 RE(<C10R' PRINCIPLES ( 7*4 ) THERMODYNAMLQS Pace 2 AZs/ _89D_C90EONEUIS_,t192.l_jEQND@dgbl@Lg_EX6dl DUESTJON 4.12 (0.75) Wh. shculd ver s fi cati on of natural circulation condi ti ons be perf ormr<d c r. e tre,o2no bes2s versus 2ndividual sets of readings? DUEG~iJCN 4,13 (3.00) The reactor 2s in a no-l oad c ondi tion with average temperature at 557 oegrees-F and SIR pressure at 2250 psig prior to start-up. Calculate the subcool2ng margin usi r.g the steam tables (pr ovi ded ). DUCSTION 4.14 (2.00) Answer each of the following regarding temperature-detection c:rruits: a) 1+ an RTD + ails OPEN. what happens to indicated temperature? b> If an RTD fails due to a SHORT CIRCUJT. what happens to indaceteo t e.mo er atur e? c) DELETED d)- If a thermocouple e f ail s due to a SHORT CIRCUIT. what happens to indicated temperature? e) Which of the two temperature detection elements, RTD or thermocouple. has the faster response time 7 f) Which of the two temperature detection elements, RTD or thermocouple. develops its own electrical output? e (***** CATEGORY 4 CONTINUED ON NEXT PAGE *****)
] !Y..,. -$h.,GEciGIUF _ESIUQ1E6g@_1731_IUgBdOQfN@b]Q$ Page 8l L IZ 3 L.8N Q _QQUEQNgyIS _11931_ J EUUp@DEUl@b S _g 360[ 1 DUES rIt N 4.15- -(1.00) Safe +v ol ves are_ us,ed i n the mai n steam system to protect the the_ system piping t r om damage due to overpres:suric ation. Which of the following ' statement s concerning the operatieri of saf etv valves is correct? (CHOD5E ONE) . When thc activating pr essure f or a saf ety valve returns to.the 11ft2ng a. . set point. a combination of steam and air pressure above the valve disk cl oses the val ve. 'O. As. et eam pr essure increases to the safetv set point. the. pressur e overcomen spring tension on the valve operator. causing the valve ~to .coen. c. As.the disk on a. safety valve lifts, less pressure is exerted on:the -disk, reducing the upward force:on the disk, preventing " valve slamming". _ i_.$$ 2d.. A saf ety valve is lif ted of f its seat. thes is forced fully open by an air-operated piston. ~DUESTION 4.lo (1.00) Whi r;h DNE'of the f ol1owi no st atements i s TRUE f or the MI XED-BED deminera11:ers7 isotopes The mixed-bed deminerali:ers are designed to remove on]y ionic a. and not' particulate. Maximum flow rate is limited to 75 gpm to prevent resin bed 'b. channel 1ing, An unsat urated mixed-bed deminerali:er can decrease RCS baron c. concentration by approximately 100 ppm. d. A m2.xed-bed demineralized can operate f or only two months with 2% -failed fuel. s (***** CATEGORY 4 CONTINUED ON NEXT PAGE
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- 4. Zi.1. 0N D _ G 90E Q NEN15_11931_ f E WU Q8 D g hl @L 5_ El s D L QUELTION 4.17 (1.00)
Fill 2n the blank: Too f r ecuent starting of a RCP may resul t in serious camage to the from overheating. DUECT10N 4.18 (1.00.) As NEO. .ou r.at:ce a cump breaker switch with a red and ember l i pt soove the pcsst2cner. Reactor power level is 75%. What'do these l i ghts me ar.' OUESTION 4.19 (1.00) BwAP 500-1, " Conduct of Operetions", allows an Operator to place a. in the controller in the MANUAL mode from the AUTOMATIC mode whenever, Operators judgement. cont 2nued aut omatic operation is unsafe or whenever it may cause unnecessary transients. This should onl y be done under WHAT TWO conds t 2 ons / s2 tuat s ons?. QUESTION 4.2u (1.50) . A pressura::er level instrument develops a leak i,n its reference leg. Expla2n HOW and WHf pressuri:::er level indication changes for th2s instrument. OUESTION 4.21 (1.00) Concerning the " Generator Field Forcing" annunciator: a. List or des.cribe a probable cause for this alarm. (Annunciator test as LO.52 not conesdered a vali d r esponse. ) b. Exol ain what immediate action you should take as the BOP if th2 s alarm ( 0. 5) is rece2ved. II .s. i .t (***** END OF CATEGORY 4
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c:. 2 (- l. p, Fage 10 l . L. _ E!1E'..EN[ Y @UD.@tyDBtl@(.,[%@N1. Ef.!OLUl.lDN1, j .! 22*a. l 1 QUESTIOf 5.01 (2.00) List 2 a ndict<ts ons f r om the Li qu2 d Radwaste F anel or the Control Roon: that en SP2 ran use to determ2ne that a li culd radioactive water release in progress has exceeded the high radioactivity setpoint. (Excl ude Rti-11 ). QUESTION 5.02 (0.50) 1 RLE c. FALEE? PDFV valve seat is considered " Pressure Bounderv LeM ece" Leake.ge pas.t c. per To:nnitel Goecifications. E x p l #. 2 r.. DUESTION 5.03 (2.00) A reati car trip alwave causes a turbane trip. The tripping of the turt2rm wou3c result 2n a generator trip 24 there were no time delay. There are two =. sa + et y-rel at ed reasons f or having a gener ator trip tip,e deley. Enol a:. the two .( 2 ) reasons, (***** CATEGORY 5 CONTINUED ON NEXT PAGE
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4 s Qf,~ . Pace 11 @,;__ghgRGENCY AtJp, ABNQRMGL;%@NT_gyQLt)TIQNg ': Cu- * *./ ).. .i DUESTION' 5.04. (3.00)~ . For each of.'the'followino cases. state whether or: not emergency borat i on i s recu red ' per DwOA-PRI-2. " Emergency Boration":- '(.25 esb a. One control rod fails to insert on a reactor trip b.. Resctor'is in mode 6 with baron concentration of-1900-
- c. '
R*_ce tor power as.100% with control bank D.at 79 steps, d. 2 Delta I is atl-17~.. Target delta I is -3 p' ' PC5 temperature i s at 551. degrees F and decreasing.with a steam generator. faulted-f. _Peactor i's'in mode 3 with Keff of.98 .g. D'.:r i n g a startup,.the reactor ooes critical.with the "Ro'd Insertion Low Limit" al arm ' li t - h.- During a reactor startup, a steam dump' fails open, result 2ng in a ecoldown-l QUESTION 5.05' (1.50) Concerning the'Emergencv Procedures. Expl ain why each of the f o12 cwi.ng. (0.5 each) -statements are FALSE:
- a.-
In general, a required; task as stated in a procedural step MUST'be completed prior to proceeding to the next step. b.- The procedures are applicable only in modes 1 through 3. c. The only entry points into the BwEP's are through BwEP-0. BwCA O.0 and emf R-G.1. !a = i 1 :, l' : l : 1 I 5 CONTINUED ON NEXT PAGE
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1,- :o.+. $ ]. C.4.,. L Es.iEMGF2Et4Cy,@ND,$BNQEM36_EL@N1_EyQLUllgUS - Pagg 12 ^ 112?. Y. ^ H. I^= s JOUESTION 5.06 (2.75) Answer the f o11'owing questions.concerning the 250 VDC: Power System a. WHAT'are FOUR conditions that will cause the "250-VDC BATT CHGR 123 . TROUBLE" annunci ator to al arm? - (Annunciator test is not considered (2.0) J . a valid ' conoitt on. ) _g b. There ssa 1/2 hour minimum time requirement'that the 250'VDC bettorv must supply power to the Turbine #1 D.C. Emergency Bearing i 011 Pump. What is this time limit based on? (.75) i. 1 QUES 11DN-5.07 ( 2. 50), . Answer ' the f ollowing questions concerning the Auxiliary Feedwater System: a. If 1B AFW pump-is running during a loss of.all AC power, WHAT indication do you have in the Control Room. If any, of how much AFW flow you have ' to S/G's. (Assume AFW flow meters to the S/G's are 2 noperabl e. Include, any appl 3 cabl e setpoints. ) (1.0) b. HOW will the AFW Pump IB starting circuit respond if AFW Fump 1B-I.' received an' AUTOMATIC stort s49nal.and the engine.does'not reach 330 rpm within'the 5 seconds crank time? (Include any applicable 's etp oi nt s. Assume engine will not start.) (1.5) QUESTION 5.08 (2.50) Answer ~ the f ollowing questions concerning the Subcooling Margin Monitor with respect oto the f ollowing given plant conditions: RCS pressure is 1200 psig, RCS Tave 350 degrees F, and the plant is currently being cooled down for a ref ueling outage. (1.0) Li st TWO inputs t o the Subcooling Margin Monitor. ca. b. 'Wnat THREE displays are available on the Subcooling Margin Monitor(1.5) primary display? (***** CATEGORY 5 CONTINUED ON NEXT PAGE
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y [ = - - p... x m.m... N gr 10 m-E '%_.EDEMENCX hNp_6BNQSd@(_E(@@IRQ(LJ11QUE. P Jf I~*.nl-( _. L 'OUESTION-5.09: i 3. OO) - TRUE or. FALSE:- If Ta' camp J contee1
- swi tch is in Pull-to-Lock on the' main control boara,, tiren 4 t < mak NOT. be coerated f rom the remote shutdown panel.
Explain. 'DOESTIDia. TJ10 (0.75) What THREE monit ors are used to indicate a S/G tube rupture? OUEST IC4J - 5.111 ?(1.00) Dur i ng - ref uel i ng ' operati ons, the Fuel Handling Building Crane area c>ona t or. ' (ORE-ARO39) al arms.- What automatic action occurs? ' QUESTION 5.12 (2.25) 'BwFR-S,1. " Response..to Nuclear Power Generati on /ATWS. ". immedi ate acti or.' If the RWST is StepJW has you. initiate emergency boration from the RWST. not available,. describe all contingency substeps contained in the RNO column in order to initiate emergency boration. QUESTION 5.13 (2.00) e Immed2 ate Acti on Step 4 of BwCA-0.0, " Loss of All AC Power," ha=- you vcr>4y - that the RCS is isolated. WHAT are FOUR indications / components that you .have to verif v to complete this step? (Include in your' answer the required condition / position of each component / indication.) .j. (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****/ j.:h p +,:e i Me
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__-'n. ~ po r -;5dgMEr GENE s' AND - A@NQRt1AL_PL6NT_gyQLyllQNS ' Page 14 M 2-s j_ ~ l. ' QUESTION b.14. _(1.75) l 1> of the f allow) ng' questions concerning BwOA ELEC-3, " Local l An ster -%c h 12 Emergencv Start'of'a Diesel Generator": St.co 2. C of i thi s procedure has you pl ace i sol ation' swi t ches 43!S-1. a. 4315-2, 4315-3.-and 431S-4 on the D/G Control Panel.in the ISOL q is the reason f or pl acing these switches. in - tne ISOL occation. ~WHAT . (Include the plant event when this would be done. ) - ( 1. 25) oosition? 6. TN* 'C411T ION j ust before_ step 2. c tell c 'you to pl ace Do Isolati on SwttcF 4310- A in the ISOL position ONLY AFTER the other 3 switches have been placed in the ISOL position. WHAT is the reason for following that order when placing the switches in the ISOL' posi ti on~;' (0.5) .mx.. c'w+pa pe ca., QUESTION .5.15 (2.00) iBwFR-C.1. " Response-to Inedequate Core Cooling," Step 9, has you c'epressariz e ai). intact S/G's to 160 psig. WHAT-1's.the reeson f or depressurizing all intact S/G's to loo PSIC? Incluce reasons f or depressuri::ing AND f or choosing 160 psig. QUEETION 5.16 (1.50) Procedur e BwOA ELEC-1, " Loss of. DC Bus", requires - a reactor ~ trip on loss of-ei ther 125 VDC Bus-111 or Bus-112. What is the basis.for requiring this- ' ac t i on"? QUESTION 5.17 (1.50) In 'accordance with T echnical Specifications 3/4.4.6. " Reactor Coolant System. L eakage", list the THREE Reactor Coolant System Leakage Detection Svstems that should be operable in Modes 1 through 4. 4: 'l (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) e 1: . j '. .-_.____.___._________._.__m___.__
e,. Fage 15 h :. g d E E p s N Q Y_ 6 0 Q _ 6]!U Q B 0 6 L _ C L 6 U I _ E'g g(. g l 1 Q U 5 126L DUESTICN 5.18 (1.50) LER desers bes a situation where the RHR pumos began cav2 tatireg A recent wh2 3 e p umping down the ref ueling cavity. Reactor vessel upper internals were ins talled 2 n the reactor and the head was off. A B-man was l oc al l y monatoring water l evel in the cavity and level remained above the reactor vessel flance throughout the pump-down. Exmlair why cavitation occurred in this situation. despite the fact that cavatv water level remained above the reactor vessel flante. OUCSTIsts 5.2? (1.00) Indiceted oressur2:er level is not al ways an indication of ectual hCS inventory. Several events have occurred in the industry where actual RCS i nventery has been less that that indicated bv pressurizer level.__ Assuming that pressurl:er l evel instrumentecion is f unctioning correctl y, explain how thi s could occur. J 1 l l (***** END OF CATEGORY 5 *****)
1 'a Page io-ts__Ekb!R _S161GtlE_32931_b9E_EL691 WIDE _gEUERIQ RE3F u ds l E< 1 L I T I ES ( 13*f1 DUESTION 6.01 (1.00) What.2s the bac2s for the Technical Speci f i c ati on minimum level in the Condensate Storace Tank? OUEST1ON 6.02 (O.50) Exclair the nt er l ock between the containment spray eductor suction valve -IL5019A U) and the auto a;t ar t si gnal for the CS pumo. QUECTION e.OT (2.00) Perm 2sc ve F-4 is actuated when a reactor trip breaker and its associat ed byoass creaker are both opened. Which FIVE of the following are functions that P-4 performs? 1. Actuates a main turbine trip. 2. Mairi feedwater isolation 3f Tavg..is less than or equal to 5c.4 degrees. 3. AussJisry Fegdwater actuation on 2/4 lo-lo S/G levels in any S/G. 4. LocLE in circuit to prevent re-opening the MFW valves which were cl o=ed by either an SI actuation or a hi-hi S/G 1evel. S. Frevides a signal to the Safety 2njection block and reset logic cir cui t to prevent re-actuation of auto SI after a manual SI reset. 6. Ac tuat e turbine trip steam dump control l er in Pressure mode. 7. Actuate turbine trip steam dump controller in Tave mode. 8. Causes turbine intercept' valves to shut and M5R spill valves to open. 9. Actuates a main generator trip. (***** CATEGORY 6 CONTINUED DN NEXT PAGE *****) __-_______m
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Pace.17 k ' h _Es9M OSTEdS_12931_6NQ,,P68NI WJpE,_GENEBlC M SFQNQJQ1!I11gS_J};31 1 O'UE5TIOt. 6.04 (2.00) a. 1* the power'sw2tch for the F2re Hazards Contro'. Panel-is "ON". sn-J the normal /f t re switch is in the fire position, list EIGHT' ..t ' 2 r.m cations that will be available at this panel. (1.6) l ' + NOTE - i+ indications are common to all available trains. 12 sting of l-cafferent trains will' be considered as one response.) A What two indications will. be available at the Fire ha:ards Control neneltif the. p7wer switch is in the "CFF" position? ( 0. 4 ) 'OUESTION 6.05 (2.00) .s List ce describe 2 controls or indications that use auctioneered low Tavo es an input. QUEST 2ON 6.06 (O.50) J n St en 2 of 'Bw r-O. "Wx Trip or Safety injecti on, " the procedure has you - e verif. turbine trio. If the turbine-did not trip.as enpected, what 1s.One -of the' FOUR possible actions that could be taken,'in accordance with b SwEP-0. to trip /stop the turbine? OUESTION 6.07 (1.50) With containment pressure at.1.2 psig, what actions must be taken in accorcance with Technical Specification ~.6.1.4, " Containment Systems - Internal Pressure"? Include time limits. QUESTION 6.08 (2.00) In oroer to close an RCP breaker, several interlocks must be met. One of these 2s that the loop isolation valve interlock must be satisfied. a)' State precisel y all condi ti ons/ i nterl ocks. etc. that must be met to satisf y the loco isolation valve interlock referred to above. bi .St ate the remaining interlock that must = be satisfied to close the RC,F breaker. Include setpoints. '(***** CATEGORY 6 CONTINUED ON NEXT PAGE
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DA__EbbullWygIEdg_jgg*s1_eND_E6@NI:WIDg_QgNE8]C Page 18 BggeONsJ eILIIJE5_J12*fl OUESTION 6.09 (O.75) How are the pump seals f or the diesel-driven aux 213ary feedwater pumo ' cooled? DLIESTION 6.10 (1.00) List FOUR loads supplied by the 250 VDC Distribution Svstem ONLY WHEN (4LL SOURCLE OF AC ARE LOST. QUES 7 ION 6.11 (2.00) Concerning the Circulating Water System: List'ALL conditions / actions that trip a circulating water pump. a. < 1. 0) (Betpotrts.are not needed) b. Li st the i nt erl ock s that must be satisfied to start a circulating water (1.0) pump. (Setpointn ARE reautred) QUESTION 6.12 (2.50) describe five conditions that will cause an SSPS General Warning. List or QUESTION 6.13 (2.00) l - List or describe 10 loads that woul d be de-energiz ed if the feeder breaker for bus 142 tripped on fault. Assume all loads on bus 142 were energized prior to the power interruption. i- '.lf( (***** CATEGORY 6 CONTINUED ON NEXT PAGE
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1 '/- ~ .4 Page 19' diaiPLASTJSYSTEMS_.JgQ%{,AND_EL@NI:WlDE_GEUE81p_ LEESE0!OI@lL]I1ES;J1331 m. QUESTIONi 6.14 (3.00) ,There are'four _(4) ' types of trips, that protect the ccre from a loss ci cool ant flow accident. One of these is called UNDERFREQUENCY. 'a) -Name'the other.three (3) trips. .bF Euplain ~the philosophy '(purpose) of having an UNDERFREQUENCY; trip'AND explain how it works. (logic, coincidence, setpo2 nt s,..i nt er l oc k s, etc.-) n GUESTION 6.15 (1.50) ~A.recent.LER describes al reactor trip that occurred while replac2ng-movable . gripper fuses.- Rod Control was in manual and the disconnect switch In the power cabinet.was open in preparation for fuse replacement when the RD attempted to move rods. A reactor trio resulted. Stc,te whet the cause of the reactor trip was, oAND expl a2 n why the trip occurred.. DUE5 TION-6.ie (1.75) progress whwn Source Range Nuclear Instrumental 2 c.n AL reactor startup is in channel N31 f ail s low. Prior to the f ailure, the nuclear instrument channel s were responding'as follows: ,N31;- 3 x 10E+4 and increasing, positive SUR N32 - oscillata.ng around 2 x 10E+2, oscillating SUR N35 - 2.x 10E-11.and-increasing, SUR oscillating positive 'N36 - 1.5 x 10E-11 and increasing, SUR oscillating positive
- N41'
'O and steady N42 --O and steady N43 - O and steady N44-- O and steady ' Evaluate per Technical Specifications, wnat actions must be taken. Include
- time. limits.
Assume that repairs will take 72 hours to complete. f n i q 1 1 1-(***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) .t-- ....j ___-_-_-_____w
cg p-(g;, ;.. ; ' 6. PLANTESY31EOS_j;O31_@Np_EL@NI;WJOE_ GENESIC Page.20 BskE9051ElLIIIEsall331 QUE57 ION-o.17-(2.50) A rec ent LER drn,cra tes a situat) on where an instrument air valve was inacuertently closed. resulting in a reactor trip. The valve.in question !supp))ed ai r to the following components: first stage reheat drain' val ve to 25. heaters. 25b heater level control, 26 heater l emergency drain valve and controller. 27 heater emergency drain valve, and 26B heatersdrein:vslve to.258 heater. . Ex p l ai n ' wh'y.1 r es of i nstrument air to these components resulted in e reactor trip. . QUEST I ON 6.18 (1.50) A recent LER describes a situation where loss of power to Instrument Bus-212 resulted-in a. reactor tr1p signal bei.1g cenerated,_when the reactor was in mode 5. Exolain why-a reactor trip signal was generated'in this case. . QUESTlGN 6.19 ( 3. 00) - -Per-FwAP 300-1. " Conduct oi Operations", what three actions must bc te. ken the SCRE/ Control. Room Supervisor deciden that a Unit'NSO shall leave wnen the "At the Lontrols Area." when his reactor is stable and under contr ol, to helo on the other Onit. ~ -QUESTION 6.20 (3.00) List 3 conditions identified in BwAP 300-1. " Conduct of Operations," which must be met to use the " pull to lock" position for testing on an active ECCS/ESF system.
- OUEST!ON 6.21 (3.00) is permitted to enter a high radiation area and who is Anv i ndi vi dual that exempt from issuance of an RWP must satisfy one of three technical What are.these speci f i cation requirements concerning radiation monitoring.
three requirements? .I. (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) 7 ,id; Y
_y. f Page 21 { @a FLANT SYSTEMS _j}O*f) _AND_FLAtjT WIpg_GENERl_C BEEE99h1BJLIIIE$_jl}31 DUESflON 6.22 O'>.75) Two hours into your shift. a B-man broke his leg and had to be transported 1a3 the hospital, which left you with only two 5-men on shift. How long. In accordance with Technical Specificat2ons. is it permissible to operate w2th this.Thift crew composition? DUFS110U 6.23 (1.00) If the Sh2ft Enoineer 2s incapacitated during an acci-Jent condi ti on, vu t h Rx at 20% power, who (title or position). If required, would act as Stat 2cn Director? : List in order of pref er ence. (Assume emergency has not been declared.) QUESTION 6.24 (1.50) l How is val ve position verified whil e perf ormi ng verification of mechanical lineups per BwAP 340-2. "Use of Mechanical and Electrical Lineups", for the f oll owinn valves: 5 0. 5 :' a. Open manual valve (Accessible) (0,5) b. Locked throttl ed manual valve (0.5) c. Inaccessible manual valve QUESTION 6.25 (0.75) A _ fire in containment occurs which requires an entry into containment under emergency dose conditions. The projected dose to the person entering containment is about 20 Rem. An A-man volunteers to enter containment based on the fact that he performed the same task 7 years ago and is aware of the requirements and procedures to compl ete the job quickly and efficiently. He received 26 Rem the last time he did an emergency entry and he has 35 Rem in his dose bank today. As the shift supervisor, do you let enter containment or not? Explain the re&soning for your choite. (***** END OF CATEGORY 6
- )
(********** END OF EXAMINATION **$*****44) i ~ 1 m____ 1
~ ~ ~ ~ ~~ ..t.. g... Pa9e 22 %_ BE9GIDB261HGIELES_.1Z31_IMESd99XNGd1GE -. y .12*el_991.._gadegugNIQ _ ilQ31_1EQuQSdENI6(g _g X 6d1 o 1 -u swas: 4.01 ( r. 00 ) preconditioned lim 2t i s def ined as the. ma::imum power level Max 2 mum fuel TO. 33) L ior.- a ' cumul ati ve 72 hours 1(0.33) - during the previous ' 7 ~ achieveed deys et 'oower coeration (0.34). IR5FERENCE' DwCA ;OD-4. pg. 6: .192OO2K119 ..(KA's) . ANSWER' d.O2 '(1.00) (0.25 ea) 'a. remain the same b.:.. decrease
- c.
- decrease d.
Increase REFERENCE ' Reactor Theorv. Ch 7, pp 7.10,'Dbj. 8 192002K114 ..' (KA' s ) I ANSWER 4.03 (1.00) because Eeta Bar effective decreases with increesed Larger GUR.-at EOL (0.5) Pu-239 and decreased.U-235 (0,5) credit given f or use of SUR and PERIOD f ormulas provided explanation includes the effect of Beta Bar effective. REF EREtK.E Nuclear Theorv, Ch 5, pp 35-36, Obj. G 192OO3K106 ..(KA's) ANSWER 4.04 (1.00) The RIl_s reduce the ef f ect of a rod ejection accident (0.5) by reducing the reacti vity inserted by an ejected rod (0.5) (***** CATEGORY' 4 CONTINUED ON NEXT PAGE
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l q- ____---___-_._-___.-______.______._-m-_________m-W
e-a. a. Papa 23 .A REAC ~ OR, PRIN;1PLES_ j.T/.l.,THERMQDyO6 mig 5 JZj; _6ND_GODEONEUI5,_11M1, jEUND60 SUI 665.Jf 601 REFERENCE Reactor Theory. Ch 6, pg 25. Db.t. 9 192OO5K115 ..(KA's) ANSWER 4.05 (1.50) initieI st rsep drop is due to buiIdup of fissaon product poisons in a clean core i 75) l e vt'i c oncentr et x on is due to depletion of burnable poison rods ( '. 75 ) REFEf ENCE FWR Fa <r demente) s - Reactor Theorv. Ch 2, pg 13 192007K104 .. ( V. A ' s ) ANSWEA-4.06 (1.50) a. boron concentration decreases with core life (.25) which makes DEW mors neoata'e (.25). Fa ssion product poison buildup with core life (.25) makes DLW l es+ negat2 ve f.25). . Boron concentration decrease is the dominent b. Boron concentration decrease is the dominant factor (.25) wh2ch m.skes DBW mer e neoat i ve with core'l2fe (.25>. REFERENCE PWR Fundamental - Reactor Theory, Ch 5. pg 20, obj 10 192904K111 ..(KA's) ~ ANSWER 4.07 (1.00) d REFERENCE Heat rr an c i er. Ch. 9. pg 41 193OO9K105 ..(KA's) AN,5WEP 4;OS (1.00) C (***** CATEGORY 4 CONTIN'JED ON NEXT FAGE *****)
z-Paco 24 A__F3E6CT QR, ERijgI[tEg_jZ*/.!_IHERMQQyN601CS .!?ht 6tJD. C90.'F 99C'JIS. 3193.L _1EWUD&dENI665,,E E801 i 1 REFERENCE Heat Tr ansf er. Ch. 6, pp 1C-21 193010K105 ..(KA's) ANSWER 4.09 (1.00) (0.25 ea) s. dec r ease b. remain the same c. DELETED d. increase e. decrease REFERENCE Heat Transfer. Ch 9. pp 24-25. obj. 8 193v08K105 .. (KA's ) ANSWER 4.10 (1.00) Eecondar, S4'ir-iency would increase (.5), because steam temperature tanc . pressure) would tacrease allowinc more energy to be obtained from eacn muu t amount c5 steam (.5) REFERENCE Thermedvnamics, Ch 4 pp 65 & 130 Obj. 11 193OO5K103 ..(KA's) ANSWER 4.11 (O.00) GUESTION DELETED REFERENCE I-1930061:104 ..(KA's) i ANSWER 4.12 (0.75) \\ i E2 2 minates ef f ects of instantaneous variations ir. readings I (***** CATEGORY 4 CONTINUED ON NEXT FAGE *****) e. - - " - - - - - - - - - - -. ~ _ _. _ _ ___ _
- f.. ' '..
L.,.. Fsge 25 2._SE6? I98. EE.l O91ELEE_12El_IdEEdQDYN@dlGG '4 JI31_6ND_ggdEQN(N15_11Qtl_1Egyp6dEUI@b5_Ef 801 REFERENCE Heet T ransf er. Ch 5. pg 23. Obj. 3 19A 08K1't2 ..(KA*s) ANSWER 4.13 ' ( 1. 00) (654-557)m97 degrees-F (+/- 2) REFERENCE CE Power Systems steam tables 193003K125 ..(KA's) ANSWER 4.14 (2.00) c) indicated T fails high (0.5) b) a nd: cated T f ai l s l ow (0.5) c) DELETED d) indscated T f eils Icw (0.5) o) T/C (0.251 f) T/C (0.25) REFEREN G PWR Fundamental s, Instrumentation and Control, Ch.
- 1. pg 39, 42 and oba 15 191002K113 191002K114
..(KA's) ANSWER 4.15 (1.00) b REFERENICE Systen Description, Ch 23, pg 12, fig 23-4 191001K101 .. (KA's) ANSWER 4.16 (1.00) C (***** CATEGORY 4 CONTINUED ON NEXT PAGE
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___y
3_- __ l.', Pace 26 nr..SE9C,7 Dh,l]'RjNCJELE _1231_ltjERMQpYNSMICE S .tI:o ; AUP_ C90[QNENIS_11231_,1EyNQ6dENI@LE_Ef @dl i REF ERE.NJ System Drstr2otion. Ch 15a, pp 21, 22 19100 7K108 ..(KA's) ANSWER 4.17 (1.00/ motor windtnos REFERENCE Svst e e Dm er i of i on 13. o.42. obj 1v.b 19100SK106 ..(KA's) ANSWER 4.18 (1.00). (0.5 esi i.ts normal position. 1. The red light means the breaker is not in 2. The amber light means that the breaker has tripped. RErEREMM DwAF.:E v-1. pg 2 191009k111 ..G.A's) ANSWER 4.19 (1.00) (.5 ea) k 1. Condstions are stable and under control 2. Continued operation would aggravate or worsen plant conditions REFERENCE BwAP 300-1. C.2.b.15 191003K1il ..(KA"s) ANSWER 4.20 (1.50) Indicated J rvel 2ncreases (h29her then actual) (0. 7 5) because of less (0.751 mass In the ref erence leg (causing DP in the bellows to decrease > 1 (***** CATEGORY 4 CONTINUED ON NEAT PAGE
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i ] 1 i 1 . _a
4 _ BE@QIQB_EBINGlE6ES_jZZ1_IMEBdggyggdJg5 Pega 27 l ZZ l _8N D_ CQUE00EUI 5_J19%. l _ j EUU p@dgN 1 GL S _ g l@dl REF ERENC E Instrumental 2cn and Control s. Ch 1. pp 25 & 36. Obj. 14 191002KlO9 ..(KA's) ANSWER 4.21 (2.00) a. ( f l uc t uat i on s in grid conditions causing) voltage regulator 2 ncr eas e in e::ci ter f i el d current (to maintain generator voltage) b. slightly reduce exc) t er 12 eld cur"ent by lowering the voltage a d.1 u s t er. (Will accept lowering tho base adjuster in manual.) (.5 ea) REFERENCE bwAR 1-19-B6 191005klO3 ..(KA's) i (***** END OF CATEGORY 4
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--_a
- g,. 4 u y, j f.g.. .Pcge 23' (a,q,, n..qpl.- E MER ENQf, AND, AgNgRtl@L_E% ANT _gyQLgTlQb@ ,L .;.1M?- ?- @e /E 4 ',s 44. r4 INSWER 5.01-(2.00) cny 2 E 1.0 ear' '.1... :: oms of flow (. 5).on Release Tank Flow Recorder (.5) (or Rel ease Teni. .; w F 1 ow. Integrator. (.5)) 2 . L qui d Radwaste Control' Panel Trouble alarm wi!I annunciate i4 the release setpoint has been exceeded. ~.3. T 9 cactive li cuid release valve (WX 353) (. 5) and. bypass : val ve '-(W A S96) ~ e.b) LindF:ste : shut. 4. %2 5 aJ at:m,. f or ORE-PROO1 REFE.RE NC E BwAR O-38-49 ' System Der:cr 2 pti on, Ch 48. pg 25 Ch 49, ppl25-26, 43 i 000059G008-000059G005 ..(KA's) . ANSWER 5.02~ (0.50) Ifolse. It in consi der ed "i dent 2 f t ed l eakaoe", tor. seat leakage can be isolated and pressure boundary leakage g can not be i solated. ) e REFERENC.E ' Tech spec 1.0, 1.15, 1.22 OOC 008EOO2 .000008G003 OOOOOBGOO4 ..(KM s) AN5WER 5.03 (2.00) 1. Certain reactor trips coincident with a f ailure of aute bus transfer could result in a loss of RCP' flow.(.5) But, if pumps were not lost until af ter a t2me delay (when the generator trips), the loss of flow would not be as serious because the reactor would have been shutdown f ear the duration of the time delay. (.5) ~2. Pumn overspeed can occur on a major LOCA. This can result in a missilo he ard. (.5) The chances of getting an RCP overspeed can be minim 2:ed by locking in the pump speed at 60 H: frequency until the generator traps. (. 5) (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) (' ~
y-- uq ay l b,,,9 % cc ~ Paco 29-l ' JE_ NDghf3EtJ[ANpiApNQBDAL,,P!,,. ANT _ESQLy119!g ~ L.ifIl E ' ' g i l REFEREfJCE l i I[ Syntem-Description, Ch.:eOb,' pp 29-29. obj.6 j .OOOOo7K301 - .OOOOO7 GOO 7 ..(NA's) l s uw, W.AN5WEF. 5.04 (3.00) 1
- p
. ;h. Nc. 3 ?ubi. ' Ye y + ' Vd., No i.; o.
- Yes i
'f.- . No 9.'. N-l
- h.
-Yes (,25 pt s each) i ~ REFERENCE ~ .? 1 DwOA'--PR 3 -2. Eritry Conditions OOOO24K302 OOOO24K301 OOOO24A205 ..(KA's) i i 'l ANSWER S'.05 '(2.50) s 1
- c..
- 5tmply starting the step is sufficient.
b.- Sorne procedures are app 12 caole in modes 4 and 5. .c, _ Entry is not allowed directly into BwFR-S.1. ,(will accepts entry into any BwEP is allowed per PRI-5 at the REP) i ' REFERENCE i 1 ERG Executive Volume, Users Guide, pp 5,.20-25 TwEP O Entry Conditions BwCA-0. 0 Entry Condi ti ons OOOOO7G012 OOOOO7GO11 .. (KA's) i l 4 1 { .y. (***** CATEGORY 5 CONTINUED ON NEXT PAGE 4****) i {! ! ' 0 h 1 i w 1?' i_2_... ~
O A,. Pace 20 9t_ _ ED,EE QENCf _6Np_8@NQSbby,PL@NT _ Ey0 9)) QN@ 9 4een: i l ANSWER 5.06 (0.75) a. 1. Low DC Outout Voltage (Charger Outaat oltage Low) 2. Hign DC Output Vol t age 7 Lcw HC Input Voltage (AC Input Ercarer Trip) 4 High AC Inout Amos 5. Blown Fuses (Any 4 &.5 pts eacts) b. The mini mum t i me per iod is based on Ma:n ar/: Feeapump Turcine Craat-Down time. (0.75) REFERFME Syrte' Description. Ch Bb. op 5 and 11. cb.7 Sd DwAR 2 0 -C] O OOOi t',8C,00t> 0000586004 .. (KW s) AiGWER 5.07 (2.50) a. a s flow 2 ncreeses to great er then 80 gpm to each E/6 [0.5]. a e-poweren status 12cnt will eneraire Ev.53. e'd r eset timo cel sv relev is energized ice- (19 seconds, f..~..'. r
- t..
n4ttemot to restart ?ngine bv cranh ng icr 5 se: ands !.J53. .'v e ( 4'- att emt ec starts will te al l owed IO.53. and then an " c cer c r sM. ' e. ar rr, loc'-cut wili energize in the Control Room 0.25J and the engine will sn (55 seconds) I. 25 's. REFERENCE System Descript2on. Ch. 26, pp 16 and 30, obj 6 and 13 000055A204 ..(KA's) ANSWER 5.08 (2 50) a. any 2 &.5 es: 1. RCS W.F:. Fr e?.sur e 2. Average of 10 highest CETs 3. Containment Pressure 4. Containment Radiation b. (0.5 each) 1. Fressure margin to saturation 2. Temperature margin to saturation 3. Trends (***** CATEGORY 5 CONTINUED ON NEXT F AGE
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'-----_m_
g;;; ~; ~~ L.. L4, Pace 31 5. EMERGENCY AND ABNORMAL _PI,Aljl_Ek'26UTigtjs - 1 J.}}'Al 1 4 REFEREtrE Sy+ t ur I ee rri pti on. Ch ~4b. pp _23-24 and Appendix A, obj 6 (4 7 SSPS P2 ant Spectf1c Supplement 0000 4A113 090074K208 ..(KA's> AN3WER 5.09 (1.00) F W se. Take local / remote swi tch on RSP t o local and control :s at REP. REFERENCE. Svsten Dever20 tion, Ch 62, pg 9, obj 4 OOvedBA121 OOOOe.,8K203 ..(KA's) ANSWER 5.30 (0.75) (0.25 pts each) 1. Steam Jet A2r Ejectors (RE-PRO 27) 2. E.'3 Blowdowr. tRE-PROOE) 3. Man n Stesmiines (RE-ARO22-23) REFERENCE System Description, Ch 49 pg 54. obj 146 OOOO37 GOO 5 000037A203 OOOO37A209 ..(KA's) ANSWER 5.11 (1.00) Upward movement of the crane hoist is inhibited. w REFERENCE -System Descr 2 0ti on, Ch 49, pg 42, obj 4a3 OOOO36K202 (KA's) ANSWER 5.12 (2.25) 1. St art the boric acid transfer pumo (.75) 2. Open emergency boration valve (CV B104) (.75) 3. Mazntain emergency boration fl ow path through normal charging (.75) (***** CATEGORY 5 CONTINUED ON NEY.T PAGE
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^
l .<~ Ptsgo 32 -5. EMEn6ENGL OND_AhNQRMSL_PL6NT_EVQLUTJgNS p n z,2 l REF EREf4CE - B w f R - S.' 1. st op 4 RNO column 00N 29G010 ..(KA's) ANSWER 5. 3 '. (2.00) 1. F ressurl:er FORV's - closed. 2. Letdown ori fice i solation valves - closed. (8149 A,B,C) 3. Letdown line 'I solati on val ves - cl osed. (CV-459. 460) 4. E.cets letdown 2 sol ati on val s es - closed. (CV-127. a153 A,B) t.5 er) REFERENCE EwCH O.v. steo 4 0000556010 ..(KA's) ANSWER 6.14 (1.75) a. J: 1solates the D/S cont ro3 s (.25) and indicators (.25) from tne P a a r. Contrci hoom t.25> 2n the event thet damage has occurred to ans DG cont r al r2rcuitrv (or centrol roon, nas been evacuated due to a f irer. (.5) b. Ths s nrevent s bl owing bacEup fuses (.5) REFEREf4CE BwCA ELEC-3. pg. 4. 5 OOC *068K207 000068G007 .. (KA's) ANSWER 5.15 (2.00) Depressurize all intact S/G's to cooldrwn and depressurare the RCS (.5) which will increase ECCS injection flow into the RCS (.5) and allow the SI Accumul ators to i nj ect. (.5) yet minimizes nitrogen injection f r om tne secumuistors (.51 REFEREf4CE EwFR-C.1. steo 9 BwFR-C.1 Lesson Plan, pp 27-29 OOOO74K311 OOOO74K310 OOOO74 GOO 7 ..(KA's) i (***** LATEGORY 5 CONTINUED ON NEXT PAGE
- 4*)
1 i i. .ee. -_.-________.m __m _.-m
L =. Paga ~C E _EME8GENGL @(Q @BNQRMAL PLANT EVOLUTIONS b 55'bI-o ANSWER 5.16 (1.50) A react or trio is necessary due to low S/G 1evels (0,5) since the Feedwater Regulating Val ves (0.5) and Feedwater Bypass Valves (0.5) fall closed on loss of either DC bus. REFERENCE BwOs ELEC-), pg 2 OOOO*3K302 ..(KA*si ANEWER S.17 (1.50) 1. The Containment Atmosphere Part icul ate Radi oacti ve Moni tor ing Gyt t em. 2. The Containment Floor Drain and Reactor Cavity Flow Monitoring System. 3. The Containe.ent Gaseous Radioactivity Monitoring System. (0.5 eai PEFERENCE l echni c al Specif2 cation? 3.4.6.1 OvvwYGOO3 .. ( K A " a 's ANSWER 5.18 (1.50) With the upper internals assembly installed in tt$e reactor vessel. flow i s restricted f rom the cavity to the reacto. coolant hot legs. (.75) This flow restriction caused a vortex to f ortn, drawing air into the suction of the RHR pump, causing cavitation to occur. (.75) NOTE: credit given for concept REFERENCE Byron LER 59-007 Ov0025K101 .. (K A's) (***** CATEGORY 5 CONTINUED ON NEXT PAGE *448*) = e s m o s.em __m.___________m___________-__-_.m .._mm__.___._____--_m mm
e l Ez. _Ebg*cmycy..eurt_6ppoE0eL._ELGUI gyO!=LJ11QNS Page 34 .G%) 1 i l ANEWEF 5.19 (1.00) I (any cf the following & 1.0) j
- 1.. Dt ri no c ol d shutdown, a combination of a vacuum f ormed in the PZR ( 5) ar 3 gasses coming out of solution at RCS high points (.5) may cause F.'F level to i ndi cat e erroneously high.
2. Dertng natural circulation cooldown (.5) a void may form in the vessel head (.5) causing PZR level to indicate erroneously high ~. Wi th a spray valve or PORV stuck open (.5) a void may form in the RCE (.5) c a _*c i n g PZR level to ind2 cate erroneousiv high Di tier answers accepted on a case bcsis REFERE!.C E Syttar De:cr i t.t i on. Ch 14. pp 31-32, ob) 25a OO:028K!O3 ..(KA's) 4 (***** END OF CATEGORV S
- 5*)
w-6,__EL6bI_SY5IEUS_13031_0Np EL8bl: HIDE _GENEBig Fage 35 BESE9651RJL111ES_11131 ANSWEF 6.01 (1.00) A mint.um water l evel (of 40%) ensures that sufficaent water (2OO. 0 X' gal. > m is ecstlable to maintain the RCS at hot standby conditions (.25) for 9 hours (.25) wi t h steam discharge to the atmosphere (.25) concurrent w2th total 2oss-of-offsite power (.25). REFERENCE Techni cal Spo: 14 2 cat 2 on 3.7.1.3 and Basis. 05cuv0 GOO 5 ..(KA's) ANSWFR 6.02 (0.50) C5 eductor val ve must be fully open (.25) to enable suto start (.25i REFERENCE Svstem Descr2ption. Ch 59, pg 22 and obj Bd 01 ~. COOK 101 013OOOK105 ..(KA"s> nN SWE F. 6.03 (2.00) 1.2.4.5,7 (.4 ea) -REFERENCE System Description, Ch 61, pp. 34-35= 012OOOK412 013OOOK401 013OOOK115 .. (KA' s) 1 l l l 1 I i i 4 4 (***** CATEGORY 6 CONTINUED ON NEXT PAGE
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t l l 1 l
7, -- [. j )
- j
.c Pcg3 36 6 __EL6NI_EfSIE5$_1}Qhl_8ND,[(@NI;W1pg_GENgBIC t BESEOdWlBILillEE_IIIZd l 1 1 ANSWER 6.04 (2.00) (Anv 5 at 0.2 pts eacn) c. 1. RC5 W. R hot leg temperatures 7. RCS W. R cold leg temperatures 2, PZR press.(Ch-455) 4 PZR level (Ch-459) 5. S/G 1A press (Ch-514) j c. S/G 1A W. R level S/ts 1B press (Ch-525: E. 6/C 1B W. R level c. Source Range (Train B) 10. Power Range (Intermediate Range) (Train bi (accept " post accident neutron monitors") (0.2 ots each) b. 1. Source Range (Train B> 2. Power Range (Intermediate Range) (Train B) REFERENCE S y s t e... Descriotton. Ch 62, pg. 17 and obj 6 BwAR 1-10-El 086000GOVE ..(KA's) ANSWER 6.05 (2.00) Tavg-Tref meter on PMO2J (turbane panel) C-16 setpoint exceeded annunciator (turbine loading stop alarm) (1.0 ea) REFERENCE Syster Description, Ch 12, pg 27, obj 6 BwAR 1-14-E3 OO1000A102 OO1000A101 ..(KA's) ANSWER 6.06 (0.50) env one 9.5: 1. Manually trip the turbine. 2. Manuallv run back the turbane at maximum rate. in PULL DUT position. Place EH pu,mps 3. Ini tiate steam 12 ne isolation and manual]y close MSIV bypass val ves. 4. (***** CATEGORY 6 CONTINUED ON NEXT PAGE
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) i L
a.s ;... 6, FL@g1_SygIEL1S_1jQZl_@ND_[t@UI WlDE;_GENEBlG Page 37 3 ~ - BESE2951016111ES_11231 i - REFERENCE BwEP-0. Step 2 RNO column 045ev0G014 045000A301 ..(KA's) l ANSWER 6.07 (1.50) Restore pressure to within limits within i hour, (.5) or be in at least bot standby within the next 6 hours (.5) and in cold shutdown within the f all ow2 ng 30 hours.(.5) REFERENCE Technical Specification 3.6.1.4 103000 GOO 8 103000 GOO 3 ..(KA's) ANSWER 6.08 (2.00) a) hot leg val ve open (0.15) and (0.15) cold l eg valve coen (0.15) OR (O.10) col d leg va)ve shut (O.151 arid (O.15) bypass val ve open (O.15) b) FCF oij 11ft pump discharge pressure (0.50) is et least 600 psig i O. 5CO REFEREf4E -System Description. Ch.13, pg. 32 and obj 20a OO':OOOK411 OO3OOOK403 ..(KA's) ANSWER 6.09 (O.75) The pump seal s are cooled by allowing a small amount of AFW to flow alcng the shaf t of the pump. REFERENCE l . System Description, Ch. 26. pp. 11, 14 and obj 4 061000 GOO 4 061000K106 ..(KA's) (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****> 4 4
62__ EL 9NI_syglgdg_1gg31_eNQ_EL6NI:W1pE_QENEEJC Pego 3B BE5EQNSIBILII1E5_11I31-L ANSWER 6'.10 (1.00) Any fou-of the f ollowi ng five (0.25 apiece)
- 1) comouter inverter
- 2) maan. turbine DC emergency oil pump 31 generator emergency air side. seal oil pump
- 4) SG feed pump turbine emergency bearino o21 pumps Se maan condenser vacuum breaker valve REFERENCE System Descript3on. Ch. 8b. po 8 and App.
A. obj 2 Ot'v00K2v1 .. (KA' s) ANSWER 6.11 (2.00) a. Anv four of the f ollowing six (0.25 aptece) 1. Manual trip 2. Pnase overcurrent 3. Ground overcurrent 4 Loss of enciter f2 eld b. Bus LN (4KV) 6. (12") H2-H1 different2al level acects associ at ed travel 2 ng screen b. 1. Dzscharoe valve must be closed (0.5s
- 2. - Non essenti al service water pressure to the pump seals must be at least 20 psig (0.5)
REFERENCE System Description. Ch 39. pp 16 & 17, obj 3, 4 075000K401 075000 GOO 7 .. (KA's) f (***** CATEGORY 6 CONTINUED ON NEXT PAGE
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i I k i l-
+ . @,1 Pagef39 s ht._ELebIiSYSIEDS_flg31_@NQ_EL@N1; Wipe _GENEB1G' BESPONgikIL111Eg_JII31: 3 W ' ANSWER-6.12-(2.50)- Any five' of the f oll owing ten, (0.5 apiece)
- 1. '. Removal 1offa: printed circuit card
-2. "A bspass1 breaker-for a train. being. closed 3. Loss of continuity:through the ground return. fuse
- 4... Pl acement ' of. switches' within a train to positions used during testing-5.-
Lcse of'.'a power: supply. '6. .Incut. Error Inhibit switch not in NORMAL 7. Logic A' switch 1not.in OFF 8.1 Permi ssives switch not in DFF - '9.. Memories switch not.in DFF
- 10.. Mode Sel ector swi tch not ' in OPERATE
- NOTE: ens enswer 6 thru.10 precludes answer 4 fnr credit.
.If answer 4 is given,. answers 6 thru 10 get no credit. REFERENCE System Description, Ch. 60a, pg 15 and obj 6 012OOOGOOS ..(KA's)- l ANSWER 6.13 -(2.00) Any 10 of.the following: (0.2 aptece) La) 4160V/480' transformer (.1) to bus 132X (.1) L .b) centrif ugel f charging pump 1B c) saf ety injection pump 1B d) residual heat removal pump 1B e) control room refrigeration unit OB f)' containment spray pump 1B g) comoonent cooling water pump 1B h). feed to component cooling water pump O - 1) ' essent i al service water pump 1B j) auxiliary building ventilation supply fan OB k) aux 211ary building ventilation exhaust-f an OF
- 1) 4160V/480 transformer (.1) to bus 132Z (.1) 1' REFERENCE L
' System Description, Ch.4, pg 45 and obj 12 062OOOK201 ..(KA's) (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
r. - =- t 5 Pace 40 I L>2.__EL6NT _ SYSIEUS_17931_6NQ_ELBNI;Wlpg_GENESIG . BEEEQNS]B16111gS_Il}31 j ANSWER 6.14 (0.00/ a) 1..UNDERVOLTAGE (0.5) . 2. LOW FLOW (0.5) 3. RCP BREAKER OPEN (0.5) b) The underfrequency trip provides reactor prot ec tion f ollow1 ng a n.ajor frequency disturbance. By tripping the RCP breakers, a minimum coastdown time is ensured (0.75). All RCP breakers trip and the reactor trips if an UF condition -below 57.0 H: (.51-exists on.2 of 4 RCP buses (0.25). REFEFENCE System Description, Cn. 60b. pp 13-16, obj 4 012OOuK402 ..(KA's) ANSWER 6.15 (1.50) (0.5) The cause of the trip was negative rate due to multiple dropped rods. The rods dropped because the movable grippers remained de-energized and the movement was demanded. fl.O> stationary grippers de-energized when rod REFERENCE Braadwood LER 88-016-00 OO1000K103 OO1000K201 ..(KA's) ANSWER 6.16 (1.75) Within 1 hour (.25) commence a shutdown to be in hot standby (.25) within the next 6 hours (.25), hot shutdown (.25) within the following 6 hcurs (.25) and cold shutdown (.25) within the subsequent 24 hours. (.25) REFERENCE Technical Specifications 3.3.1, 3.0.3 015000 GOO 5 ..(KA's) (4**** CATEGORY 6 CONTINUED ON NEXT PAGE
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I 4 I'
Pcgo 41 PLANT _SyglE05_11931_SND_PL@NI;WlDE_GENSElC [ BESEONSIBIL,Illgg_J1}%1 ANSWER 6.17 (0.50) Lose of instrument air resulted in the emergencv drain valves repositioning to the open position. (.5) lhls directed the flow from the heaters to the condenser instead of to the heater drain tank. (.5) When the HDT level ' roached the 10-2 setpoint. heater drain pump discharge valves closed. (.5) With loss of HDP input to the feed system, (.5) steam generator l evel s dropped until the S/G lo-lo trip setpoint was reached. (.5) REFERENCE Brsidw od LEF ES-019- 00 078000K302 ..(KA's) ANSWER 6.18 (1.50) to source rance N32 arid Loss of bus 212 results in loss o# control power intermedi ate range N36. (.75) This results in the high flux b1 stables being de-energi:ed, generating the reactor trip signal. (.75) REFERENCE Braidwcod LER SP-OO3-OO 015000K201 ..(KA"si ANSWER 6.19 (3.00) 1. L2 censed operator must be specifically assigned to monitor the controls of the unattended unit and respond to all unit alarms. 2. Same licensed operator must remain within line of sight of unit's front panel. 3. Review the status of the unattended uni t f rom within the unit's "at the controls area" on a periodic basis (5-10 minutes). REFERENCE BwAP 300-1. C.3.m.9.b 194001A111 ..GIA's) t i (***** CATEGORY 6 CONTINUED ON NEXT PAGE
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s a iz__E66NI_$yylgdS_f_3931_@Np_EL@N1;W1pE_gENEBIC Page 42 EEEE9BS.I.bl6111E5_11}%1 .i ANSWER .6.20 (3.00) anv 3 & 1.0 ea '1. Test se per a regular procedure. 2. Imcrac ti cal to modifv equipment or procedures to allow testing in nce mal alignment. 3. Orerator is available to return the switch immediately when test is coroleted or if interrupted. 4 Enter LCD for that component / system 5. Enr ure that other train in operable j 6. Nafy Shi4t Engineer or designee REFE.4ENCE DwAP 300-1. C.3.cc.3 190'01K102 ..(KA's) ANSWER 6.21 (3.00) Indivi cual s permi tted to en'ter shall be provided with or accompanied by one or more of the following: 1. Radi at i on monitoring device which continuously indicates the rr,01ation dose rate in tre area. (1.0) 2. Radiation monitoring device which continuously integrates the radiation dose rate in the area (0.5) and alarms when a preset integrated dose is received (0.5). 3. Ar. individual qualified in radiation protection procedures with a i radiation dose rate monitoring device. (1.0) I REFERENCE Techni c al Specification 6.12.1 194301K105 ..(KA's) 3 l AN5WER 6.22 (0.75) l 2 hours REFERENCE ) Technical Specification 6.2.2.a and Tabl e 6.2-1 194001K116 ..(KA's) i l l 1 i (***** CATEGORY 6 CONTINUED ON NEXT PAGE 14#**) 1 l 1 1 - - ~ - - - - _ - - _ _ _ - - _ - _ _ _ - _ _ _ _ _ _ _ _ _ _.. _ - _ _ - _ - _ _ _ _ _ _. _ _ _ _ _ _ _ _ - _ _ _ _
,m PLAN 7,9ySIEIMS_,GQ31_M D_EL MI WJDE_GENERJG Paga 43
- 4..:
fiE p_(t@ lklL11]Eij_j G Z1 1 1 I I ANSWER 6.23 (1.00) ) 1. Shift Foreman 2. St ation Control Room Eng2neer (SCRE) to.5 ot s each. order i mport ent. 1/2 credst af out of order.) REf-ERENC E Ew P 1C'. E.I 19 % O1A116 .. (k W s) ANSWEP o.24 (1.50) a. At t emot to close salve (0.25) then return 2t to full open posi ti on (0.25) b. Observe lock 2 n pr oper position (0.25) and val ve posi ti on indicator other than full' c1csed (0.25) c. Transf er of ini t.i al s from previous 12neup (0.5) REFERENCE UwAP !.40-2. pg 7& fl 194GO1K101 .. (K A's) ANSWEF 6.25 (O.75) No. An acute whole bodv dose equivalent i n e:-: c ess of 25 Rem shall be limites to once in a lif etime. REFERENCE e BwRP 1*: OO-A1, pg 26 194001K103 194001K104 ..(KA's' (***44 END OF PATEGORY 6
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(******4*** END OF EXAMINATION
- 41*****4)
2 4 + TEST. CROSS REFERENCE Pego 1-09EM 3 sti YAWE BEEEBEL4GE_ 4.01 1.00 9000079 4.02 1.00 '9000122 4.03 1.00 9000129 4.04 1.00 9000100 4.e5 1.50 9000135 4.Oc-1.50 9000136 4.07 1.00 9000119 4.99 1.00 9000120 4.09 1.00 9000121 4.10-1.00 9000124' l 4.11 O.00 9000125 4.12 O.75 9000126 4.12 1.00 9000131 4.14 2.00 9000094 4.15 1.00 9000116 4.1e 1.00 9000117 4.17 1.00 9000118 4.le 1.00 9000123 4.19 1.00 9000127 4.20 1.50 9000128 4.21- -1.00 9000137 22.25 5.01 2.00 9000077 -5.02 O.50 9000081 -5.03 2.00 9000090 5.~ 04. 3.00 9000097 5.(A 1.50 9000098 5.06 2.75 9000099 5.07 2.50 9000100 5.05 2.50 9000101 5.09 1.00 9000102 5.10 C.75 9000103 5.11 1.00 9000104 5.12 2.25 9000105 5.13 2.00 9000106 5.14 1.75 9000107 5.15 2.00 9000108 5.16 1.50~ 9000109 5.17 1.50 9000110 5.18 1.50 9000113 5.19 1.00 9000134 33.00 6.01 1.00 9000073
- 6. O2 O.50 9000074
- 6. O3 2.00 9000075 6.v4 2.00 9000076 6.05 2.00 9000078 6.06 O.50 9000080 6.07 1.50 9000086
- 6. OS 2.00 9000088 6.09 0.75 9000089
i ( = 1 TEST CROSS REFERENCE PC92 2 99ESI109 ygbyg SEEEBENGE_ e.10 1.00 9000090 6.11 2.00 9000091 '6.12 2.50 9000092 6.12. ' 2.00 9000093 o.14 3.00 9000095 6.15 1.50 9000111 6.le 1.75 9000112 6.17 2.50 9000114 6.18 1.50 9000115 6.19 3.00 9000082 6.20 3.00 9000083 6.21 3.00-9000084 6.22-O.75 90000e5 6.23 1.00 9000087 6.24 1.50-9000132 6.25 0.75 9000133 43.00 =*a-w = - + - G i l l l j } l i J j
'9 U. S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINHTIGN REGION 3 FACILITY: Br a i.d.tyo gd _1_( 2_ _ _ _ _._ _. _ _ REACTOR TYPE: EhlR-WEGe________ _______ DATE ADMIN 5TERED: @841;f95___________.___. _ IN$} BQsllpNS_.lQ_CSND.I DeJE; Use separate paper +or the answers. Write answers on one s2de on1v. 5t sol e ouesti on *;heet on too of the answer sheets. Points for eacn ouest2cn are indicated in parentheses after the questi on. The passing gr ade requires at least 707. in each category and a final grade of at least 80%. Examinat i on papers will be picked up sax (6) h our s.- after tbe eu amination starts. % OF
- CATEGOR,
% OF CANDIDATE'S CATtiGORY __yet,ug_ _Iglek ___SggEE___ _yOLUE__ ______________G615 GOBY ________.._____ _27tZ5__ _Edz95 ___._____ 1. REACTOR PRINCIPLES (7%) j THERMODYNAMICS (7%) AND COMPONENTS (117.) (FUNDAMENT ALE EXAM) "2. EMERGENCY AND ABNORMAL PLsNT .?Z.99__.27 ?4 EVOLUTIONS (27%) _58 99__ _$8,_61 ______.__ ~. PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC 3 RESPONSIBILITIES (10%) _ _9 8. 2 5._ __ TOTALS FINAL GRADE All work done on thi s ex amination is my own. I have neither gi ven nor received aid. Candidate's Signature MASTER COP)
n NRC RULES AND GUIDELINES FOR LICENSE EX4MINATIONS Durinn the administration of this examination the f ollowing rules apply: 1. Cheat i ng on the ex amination means an automatic dental of your application and cou) d result in more severe penalties. h 2. Rest-ocm triou are to be limited and eniv one candidate at a time may lea.e. You must avoid all contacts with anyone outside the examination roon-t o' a voi d even the aopearance or. possibility of cheating. 3. Use black ink or dark pencil only to facilitate legibl e reoroducti ons. 4 Print your name in the blank provided on the cover sheet of the e:; a mi.n at i on. 5. Fill in the date on the cover sheet of the enaminetton (if necessarv). 6. Use on1/ the paper provided for answers. 7. Pr i rst vour name in the upper right-hand corner of the first page ot each secti on of the answer sheet. 8. Consecuti ve} y number each answer sheet, write "End of Category _ _. " as apprcoriate. start each categorv on a new page, write only on one side '~ of ine paper, and write "Last Fage" on the last answer sheet. 9. Number each answer as to cateoorv and number. for example. 1.4.
- 6. 3.
- 10. Skip et least thr ee lines between each answer.
- 11. Seow ate answer sheets f rom pad and place f inished answer sheets tac 2 down on vour desk or table.
l
- 12. Use abbreviations en1v af thev are commonly used in f acility literature.
- 13. The ooirt value f or each ouestion is inoicated in parentheses after the l
ouest i on and can be used as a guide for the depth of answer required.
- 14. Show all calculations, methods. or assumptions used to obtai n an answer to rr.athemati cal probl ems whether indicated in the question or not.
- 35. Parts al credit may be given.
Therefore. ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLANK. i
- 16. If oarts cf the examination are not clear as to intent, ask ouesti ons of the examsner on1 y.
- 17. You must sign the statement on the cover sheet that indicates that the work is your own and you have not received or been given assistance in comc l et i ng the ex ami nat ion.
This must be done af ter the examinatt or. has.
- been comp 3eted.
( I f
- 16. Whnn.<ou complete your e::ami nat i on, you shall:
a. .~,ss.emble your examination as follows: 1 !? E::am ouesti ons on top. .2) E::am aids - f i gures, tables. etc. 4 ~, ) Answer pages including figures which are part of the answer. b. T urn in your copy of the examination and all pagen used *c snswer the examinat. ion questions. c. Nurn in all scrap paper and the balance of the paper that vou d1:1 not use for answering the questions, d. Leeve the examination area. as deilned Dv the examiner. 11 af ter leaving, you are found in this area while the examination is st211 in progress, your license mav be denied or revoked. 4 e e+ e __.______a
Pcgo 1 ef 5-4 DeIe_SUEEI BE8CIQtt_INEQBY_EDBduLe5: SUR(t) P = P,t/T p,,p 3 O EI th SUR = 26.06/5 p = -------- 73--issions/sec 3.12 x 10 f 8 2 1 eff 1 -(B L 2' " ~~ * ~~~~~ p = th 1' + 15 th 2 2 y 1+ (B L th K~I -(B L ) =e f p = _____ P, K K 60 = In 'bbOfb-- ,,,- C N 3 E I,j g 3/SI, initial ]I 0 T "~ ~-~~ C (1-K,4fg) =C2 (I~Keff2} (p g 'itael__ initial 2 - -- + - -- - 8' (- I + AL-1!!-) 1 of 1 ap AL "r " f at p At at at T~Ei~~~p =P ~ = ( P, p Pth ' N 1 O K,,, Ieff 9 1 e e i i i
Pcgo-2 cf 5 c L !. ', ".,, D8Ie_SUEEI IHEBt20DYNet31CE_8ND ELUIQ_DECH8 NICE EQBURLGE: 6 = 4 'a h ' 2 w.La7 ,g. _______________________ 1 In R /R -In-R /R 2 3 3 2 - + -------- + -------- O=UA (AT )- K K K 2 3 U=5c (AT) P b = a d A R" n. _Le_:_6 '6 n - - !B--- "1-) CE*l-- (h -h _eut g ) ideal Q (h -h in g actual 1 1 22 T T supplied g 2 4 - pAV pAv =pAV g g 3 222 3 Q,f5 = xA aT,TEf = KA ap J ne A = KA & = KA,fAP p x nc . eI_1Lel_:_eI_1guti 3 gb- -- I 47 " AT (in) 8.Bxto in (--------) AT (out) Gr kAAT G = ----- T"I - T " = --- P 4k Ax A ATtotal Q = gy--- gg-- AX a b n + ___ K K K a b n I e i
p g. Pc93 3 Of 5 Dele _geggy GENIBIEUGeL EutlE.LeWS (N _ H (N ) P __1_) _ 1.. &_1 1 1 . _1 W' N A (N H (N P 2 2 2 z 2 2 BeDieI1QN_eND CUED 1EISY_EQBdWLBE CV =Cv R/hr = 6CE/d I, = 10 g g 22 e ~8* e = QLlutten_Batt I=I ill" C=Co= o Vol ume 10 A = AN ~ A=A e 0 GDNYEBEIQUE: 3 1 gm/cm = 62.4 lbm/ft Density of water (20 C) = 62.4 lbm/ft 1 gal = 8.345 lbm ~ 23 1 f [ = 7.48 gal _ Avogadro's Number = 6.023 x 10 1 gal = 3.78 liters Heat of Vapor (H O) = 970 Btu /lbm 2 1 lbm = 454 grams Heat of Fusion (ICE) = 144 Btu /lbm ~ e = 2.72 1 AMU = 1.66 x 10 grams w = 3.14159 Mass of Neutron = 1.008665 AMU 1 KW = 738-ft-lbf/see Mass of Proton = 1.007277 AMU 1 KW = 3413 Stu/hr Mass of Elecfron = 0.000549 AMU 1 HP = 550 ft-lbf/sec One atmosphere = 14.7 psia *= 29.92 in. Hg i HP =.746 KW 'F = 9/5 *C + 32 1 HP = 2545 Stu/hr
- C = 5/9 (*F - 32) 1 Btu = 778 ft-lbf
'R = *F + 460 -16 1 MEV = 1.54 x 10 Btu 'K = *C + 273 ~ h = 4.13 x 10 M-sec 10 1 W = 3.12 x 10 fissions /sec g = 32.2 lbm-ft/lbf-sec c = 931 MEV/ AMU 1 inch = 2.54 cm C=3x 10 m/sec ~0 2 l r = 0.1714 x 10 Btu /hr ft R
Pcg3 C cf.5 Del 8_5BEEI-eVEB&GE_IBEBdeL_CQNDUCIIVIIY_1El E BatstLal Cork O.025 Fiber Insulating Board 0.028 Maple or. Dak Wood 0.096 Building Brick 0.4 Window Gl ass O.45 -Concrete 0.79 1% Carbon Steel 25.00 1% Chrome Steel 35.00 Aluminum 118.00 223.00 Copper Silver 235.00 Water (20 psi a, 200 degrees F) 0.392 Steam (1000 psia, 550 degrees F) 0.046 Uranium Dioxide 1.15 Helium O.135 Zircaloy 10.0 dlSCELLONEQUS_INEQBdellON: E = me KE = 1/2 mv PE = mgh V =.V + at j O Geometric Object Area Volume Triangle A = 1/2 bh /////////////// Square A=S ///////////////// 2 Rectangle A=LxW /////////////////l 5 wr 2 /// //////////////l Circle A Rectangular Solid A = 2(LxW + LxH + WxH) V=LxWxH z Right* Circular Cylinder A= (2 nr2)h + 2(wr2) V = wr h A = 4 wr V = 4/3 (wr2) 2 Sphere ///////////////////////////// V=S Cube i i
- U-
Pcgo 5 cf 5 DOI 8_EdEEI d1SCELL&WEQUS_INEQBdel10N_1continuedt: 10 CFR 20 Appendix B Table ! Table II Gamma Energy Col I Col II Col I Col II MEV per Air Water Air Water Material Half-Life Disintegration uc/ml uc/ml ue/ml uc/ml Ar-41 1.84 h 1.3 Sub 2x10
- 4x10 '
~ ~ ~3 Co-60 5.27 y 2.5 S 3x10 1x10 1x10 ' 5x10 ~ ~# ~3 ~3 -20 ~# I-131 B.04 d 0.36 S 9x10 ' 6x10 1x10 3x10 ~ ~# ~3 3x10 Kr-85 10.72 y 0.04 Sub 1x10 Ni-65 2.52 h 0.59 5 9x10 4x10 3x10 1x10 * ~# ~3 ~8 ~ ~1* -6 Pu-239 2.41x10' y 0.008 S 2x10 1x10
- 6x10 5x10
-22 ~ ~3 ~ll ~# S 1x10'E 1x10 3x10 3x10 Sr-90 29 y ~# Xe-135 9.09 h 0.25 Sub 4x10 " ~ 1x10 > 2 he -5 -10 -6 Any single radionuclides with T 3x10 9x10 1x10 3x10 which does not decay by alpha br ~ spontaneous fission Neutron Energy (MEV) Neutrons per em Average flux to deliver equivalent to 1 rem 100 mrom in 40 hours 6 thermal 970x10 670 6 0.02 400x10 290 (neutrons) 6 0.5 43x10 30 10 24x10 37 g,2, ,,g 6 Linear Absorption Coef ficients p (cm~l) Energy (MEV) Water Concrete Iron Lead 0.5 0.090 0.21 0.63 1.7 1.0 0.067 0.15 0.44 0.77 1.5 0.057 0.13 0.40 0.57 2.0 0.048 0.11 0.33 0.51 2.5 0.042 0.097 0.31 0.49 3.0 0.038 0.089 0.30 0.47 l } i
d Pcgo 4 1, RE4CTOh PR I NC I E'LES j ?*f } _TtjgBMQDYbAMI CS 37'n _9N DJODE 90ENI 5_j il*f l_ j ELJNDBME NJ @L S _ E l eM.t QUES 1IGN 1.01 (1.00) For the t oll owi no power historv. select the oraph (a-d) that represer.tr wnst :enon concentration would look like versus time. (Circle the correct letter) SEE FlWEE l 01 OUE ST J Or4 1.02 (1.00i Wijj the shutdown margin INCREASE, DECREASE. or REMAIN THE 54ME f or e:cr cf the f c4 l owing condi ti ons? (Consider eacn cese separately')
- a. Loed r ej e-ct i on from 100% t o 90% power. control rod position Jowere end 1 -a. 9 ecuel s orogrammed T-avg.
- b. The reactor is steady state at 50% power when a small dilutior. occurs with contr ol rods in. automatic.
- c. The reactor is steady state at 50% cower when a small dilution occurs watn control rods in manual.
- d. Fesctor power helding steadv at 50% f oll owi no a startuo. wi th - :: e ncn 2 ncreasing.
i DUESTICf4 1.03 (1.06) j For two ecu1 valent pos2 tive reacti vity additions to a critic.al reactor, wili the SUR be the same, larger, or smaller at EOL as comoared to BOL? Explain your choice. Use of appr opri at e f or wul as i s acceptabl e. QUESTION 1.04 (2.00) Durino a startuo the reactor is critical at 3Ov0 CPS on the source range 2nstruments when a steam dump valve fails ooen. DESCRIBE the effect on and T-avg and WHY the=se effects are seen. Continue your reac t or power action. exol anat2 on until stable condations are reached with no operator ( As surre the reactor a s undermoder ated. at BOL and no reector trip cc:urs.) ( 4 t 9 (***** CATEGORY l CONTINUED ON NEXT PAGE
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l! 1 ~l
\\ i I I Psm w/. p% _\\ 4 i 'l 1 /% A, y i.$.. f X t k. (w l i, J 1 w nA o o a a e => ro k f \\ 4 n wk em r$l \\ r 1 gup%,,:!.. W weew:ere mswent;c C L lo0T+ 1:4 4 6. \\ v So 44 L. is a t<> mo - 3n en e r n s wl. m j h L, / s 1 w g E', i e im 644 4 e Epa l.o1 i i I )
Pace 5-1,...._ msg I 911_ f S ING IPLG E _.1231_It!GBOO Q1N 9d ig g CL i _eN Q _gOdP QN jidIg _111% l_1E(JN Q6dgN I6(@ _g,X 601 OUE ST I Ot< 1.05 (1.00) Dr.e r eP Eon i or having Rod Insertion Limits (RIL) is to ensure that tt.e catential effects of rod misallonment on accident analvses are limited. EXFLAIri how RILs reduce the severity of an accident. (Include in your answer which accident is considered.) DUEETIOf. 1.06 (1.00) Per Ew.). Rod-4. " Dropped Rod Reccvery". what i s the ma::1 mum f uel creconcitioned limit defined as7 (Assume th2s is during the initial power ascenston af ter a refueling outage.) QUE51 ION 1.07 (1.00) the f ollowing prevents DNB f rom occ,urrino during normal plant Which DNE of operat i ons?
- a. Min: mum temperature for cri t 2 c al i ty (550 degrees F)
- o. Hea. Flux Hot. Channel Factor c.
RCS nressure safety 1imit (2736 psig) d. Enthalpy Rise Hot Channel Factor QUEC:1 ION 1.08 (1.00) Which ONE of the f ollowing is NOT characterist2 c of fast neutron irradiation on reactor vessel metal's? a. Increased st rength b. Decreasod ductility c. Nil-ductility Temperat ure (NDT) decreases.
- d. Changes in the lattice structure of the metal.
i 4 (***** CATEGORY 1 CONTINUED ON NEXT PAGE
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{ I j
[x
- o..
a 5 Pag,e 6 -..F11 t__SE BC I 9ffi EEING1 ELE 5;1Z31_INEBdgDyN6digg ' 1231_8ND_C9dEQNgNIg_11131_1E9Np6dENI865 E18dl ~.
- 1..
'DUESTION 1.09 (1.00) s For ' each' of t he f ollowing changes in pl ant status.. indicate whether the ~ DNBR in the. core will INCREASE.. DECREASE. or. REMAIN THE SAME.- Consider-p each'chenge, separately, and assume all other parameters remain unchanged. 'The. reactor is initially at 50% power. a. Increase reactor power-b. LIncrease CVCS charging and, letdown. ' c.- DELETED. d. Increase pressuri er pressure e. Increase core inlet temperature 1 .DUESTION 1.10' (1.00) 14 Imoulse Pressure to the rod control system was calibrated so that Tr ef was ' reading f 2 ve degrees, hi oner than it normally would read, what effect would th2E have on.,econderv plant e#fattency? Why? (Ascume no opera, tor acti on. ): OUESTION 1.11 _ (0.00) e QUESTION DELETED QUESTION 1.12 (0.75) Whv shculd veri fication of natural circulation conditions be perf ormed on a trend 2ng' basis versus individual sets of readings? QUESTION 1.13 (1.00) The reactor is in a no-load condition with average temperature at 557 deorees-F.and pressurizer pressure at 2250 psig prior to start-up. Calculate the subcooling margin through the use of steam tables. (***** CATEGORY 1 CONTINUED ON twEXT PAGE *****)
rege 7 1.t_ _FLbCT 28181N91ELES 3?"$1_THEBMDDiN6MICS Otl.099,COMPONESI5_111*f1_1EUU26MENI66E_E?,6M1 OUESTION 1.14 (l.00) Safett < elves are used in the main steam system to protect the Which of the syste.m ciping from damaoc due to overoressuritation. f ollowi ng stetements concerning the operetion of safety valves is correct? (CHDOSE ONE) a. When the acts veting pr essure f or a sef ety valve returns to the 12 f ti r.o above the valve disk se ootnt. a combination of steam and air pressure clones the valve. to the safety set cosnt. the pressure b. As steem pressure increaves overcomen spring tension on the valve operator, causino the valve to ocen. As the disk on a saf ety valve lif ts, l ess pressure is exerted on the disk. reducing the upward force on the dist, oresenting " valve slammino". d. A s.af et s val ve is lifted o+f its seat. then is f orced f ull y cpen b y a r. air-coarated oiston. COF5 TION 1.15 t1.00) Which DNE of the follow 2ng statements is TRUE f or the MIXED-BED d emi ner al i z er s? ionic i s ot.mp e s deminerall:er s are designed to remove only a. The mixed-bed and not particulate.
- b. Max i mum f l ow rate is limited to 75 gpm to prevent resin bed channelling, i
- c. An unsaturated mixed-bed demineralized can decrease RUS boron concentration by approximately 100 ppm.
- d. A mixed-bed demineralized can operate for only two months with 1%
e i i f ail ed f uel. 4 1 DUESTION 1.16 (1.00) j 1 Fill in the blent. Too frecuent startino of a RCP may result in serious damage to the __________ from overheating. (*4*** CATEGORY l CCNTINUED ON NEXT FASE *****)
Pago 8 12.._REN;IOS EEJNQlELE$_JZ31_JHE800pyNSd1GS 2272 M 9_COMEOURUIS_11131_lEUbp6 BEN 18LS_E1@M1 QUEST 1ON 1.17 (1.00) BFIFFii describe how a scint211 ation crystal det ect or works for detectino nucl ear radiation. QUESTION 1.18 (1.00) As N50. vou notice a pump breaker swatch with a red and amcer light at _1ve the pas. soner. heactor cower level is 75%. What do these lights mean? OUESTION 1.1C (1.50) BwAP 30<-1. " Conduct of Operations", allows an Operator to place a in the controller in the MANUAL mode from the AUTOMATIC mode.whenever, OperatorE.iudgement. continued automati c operati on i s unsaf e or whenever it may cause unnecessary transients. This SHOULD only be done under WHAT TWO conda ta ons/situat i ons? Q U E S 1 I O t. 1.20 f2.50) i s.75) a. What is cavitation? b. Whv is cavitati on undesirabl e? (Li st TWO reasons) (0.5) List TWO MCB indications that a Main Feedwater Pump is cavitating. (Do (0.5) c. not include local indication) OUESTIOtJ 1.21 (1.50) A pressur2:er level instrument develops a leak in i ts ref erence leg. Exclain HOW and WHf pressurizer level indicelion changes f or thi s i nst rttment. 1 i l l l l 1 i (***** CATEGORY 1 CONTINUED ON NEXT PAGE
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I5i I I ___._-____-______a
1z_ _S&9C I98_ ESINGlCLES_,17b1_ IbgBbppyNADJ Cs .Fcge 9 j .( ? h 1_BN D_ QOUPONENI$_J1331_ J E UN DOMg tJI BL S_E @dl l 1 QUESTlDN 1.22 (1.50) How is valve position veri f ied while perf ormino vertfacation of mc chan 2 c S.1 lineups per BwAP 740-2 for tne icilowing valves: (0,5) a. Open manual velve ( Accessi bl e s (0,5) 6. Loci:ed throttled manual valve to.5) l .c. Inacce=sible manual val ve l l I e i i i l '\\ \\ l 1 (***** END OF CATEGORv 1
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1 2 r 9 A
i [.... Page 1Q Er __E5fESEyCy,,99Q_@bNQEd66_EL@NI_EyO6gligNS \\ K Yr-OLIESTIOt-2.01 (2.00) For em of the following cases. state whether or not emergency boretton se roQuir e per BwOA.PRI-2, " Emergency Boration": (Treat each case separ eit ei y i
- a. On* control rod falls to 2nsert on a : eactor trio
- b. Rea: or power is 200*/. with control bank D at 78 steps
- c. React or i s, i ri mode 6 with boron c onc ent r at i on of 1900 optr
- d. Del t a-I is at -17 with target delta-I at -3
- e. RC5 t emper ature is stable at 551 deg.F f ollowing a reactor trio when a 5/6 becomes f aulted
- f. Reactor is in mode 3 with a 0:eH of.98
- g. During a startuo, the reactor goes crit: cal with the " Rod Insertion Leo L i mi t " a: arm lit
- h. Durano e recctor startup, E t e atr. d urnp failure results in a cooldown to 550 cro.F OL'EST I ON 2.02 (2.00)
TRUE or FALSE: If e ouma control switch is in PULL-TO-LOCK on the main control board, then it may NOT be coerated f rom the Remote Shutdown Panel. e Ex pl ai n. l (t**** CATEGORY 2 CONTINUED ON NEXT PAGE
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e> Page 11 2. E!1EE Q EL4C1_6b D._6BNOE066_EL6N1_ E VQLUT I QN 5 12222 DUE5 TION 2.03 (1.00) 'What ac the f ail posi ti on of the f ollowing valves 2 f instrument a:r+2s lect? a. FCV 121. Charging ilow control b. CV 1124. HUT divert c._CV G142.
- 1 seel bypass isolation c.
AF 005A-H AFW 4 low contro) e. FW Q12A-C MFP recirc valves OUESTION 2.04 (1.750 Per BwC A PRI-5. " Control Room Inaccessibility": a. WHAT TWO actions should the NSO cerform (if he/she can) ori or to Ivaving the contr ol room? (Do not include sub-steps in your answer. - (1.4N b. Wnere does the N50 go to when evacuating tr.e control room? (0.5) c. Whc4 (by positi on) also goes to the location in b. above? i. :.5 / DUESTlOre 2.05 (2.00) Per BwEP-0. " Reactor Trip or Safety Injection": 0.' Hcw is a Reactor Trip verified 7 (List THREE verifications) (1.2) 6. How is a Turbine Trio verified? (List TWD verifications) (0.8) GUESTION 2.06 (1.50) and/or protective interlocks occur with a Low-Low What r e oui r ed ac ti ons l e vel in the CCW surge tank? List three. (*4*** CATEGORY 2 CONTINUED ON NEXT PAGE
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---i----_a____m_
4 'h1'26MES9EN(y_99D_@hN0$MSL_PL@NI_gyQLUllgNS Page:12 2 12L*4L l L; l QUESTION 2.07 (1.50)- LIST-TWO indications from the Liquid Radwaste Panel'or -the Control Room' ~ liquid radioactive water release-2 that ! ar NSO can'use to-determine when a was Eautomatica] 3 y terminated.
- QUESTION
.2.OBL (2.00) BwFR-E.1, "Fescanse to Nuclear Power Generation /ATWS".. immedi ate -action I steo O nes you verify.thet the-turbine has tripped._ WHAT actions should.be carriec'out'bvlthe operator if the turbine.has NOT tripped? (Include all cont 2ncencv.sub-steps contained in the response not obtained column.in your answer.) QUESTION 2.09 (1.25) Answer the f ollowing. questions concerning the Subcooling Maroin Monitor with respect to the following given plant conditions: RCS Pressure is 1200 psig, RCS Tavg is 3,50 deo.F. and the plant is ' currently being cooled down for.a refueli.ng outage.
- a.
'Li st the TWO Inouts into the Subcooling Marga n Monitor. (0,5) .b. What THREE displays are available on the Subcooling Margin Monitor (0.75) primary displav? QUESTION 2.10 (1.00) Per BwOA PRI-2. " Emergency Boration". how'does the coerator verify that the ' borati on is having the desir ed ef f ect at power? (List TWO methods) DUESTIOf J 2.11 (1.00) In accordance with BwOA ELEC-1, " Loss of DC BUS": (0.5) a. How i s ESF DC Bus verified de-energized? b. How are the AC :nstrument buses verified enercized? (0.5) (***** CATEGORY 2 CONTINUED ON NEXT PAGE
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\\ g. EMERGEldC V AND ABNORMAL FLANT EVOLUTIONS Page 13 ) 30Z32 t i QUESTIOrJ 2.12 (1.50) Using the attached excerpt from BwEP-1. WHAT actions would you, as tne Nbd. recommend to the Shift Engineer as you attempted to perform Steo 6 of BwEF-1 during a small break LOCA. Plant conditions are as f ollows: 1. RCS pressure is stable at 1200 osag 2. Containment pressure is 7.5 psig 3. Containment Radiation is 10E(3) R/hr 2 RCS temcereture 2s 526 deg.F (by the average of 10 highect CETs) 5. Iconic d 2 s p 1,2 y s are out of serv 2ce e. ECCE pumps are unn2ng from SI si c> n al 7. Total AFW flow available 3s 740 gpm 5. NR S/G levels are all at 11% Q P2R level has recovered to 43*/. DUEETION 2.13 (2.00) A pressurizer pressure channel (contro112 ng ) fails hign causing spray valves and a POM' to open. Answer the following considering each case separatelv: ~' a. Miat must be done (ner BwDA INST-2) if a PORV caw t be shut t Li s t TWO actions and assume the first doesn't wort) .1.0; b. Pressure is below 2260 psig but spray valve RY455B can not be shut. WHAT TWO ections are required? (1.0) OUESTION 2.14 (1.00) Explain the effect on pressuri er level if auctioneered Tave f ails high with pressurizer level control in AU10. Include setpoints, t 3 QUESTION 2.15 (1.00) j Why is power level reduced to less than 70% bef ore perf orming a dropoed rod recovery per BwOA ROD-4? t, i 1
- 4
(***** CATEGORY 2 CONTINUED ON NE)T PAGE
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.-----__--____-_---__--------__------____-----------------__.-----------._---------------------------___--,--_--.--_a
p, ...I ' F ' LOSS OF-REACTOR OR SECONDARY COOLANT 1BWEP-1 REV. 2A 'WOG-1 UNIT 1 ~ STw - AcnON/EXP9CTED RESPONSE ~ IiAEPONSE'N6T OSTA8NED - - + -- 6 CH ECM 'F SI SHOULD BE TE IMLMaTED: I a.. Check RCS subcooling - .a. DO NOT STOP ECCS PL7.PS. l GO W Step 8. i ACCEPTABLE per: o ICONIC DISPLAY OR-o ATTACHMENT A,
- b. Secondary heat sink:
- b. IF NEITHER condition satistied,-
o Total feed flow to intact THEN DO NOT STOP.ECCS SGs - GREATER THAN 500 GPM PUMPS. GD TO Step 8. AVAILABLE -OR-( o Narrow range level in at least.one intact SG - @'ATER THA!I 4% f 34% FOR ADVERSE CNMT) .c. RCS pressure - STASLE OR
- c. DO NOT STOP ECCS P~21.:3 GO TD scey 8.
INCRzAsIwo
- d. PZR level - GREATER "HAN 4%
- d. DO NOT STOP ECCS PL7_:S.
(38% FOR ADVERSE CNM) Go 70~ step 8.
- 7. Go To inWFP ES 1.1. SI TERMINATION, STEP 1 A7M C*/ID
..e .?tE:?5 1 Page 7 of 18 0189E(090487) .. e m__-_.._m..__ __-__m _-__m_.__.___-_.__m-____m___._-__mm____.-----______m___ _m A ___.m h
INFORh4ATION ONLY 1 REV. 2A LOSS OF REACTOR OR SECONDARY COOLANT 1BWEP-1 l WOG-1 UNI.T.1.. .:a. .= u..... 200 300 400 500 600 '700 2600 C.)5l 2600 ~ ~ l 2500 ~! 2500 \\ ~ 2400
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- g g.,.s m-11:1iM41.m g 2100 gw
...y 2000, f * ;- 2000 1900
- /.
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- = ;= m; 1300 g 1800 j;g ggy 3yj ;:j 1700 g 1700 iACCEPTABLEi-
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==:: 1600 & 1800 n.= n== w ( e 1500 y :4._; 1500 1400 8 1400 ..._((gfg 1300 l1300 =. egg 1200 m 1200 =r s -A D V E R S E ". ---- g 1100 ' '[UN MT /j 1100 g ,=/ 1000 1000 e 900 O 900 ....,; N O T.;... e -+ -, m 800 800 .h gsACCEPTABLEj' t==-j-700 700 600 400 500 _j . g. g.gg;.:-., - ;;_ 500 400-400 = 300 300 - ' - - r ;8 ATURATION ~ ! NORMAL 7 200 200 igggyW .= _7 =;= 3 100 100 200 300 400 500 - 500 700 APPRovgo TEMPER ATURE (*F) i SEP 30 ss7 I FIGURE 18wEP 1-1 RCS SUBC00 LING MARGIN mwowooo
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Page 17 of 18 0189 E( 09048"l)
x. INFORMATION ONLY e o LOSS OF REACTOR OR SECONDARY COOLANT 18wEP-1 REV. 2A WOG-1 UNI.T 1 -a ATTACHMENT A A. Determination of Post-Accident RCS Subcooling:
- 1. Check Cut for ADVERSE conditions:
o Cnmt. pressure greater than 5 PSIG -OR-5 o Cnat radiation greater than 10 R/hr.
- 2. Check RCS pressure on wide range pressure instruments (1PI-403A/405).
- 3. Determine temperature for RCS pressure using NORMAL or ADVERSE Cnmt curves per Figure 1BvEP 1-1.
(.
- 4. Check average of ten highest core exit TCs from MCS indicators (1TI-1T.001/1T002).
- 5. If average of ten highest core exit TCs less than temperature for RCS pressure, then acceptable subcooling exists.
1 l l APPRoyfD SEP 30 887 a=4:owoo % nev o. 1 1 4 l ( Page 18 of 18 I 0189E(090487) )
2 EMERGENCY AljD_4blJQRM%,P((3NT,EVQLt)llgNS Pege 14 ~ ^ t 127*h QUESTION
- 2. l e, (2.00)
A rentured S/G 1s i sol ated during BwEP-7.. Why is this isolation neresunev? (Give FOUR reasons) e DUESTION 2.17 (1.50) LwEP-1. "Lors of Reactor or beconderv Coolant". directs the operator to niece the ste.am dumps in thc-STEHM PRESSURE mode of operation after tne 'RCPs are t r3 poed. Why? ( G ) v e-TWO reasons > DUE5 TION 2.18 (2.00) After a reactor trip / turbine tr_ip, the main generator trips after $ time delav. What are TWO safety-related reasons for this time delav7 e e l (***** END OF CATEGORY 2
- )
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w.a J ' 7;s2 itiANT ' gySigt!g_Hg31_ eup_EbeNI Wlpg_ GENE 81Q Page.15 b BESPONSiglLil]Eg llQ31-h . QUES')IDN'- 3.01 - ( 1.'00) ' Whet -position would the Makeuo Mode Selector Switch be selected t o '4 or the following mateup system flowpath? (Multiple choice: choose ONE) ( QFgt To F aset.s = 3. ol ad Dilute b. ' Auto c. Alt-Diloto d. Borate QUESTION 3.02 (1.00). ' State whether each of.the.following conditions reauires entry into a limiting condition for ' Technical. Specifications as a violation of peration:(LCO). (Consider each case sepat ately) a. OPTR is-1.03 with steady state operation at 47% power. 15.545deh.Fwhileoperatingat 32% power b. Tavo c. Shutdown margin is 1.5% delta-k/K while in four loop operatior. d. MTC i s 1 (delta-K/K)/deg.F at BOL, HZP with all rods withdrawn QUESTION 3.03 (2.50) On a Saf ety Injection the Centrif ugal Charging Pumps start to provide 1)cw to the RCS. Using Figure 15a-1, LIST FIVE other functions provided by the CVCS on an SI. Include val ve actuations caused by the SI and resultant Phase 4 'i solation signal. (Do not include actions that require any other conditions other than SI or Phase A) j (*6*** CATEGORY 3 CONTINUED ON NEXT PAGE
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e Fage 16 st__PLeNI_siEIBMS_32@3t_6ND_EL6SI:W10E_94NhBig Rgb?ONslDibillES_11931 l DUESTION 3.04 (1.50) WHAl automatic actions / interlocks occur when the following radiatsen monite s reach their al arm setpoint? (Consider each case separatelv: ( 0. 7 =-) a. 0;E-ARO39. Fuel Handling Buildino Crane Mon 2 tor b. CRE-ARO55(56), Fuel Building Fuel Handling Incident (0.75) 1 OUfc STION ?.05 (1.00) Permi cs2 ve P-12 (PIR Low Pressure) al l ows for an orderly reduction oi PC '; pressuee without causing a Safety Injection. What SI signals (2nclude setooints) can be blocked w2th P-11 present? QUES 7 IC N 3.06 (2.00) LIST TEN loads supplied bv bus 142. QUESTION 3.07 (1.50) a. What TWO automatic actions (other than an alarm) occur if a boric a:2 d '1.0) flow deviation conditicn e::ists f or 25 seconds? b. In what mode (s) on the makeup mode selector sw2 tch ere the acti or.s 2n (0.5) part (a) above NOT applicable? QUESTION 3.08 (1.50) LIST ALL. signal s used by PORV 456 and 455A when pl aced in the ARMED COLD OVERPRESSURE position. QUESTION 3.09 (1.50) a. Duri ng nc,rmal op er ati ons. WHAT should be the status of the GROUP 1(1.0) " READINESS", men 1+rr 11phts? 'O.br b. IWHAT is inuicated bv the above status? (***** CATEGORY 3 CONTINUED ON NEXT PAGE
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_ _ _ _. ~.. _ _
Page.17 3. PL69I_nf 9IEMa_1;e31_eND_E66N1;WlQE_@[NEEIC fE BESEQN((hlL]I(($_flQ31 QUES 170N ~. 10 (0.75) Kev l ec t ed val s es (WX 357.869) are used t o prevent an inadvertent aischsege of.licaid i c the release header. WHAT THREE conditions / signals must be present t o open these valves? DUES T 10iv 3.11 (2.00) WnAt sctions (ot her than Tech. Soec. Sect ion 6 admin reout rements) ere recu2 red li the RCS Pressure 5AFETY LIMIT is vi ol ated during each of the f oi l owi no modes of operation: (3.2) a. Moce 2 (0.8) b. Mcce 5 DUESTION 3.12 (1.00) The Ur.2t i reector trion frcm 987. power. What FOUR busses uncergo 6:10 actior if the AC Di stributi on is in a normal lineup? DUESTION 3.13 (1.50) a. LIST THREE sources of hydrogen in containment f oll owing a design bases (.75) L C-CA. 6. If a failure of the hydrogen recombiners occurs during a LOCA:
- 1. *What hazard associated with hydrogen could exist and at what (0.5) c onc entrat i on?
2. What system is the primary backup to the hydrogen recombiners'i (. 25) CJUE ST I ON 3.14 (1.00) LIST *TWO purposes of control rod BANK OVERLAP. 2 (***** CATEGORY 3 CONTINUED ON NEXT PAGE
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l i -______--___-_-___-_____-___-----------_._.___.m__
o 3. PL AN1_SYS1E!15_ (ID32_ @4D. P66BI: WIDE _GENERi? Pcoa 18 FE550N,SIBJ LillE5_11031 DUESTION 3.15 (1.00/ LIST t5e inoute into the Feedwater I sol at i on interlocks Logic belowe REFER. Tb Fih(E 3 16 e-o c d QUESTION 3.16 (1.00) For ecch of the followino sets of cond2tions. STATE whether the E5W.suct2cn vol ves to the' Aux 111arv Feedwater Pumoc.-(AFO17 and AFOO6) will be OPEN,_or CLOFED if in AUTO. (Consider each case separately) c. 5I b. 2/4 Lo-Lo 5/G 3evel sionals from two 5/Gs c. 51 and Icw AFW oump suction pressure d. 2/4 Lo-Lo S/G 1evel signals f rom one 5/G and 2/4 RCF busses ur. der vol t ag e DUEST IGTJ 3.17 (2.00) a. What TWO signals cause C-8 (turbine trip) to actuate? (Setpoints anc coincidences not reouired f or full credit) (0.5) 6. What function does C-8 serve i n the team dump system? (0.5) c. If Unit 1 tripoed from 65% power, WHAT would be the position of all the steam dump valves with Tavg at 575 deo.F? (Assume ell systems (1.0) responded normally to the trip.) DUESTI C#J 3.JB (2.00) Permissive P-4 15 actuated when a reactor trip breater and its associated bvpass breaker are both opened. List FOUR functions that P-4 performs, t (***** CATEGORV 3 CONTINUED ON NEXT PAGE
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l., "; t. e .= n I d,I LL ,e. i l ' L ") muuu., t m RENT ,.yL L OR 41 t i I --t r l i l kL ~" '~ OR ca j 'NANUAL aEur A j L., 3 t 4, i CLDSE FEEDS &TER WLVES ,7 MAIN TAIP ALL FEEDWATER TUROnlE MM*MW!!fff TRIP ' #:eibN n305 u e,5,n.py gg;g M dd N Pulr5 FEEDwATER ISOLATION INTERLOCKS e' t FIGuer 3.ir d' ) O e
Page 19 It__ELN I_51SIEMS_12831_BND_CL3NI;WlDE_GENgBIC BESE01SIBILIIIES_J1931 QUESTION 3.19 (1.001 You, as thm NSO. notace that there is a demand for automatic rod withdrawal. but the rod control system is not responding to the demand. You are d2rected to place the rods in manual and attempt to w2thdraw the rods. The rods move outward in manual. WHAT TWO oossible rod wa thdr ewal interlocrs may have ex i st ed to prevent the automatic withdrawal of rods? QUE.51 I ON 3.2v (1.25) a. WHAT are THREE conditi ons/ signal s that will generate a Containment Ve nt11 ats on Isolation Signal (CVIS)? (Coincidence and setpoints not (.75) recaired) b. WMAT TWO automatic actions occur on a CVIS? (0.5> QUESTION 3.21 (1.50) 8. On e' loss of DC Bus 113 (non-vi t al -125 VDC bus ). HOW is operati on of tr.e Permanent Magnet Generator (F MG) affected? Why? (.75) b. Tne' loss of either v2tal 125 VDC bun while at power requires e manum (.75; reactor trip. Why is this necessarv? QUESTION 3.22 (1.50) a. Describe the seovence of events involving the Emergency Diesel Generators and loading secuen es et safety related loaos during a Safety Injection with off-site (1.0) power a vai l abl e. b. For a SI with a loss of off-site power, containment spray pumps secuence on at 15 seconds if a CSAS i s present. WHEN will the containment spray pumps start if a CSAS activates at 25 seconds. (0.5) OUESTION 3.23 (1.00) E::pl cin HOW and WHY the 120 VAC Instrument Busses remain energized on a loss cf 480 volt ESF power. l
- 1 i
I (4**** CATEGORY 3 CONTINUED ON NEXT PAGE
- 8) 1 L
3I PLAN" SYSTEML (38hl AND_PLAljT-WlDE_GENERIG Page 20 tE=;ON31BR 111ES_J1931 DUES:10N
- 3..:4 (2.00) a.
DE w. 2 s operat ing in LOAD control when an AUTO CONTROLLER OFF lemo 11 nts on the DEHC control canel. WHAT TWO conditions can cause this (1.0) lean to licht and HOW is DEHC affected? b. Describe the operational sequence of a turbine runback. (Include times (1.01 and/or load rates.) PUECTICN _. 25 (2.00) a. L:n i t 1 is operating at 9e?. power with all control systems in automatic. The output of auctioneered Power Range NIS starts to fail (1.0; hagh. Describe INITI AL plant response to this f ailure. b. Describe the resconse of the plant if.this failure happened at 9% ocwer wh2le conducting a plant startup. Assume that control systems are lined uo as thev would be normally in this condition. (1,0) QUE5 TION ?.On ( 2. C";.'.' Unit 3 has just reached 95% power f ollowing a plant startup with Xenon building uc toware equilibrium. Roc control is in automatic with bank D at 18e er tps. A ROD CONTROL URGENT FAILURE alarm is received in the contro] room and an A-Men reports that power cabinet 1AC is causing the alarm. I a. HOW would the A-Man know it is power cabinet 1AC that is causing the (0.5) alarm? j b. HOW would the NSO counteract the negative reactivity inserted by the xenon using the rod control system? (If he/she can't use rod (1.0) control.then state so) e } c. I&C discovers that a thyrister has lost gate control and is acting as } a diode causing a phase f ailure. What can be done to ensure that 1AU rods remain at their positi ons while I+C replaces the thyrister' f ( 0. 5.- 1. l I f (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) i
Page 21
- [ PLANT S Y ST gM3,12.@31_6Np_[6 @NI;Wlpg _ggNEBIC SESEQNg1FILillgS_fl231 DUESTION 3.27 12.00>
Fill in the bi snts with the correct phrase: (0.5 eech) a. "AT THE LONTROLS" means that the Unit NSO is in the ___________,_______ of the f r ont panel s. b. The Unat NSO may. leave the "AT THE CONTROLS area when reoutred to go be"ind the back oanels only after ________,_____________________..____. c. The Uni t i N30 ma. be directed to help out the Unit 2 NSO on1v efter a c c r o a 1 b y t h e _.. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _.. _ _ _ _ _ _ _ _ _. d. Orenge dets placed at the discretion of the NSO should be repl.ced be + caution cards if the condition is expected to exist for more than QUESTION 3.28 (1.00/ as the i ni ti al Station Which ONE of the following on-shift people acts Di r ect.4r until the Station Manage- (or his designeei arrives to fill that oosa t) c n? a.' Doerati ons Superintendent b. Shift Foreman c. Station Control Room Engineer (SCRE) d. Shift Engineer 1 i i l l I i, 1 i }' (***** CATEGORY 3 CONTINUED ON NEXT PAGE
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. R_ E5_ !. O_ N.,51 pg 1 T I gg_11031 1
- DUE5T!Or.
3.29 (2.00) - flit cts 't ne ' 4 ollowino: 1 Master out'of: Service Card ' a. khtte with red letters 1 and'a red cross-ner.ched border b. White with blue letters-2. Out o+ 5ervice' Card and a blue border 3. ' Personnel Frotecti.on Card c.- . Yellow w2-h ' bl ec x l ettert-m - d. White with red letters 4. ' Caution Card and a red border ' QUE3 TION '3.30 (2.00) 'i WNAT are:the ouarterly Iegal MAXIMUM permissible doses.fori . a'. t.25) 1. Lens of the eve (.25) 2. Angles g (.25). 5. Skin (. 25). 4. . Abdomen f or accumulative occupational dose f or. a 27 year.old' b. What is the limit (0,5) . person with a Form NRC-4 on file? WHAT kind of area would you expect an area to be posted as if_you t cot 1d expect a dose of greater than 100mr in five working days? (0. 5 ) ' c. QUESTION 3.31 (2.00) WHO is directly responsible f or an individual's exposure control? (0.5) a. j" i b.
- 1f you are in the area of a radiation source. WHAT THREE methods are h
(.75) . ef f ect2 ve f or minimi::ing your exposure? a{ LIST. THREE ways to minimi::e. stay time in a radiation area to c. (.75) ' accomplish work. (***** CATEGORY 3 CONTINUED DN NEXT PAGE *****) 'f ee, 4 na -_-_n. ___i____a-_---_--
Fago 23 01__EL6"I_nISIEDS_[g@Kl_6ND_EL6NI;W1DE_GENEEIC SE5F,3Ng101L111ES.11931 C'UEST I ch 7.72 (1.00) You arm the NSO on dav shift. The f C110w2 ng is en excerpt from tne* control room icos for vour un2t. Mat.e corrections to these logs f or each of the f ollowi ng condit2 ons: ( Assume that the time is now 1400) a. You discover that the item at 1300 is incorrect in that Accumulator 1D ( 0. 5 / o eesure was 647 psig instead of 547 osig. b. YOu discover that you f orgot to log that you started the 1A EDG ( U. E ' oer ata l : t v test at J220. EXCEFF15 FROM CONTROL ROOM LOGS. BRAIDWOOD UNIT 1. 12/5/88 ?.1 4 5 Comoletee borating for load change 1215 Comol et ed ramp down to 75% power 1230 Restored 75 gpm letdown 1250 Loco 1D Accumulator Low Pressure alarm, entered LCOAR and. commenced orersuri:Ing the accumulator 1300 Pressuri:ed Accumulator ID to 547 psig 1345 Secured 1A EDE after satisfactory 1 hr. operability test I! I i ( 4 i i } (***** END OF CATEGORY 3
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} (***444**** END OF EXAMINATION $4***4**44) u
y; , ;.l... Pago-24 s.: J1. r. REACIDR PRI!iCIE6gg 777.) THERMODYNAMICS-. ? ~ ' ' 07. F GNp _cDL1EQNENIg;11171_1F WpedENI@65_,5 K90), - MNSWEN- .1.01 (1.00) b.- l< -F<EFERENCE-obj 4 ' Peect or. - Theor v.. Ch 4,. Fi o RT 4-4 .192OO6K111 ..(KA's) ANSWER .l i 02 -(1.00) . 0.' 25 ' e a ) ( a.. retaain the same, ,b. decrease
- c.
. decrease _ i __ ~ ' [. 8.- ' increase - -REFERENCE Reacter Theorv. Ch.7.--pp'7 to 10. obj 8 19d.02K114 ..- ( K A ' s ).
- ANSWER 1.03 (1.00)
Larger SUP at EDL'(0.5) because Beta Bar ef f ecti veg decreases (.25)-with 2 r.cr er : Pu-239 and decreased U-235 (0.25) will accent explanation using-SUR or PERIOD f ormulas provided e planett on 2ncludes-effects of changing Beta Bar effective. REFERENCE Nuclear Theory, Ch 5. pp 35 to 36, oba 8 192OO3K106 ..(KA's). ANSWER 1.04- - ( 2. 00 )- The excess steam ~ flow causes T-avg to decrease (0.3) and insert positive- ^ react 2 v2 ty (0.3) Power increases 40.4). At the POAH. negative reactivity, + -i s inserted (0. 3 ) from power defect (M1C and doppler) ( 0. 2i. Power rise and cooldown continues until reactor power eouals steam demand (0.5)
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j' (***** CATEGORY 1 CONTINUED ON NEXT PAGE
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i. --- - - - - _ _. ~ _ _ _ _. _ _ _ _ _, _ _ _ _ _ _ _ _ _ _, _ _
!1[__EEe;I98_ERINg]ELES_JZ%[_THg$$9pYU901QS Fope 25 iT4 t _9Np_ GQMPQNEN15_j1171_ jEyNp9dENISL S_ g f 9dl REFERENCE Reactor Theory, Ch 8, pg 17 192ev8K121 ..(KA's) ANSWER 1.05 (1.00) The RILE. reduce the effect of a rod ejection accident (0.5) bv r educ2 ng tne r eact 1 *. i t y inserted by an ejected rod (0.5) REFERENCE Reactor Theorv. Ch 6. pg 25. obj 9 192OO5K115 .. (KA's) ANSWER 1.06 (1.00) Maximum fuel crecond2 ti oned limit is defined es the maximum power level achieved (0.33) for a cumulat2ve 72 hours (0.33) during the previous 7 devs of power oper at i on (0.34). REFERENCE BwCH F;C D-4 pg. b 192008K119 ..(KA's) 1 ANSWER 1.07 (1.00) d l REFERENCE l Heat Transfer. Ch 9. pg 41 193OO9K105 ..(KA's) ANEWER 1.08 (1.00) l. l C a l 1 s i 1 (****4 CATEGORY 1 CONTINUED ON NEXT PAGE
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J f i
1,'__RM;2OE_EB1991ELES lZ32 ItLEBDQDfbed]CS Popo 26 a ZE 890_CPOE995NIS_jlj }1_j((Jyp$$[N1$($_EfSD1 FEFERENCE Heet T-c.n s f e. Ch 6. pp 19 to 21 2c1C10K105 ..(LA's) ANSWER 1 09 (1.00) (0. 25 ea) 9. dFcrebse b. remaa n the sarne c. DE ETEu d. Increase e. oecreese REFEREN~E Heat Tr ansf er. Ch 9, pr 24 to 25. obj B 19 OOSK105 ..(RA"s) ANEWEP 1.1O (1.00) Setemcarv eificiency wou; d ancrease C.5). becsuse steam temooratur e san 3 o r e s,st r e ) woul d increase allowing more energy to be obtained from each uni t. amottnt of st eam (.5) REFERENCE Thermodynamics. Ch 4 pg 65 & 130. obj 11 19!OO5K103 ..(KA's) ANSWER 1.11 (0.00) l DUESTiDN LELETED REFERENCE 197OO6K104 ..(KA's) A ANSWER 1.12 (0.75) e Eli,minates ef f ect s, of instantaneous s ar i ations in readings i V (***** CATEGORY I CONTINUED ON NEXT PAGE
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l F'ega 27 Iz__SE6C JQE_EEIN(1E([@,,1?Zl_ltjgEDQQyy@DJ GE 12's;_6ND C9dE9NEN1E_11131_1EWND9dENI@bS_[K@D1 i AETERENCE I. l-Heat Tr ent,f er. Ch 5. pg 23. obj 5 1 0.*0 tth 1 2 2 ..(KA's) AN5WER 1.13 (1.00) (654-557)=o? degrees-F (+/- 2) REFERENCE CE Fower 5, stems steam tables 193OO3K125 ..(bA's) ANSWER 1.14 (1.00) b REFEREfJCE Svs t em Deecriotion. Ch 23. po 32. f 2 (- 25--4 1-41 0 01K1t.>1 .. i b W 71 ANSWER 1.15 (1.00) C REFEREt4CE Svstem Descr2ption. Ch 15a, pp 21 to 22 191007K108 ..(KA's) [ ANSWER 1.16 (1.00) 2 l motor windings t j REFERENCE l Svsten. Descript2on, Ch 13..pg 42, ob; 10.b 3 191005K106 ,..(KA's) J l l l (***** CATEGORY 1 CONTINUED ON NEXT FAGE *****.* e i 4 4 .- s j
0* } ~ i Page 28 1 REAC'09 PR10CJfLE5_1231_THEBMQQ1NAd]C$ lII.__0bp_cptepuEUIS_1113)_jEUSQ8MENIBL5_Ef601 1 ANSWER 1.17 (1.00) As radi at) on passes thr ough a scintillation crystal, energy is trensf erred ~ to.the cryst >l (.25). This leaves atomo an tne crystal in an excited state (.125/. When at oms return to their groured state. energy is radiated (.125i. The light from that process is detected and measured es a radle;1on level (0.5). REFERENCE E v s t er. Leacription. Ch 49, pg 73, obj 2.c I c. Ot. Ji 113 ..(KA's) ANSWER 1.18 (1.00) (0.5 ea) 1. The red light means the breaker is not in its normal positson. 2. The smber light means that the brealcer has tripped. RE3ERENCE BwAP 360-1. po 2 !c COSK111 .. (if A's ) ANSWER 3.19 (1.50) (.75 es) 1. Conditions are stable and under control 2. Cor.tinued operation would aggravate or worsen clant condi ti ons REFEREtJCE DwAP 300-1. pp 5 191003K111 ..(KA's) 4 t i ~ l l (***** CATEGORY 1 CONTINUED ON NEXT PAGE
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2.. RE AC T OR PR I NC I PL E S_J Z31_TbgE:dQpy N@MIC S Fego 29 iZ31_6ND.C00E9N5NIS_J1131_1EpNQ@d[NI@L5_Ef@dl ANSwEf-1.20 (1.501 a. The f ormast a an and subseouent collepse of vapor buboles in a pumo-i.75 b. (.25 ea) 3. decreased ef42ciencv (due to i rrever s) bl e energv losses). !W211 accept reduction 2 n f l ow rate) 2. Mechanical pump d s.m ag e (due to pa tting, erosion and vibretton) c. tan. 2 &.25 ea) 1. nressure fluctuations 2. flow 41uctuations 3. MCD smps fluctuation 4. low flow alarms on components w2th inascatzon on the MLb REFERENCE Fluid Fl ow. Ch 2. pg 47, obj 10 191004K101 _..(KA's) ANSWEA 1.21 (2.50) I ndi c M ed Invel increases th29 er tnan act ual * (0.75) bec7use of less h mass 2n the reference lec (caur.ing LP 2n the bellows to decrease) (0.75/ REFERENCE Instrumentation and Controls. Ch 1. pg 25 & 36. obj 14 191002K109 ..(KA's) ANSWER 1.22 (1.50) a. Attempt to close valve (0.25) then return at to full open posit 2on (0.25) b. Observe lock in proper position (0.25) and valve position indicator other than full closed (0.25) c. Trensf er of init 2 als f rom previous lineup (0.5) REFERENCE FwrP 340-2. pp 7 & 8 191001K108 ..OJA's) (***** END OF CATECORf 1
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1 i ( . ~ -
( Pcge 30 2 _EDEE @lNQf AND_AQNOBOL4,E'LANI_E29(.LJllgNS 12Zh; f ANSWER 2.02 (2.00) i (0.25 each) G. no 6. ves C. Ves d. no c. ye= f. no O. no h. no REFERErCE BwDA FPI-2. Entrv Cond2tions OOOO24K301 ..(KA"s) ANSWER 2.02 (1.00) false. Take the Local / Remote switch on the RSP to Local and control is et the R5F. NOTE: no cred2t f or True/ False answer without correct e::pl anat i on REFERENCE System Descripts on, Ch 62, pg 9 obj 3 OOOOo8A121 ..(KA's) ANSWER 2.03 (1.00) (0.2 each) a. open b. to VCT c. closed d. open e. open 1 REFERENCE l j System Descr2ption. Ch 53. pp 47 & 48, obJ 6 ) OOW 65K303 ..(KA'si } (***** CATEGORY 2 CONTINUED ON NE).T FuGE
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+ Fcoa 31 Et__E!1EngENCy 6bpMUDEUB6_Ekbyl_EyOLUIl9di .iEI' : ANSWEre 2.04 ().75) c. (c.5 each) 1 Manually trap the reactor 2. Checi: that an SI is not actuated b. F e+0t e Ghot down Panel (0.5) c. %CRE (0.22) PEFE.RFrK E DuOf FBI-5, oc 5 % 6 OOOveBF.312 ..i.F.M s/ ANSWER 2.05 (2.00) a. (0.4 each) 1. Rod bottom lights lit 2. Ro trip and bypass breakers coen 3. Neutron flux decreasing b (0.4 each) 1. All tur bine throttle stop valves _ losers 2. (ell turcine covernor valves closed REF E RE fC.E. SwEP-0. po 3 & 4 OOOOO7A206 OOOOO7A107 .. ( F.A ' s ) ANSWER J.06 (1.59) (0.5 each) 1. Trip the reactor 2. Trip the RCPs 3. Trip CCW pumps REFE~RENCE Eystem Descript3on. Ch 19, pp 6 6 62, obj B Lesson Plan. BwOA PRI-6, pp 22 OOOO26A105 ..(KA's) i i 1 l / (*4*** CATEGORY 2 CONTINUED ON NEXT Ps5E A***4) r i
Pcgo 32
- '2__ED,E[%NCY pt1D,,@BtjO6dAL_EMNT,JyOWI]QNS u.
- .
i ANSWER 2.07 (1.50) (anv.J s t 0.75 each) 1. Loss of ilow on Relense Tant Flow Recorder or Release Tank Flow Integrator. 2. L2 aui o Radweste Control Panel Trouole Alarm 3. Radi oactive li quid release valve (WX 053) and bypass valve (WX 896) 1rdacete shut. 4. FM-11 oper at e f allure alarm REFERENCE S v s t er. :. escri nt s on. Ch 48a. pg 25. ob.i 11 tv0059A205 ..(KA's) ANSWER 2.08 t2.00) 1. 19snus11 v trip the turbine (0.5) 2. Manually runback the turbine (0.5) 3. E.- oumos to PULL OUT (0.5) 4. Ir.2 t2 ate steem12 ne i sol at i on (O.3) and v<c21v MSIV ( O.1 ) ano MSIV bvoass valves (O.1/ c l or,e d. REF ERE Nt. E BwFR-S.I. pg 3 OOOO29K312 OOOO29K306 OOOO29N308 ..(KA's) ANSWER 2.09 (1.25) a. any 2 O.25 ea 1. RCS* wide range pressure 2. Average of 10 highest CETs 3. containment pressure 4 containment radiation l (.25 es) b. 1. Pressure margin to saturation ( 2. Temperature margin to saturation j 3. Trends (***** CATEGORY 2 CONTINUEL ON NEXT PAGE
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n,, l v t Pcge 30 'c__EDESEEUGi_GUD_8kNQBd66_E6@N1_5296pl]QNQ. .12Z.41 REFERENCE Svstem Description. Ch .'.4 b. App. A. obj 6,7 WOO 74 A113 ..(LA's) ANSWEP 2.10 (1.00) 1 (0.5 each) 1. T,=-e decreasing 7. Vs-ifv rods withdrawing REFERENCE BwCA F B I-2. pg 5 OOOO24k103 OOOO24V102 ..(kA's) ANSWER .1 (1.00/ a. Low voltann-annunciator lit ( 0. 25.- and MCB bus voltmeter zero (v. 25; b. Instrument and Contro~. oower av ail able to all channel s of ruclear i n st r tu et it at. i c n. (0,5) REFEREN;a BwCA ELEC-2. op :_. 3, 6 OOOO5GK302 Ov00584202 .. (KA's) ANSWER 2.12 (1.50; Recommend NO7 stooping ECCS pumps (1.0) and GO to step 8 (0.5). REFERENCE BwEP-1. pp 7.
- 17. 18 OOv.>9A210
..(KA"s) 1 i l ) i ( (4**** CATEGORY 2 CONTINUED ON NEAT F AGE
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lj e i 4 1 i - -- ---_.---_______________j
.. = Fcoa 04 .,L._ liifi5M'JCf 69D_9DUQEO,@L_E* @yI_ES.OLQIlgNL 1sk ? ' ANEWhR 2.17 (2.00) (0.5 each)- a., 1. Cicse t he F OW isol ation 2. Trip the reac. tor 6. Tr.o t ne reactor 2. 5tso RCP ib REFERLNLE itwOA UrT . op 11 tc 1;: O :p y.:7A21S .. Ut A' s ) ANsWEh
- .14 (1.00' raise FZR level to 60% (t ie 4.Cheroing nunips would 2 nerease speed / flow and) orograr med maxi mum level).
(1.0) REFERENCE Evstem Des r ipt 2 cn. Ch 14. pg 44 Figs. 14-15 L ;4-2. ot3 20 nuO '28A.'02 ..(KA~s) ANSWER 2.15 41.00) T o ensure that Rx Power does not exceed 90% upon recovering the dropoed rod. REFEREr4CE Lesson Flan, BwOA ROD-4, pp 6 to 7, ob] 7 OOOOO3K304 .. ( K A' :. ) l i ANSWER 2.16 (2.00) (any 4 at 0.5 cach) 1. Minind re radiol ogical releases 2. Maint ain ruotured 5/G P, non-ruptured S/G P 1 3. PCS P reduction will stop the leat 4. Non-ructured S/Gs can remove heat 5. Subcooling will be tr.eintained i 2 (***** CATEGORY 2 CONTINUED ON NEXT PAGE
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a
Ps.ge 35 2-EMEAGENCY AND ABNORMAL P1,@I,EYQLUTIgNS J E22-1 REFERENCE
- Losron F 1 an. BwEP-3, pp 20 to 21. obj la
. 000381 2.Oo ..(KW s) AN5WER 2.17-(1.50) anv 2 of the f ollowing &.75 ea: 1. leve signal as in error beceuse of little fl ou tnrough the bvt.as s man 2 folds, s. 5t ean. pressu-e mode prev 2 des finer control 3. 1 :. allow rooldown less ttan 550 degrees F. FiEFERENC d -Lesson Plan. BuEP-1, pp 14 & 15. ob3 Id 0 0'. 0 4 01:304 ..(KA's) ANSWER 2.18 (2.00) 1. Certain reactor traps coincident with e failure of euto bus trans+er could result 2 r-e 1oss c4 RLE f1aw. The t: me del av ensures f1ow tor c lenoth of time when the reactor :s shutdcwn making the loss of ficw l e s a, serious. ( 1. 0.i 2. hCP overspeed can occur on a major LOCA. resulting 2n a missile hazard. The chances of RCP overspeed is reduced li the pump 11 l oc a. ed in at eO H: until the generator trips. (1.0) REFERENCE System Description. Ch 60b, pp OS to 29, obj 6 000007K301 ..(KW s) 1 , i l I (***** END OF CATEGORY
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e
l A_'. E6eN1_SX51Et% DD31_96D_EL6NI-WI M_ GENE 6]G~ Paga 36 BE5EONp1RJL11]ES 11931 l l ANSWER 3.01 (1.00) a REFERENCE System Description. Ch 15b. Fig. 15b-5. ob) 7c OO4000K106 ..' (K A' s ) ANSWER 3.02 (1.00) (0.25 each) 1. no 2. yes 3. no 4. ves REFERENCE Techni c al Soecificat2ons, pp 3/4 1-1, 1-4. 1-o, 2-10 OO1000G011 ...(KA' m) ANSWER 3.03 (2.50) 1. CV 9105 and CV B106 close (0.25) to isolate nermal charg2ng (v.2b) 2. CV 8152, CV B160 and CV G149(A,B,C) close (0.25) to isolate normal letdown (0.25) 3. CV 112B.C close and CV 112D.E open (0.25) to align charg2ng pump suction to the RWST (0.25) 4. SI 8801A,B open (0.25) to allow maximum flow to the RCS (0.25) 5. CV S112 and CV 8100 c, lose (0.25) to isolate seal return flow (0.25) REFERENCE Svstem Descr2ption, Ch 15a, pp 75 8< 76, Fi9 15a-1, obj 7&B OO4000K115 .. (K A's) (***** CATEGORY 3 CONTINUED ON NEXT FAGE
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3, PL ANT ' SYSJ EMS _j3@$1_SNp_EL9N1-Wlpg_QgNERlQ Pags 37 BE@CQNEJklbillgS_J1931 ANSWEP 3.04 (1.50) a. Uoward movernent of the crane holst is 2nhib2ted (0.75) b. (0.25 each) 1. Charcoal Dooster Fan (OVA 04CA(Bs) starts 2. F21ter bypass dampers close 3. When one fan an b.1 starts. the other is locked out REFERENCE System Descr3pt20n. Ch 4'i. pp 42 & 43, obj 4a 072Ov0K101 ..(KA's) ANSWER 3.05 11.00) 1. Low PZR Pressure (0.4), 1829 psig (0.1) 2. Low St eamline Pressure (O.4). 640 osig (O.1) REFEREtiCE System Descr2pt2on. Ch 6. pp 35 to 36. obj 5& 6 012OOOKoO4 .. (KA's ) ANSWER 3.06 (2.00) (anv 10 at 0.2 each) 1. (4160/480 volt xformer to) bus 132X 2. (4160/480 volt xformer to) b+ts 132Z 3. Chg Pump 1B 4. S1 Pump 1B 5. RHR Pump 1B 6. Control room refrigeration unit OB 1 7. Containment Soray Pump 1B-8. CCW Pumo 1B 9. Feed to Cooling Water Pumo 0 10. ESW Pumo 1B 11. Aux B1do Vent Supply Fan OB 12. Au r-Bldo Vent Exheust Fan OB REFERENCE System Description. Ch 4, pg 45. obj 12 062OOOK201 .. (KA's ) (C**** CATEGORY 3 CONTINUED ON NEXT PAGE
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i
Paga 08 ( l 3a PLANT $ Y W T gtjS_j 3831_ AND_PL ANT -WJ DE_GgfjgBJ G BE$E-Q9 SIP.ILITIES.11931 ANSWER 3: 07 (1.50) 'O. 5 e a: h) a. 1. CV 110B (Blender to Chg Pumps > shuts 2. CV 111B LBlender to VCT) shuts b. Manual REFEFENCE Svstem Description. Ch 1Sb. pg 52 BwAR 3-9c-he
- .$O 4 0 2 0 A 4 u l
..(KA's) ANSWER 3.08 (1.50) (0.5 each) ). Auct. Iow hot leg temperature (455A) 2. Auct. low cold leg temperature (456) 3. Wide range pressure (407 - 455A) (406 - 456) REFERENLE Syst em Dr-scr 2 pts on. Ch 14 Fig'14-13C, obj 24 01000uK402 ..(KA's) ANSWER 3.09 (1.50) c. All lights should be dark (0.8) e:: cent RH 610 and RH 611 Open lights (0.2) b. ECCS 'comoonents are in their proper standby configuration (0.51 REFERENCE l System Descri pti on, Ch 58. pg 31, obj 10 t OlOOOOK403 ..(KA's) i-1 ) ANSWER 3.10 (0.75) (0.25 each) 1. Control sw2tch open signal 2, Rad monitor read 2ng less than al arm setpo nt 3. Suffic2ent circulating water blowdown flow (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) 2
.=, c, ~ e. Page 39, N _ELAt!I_EYSItt!ELGE31 AND ' PLANT--WlDE_GENEFjlg t CBEEEQN@l@lkill[$_flQ31 4 .REFERENLE. ,'Eystem-Descr2ption,'Ch 48a, pg.25. obj 12 '.065000A404- ..(KA's) .f C ' ANSWER 3.11, (2.00) .e.. Be in bot stby.(0.4). with-RCS pressure within its 12m2t (0.4s w2than 1- 'hr (0.4) . b ', Reduce RCS pressure to within its 12mit ~ (0. 4) c wi thi n S mi nuters (0. 4 >. TREFERENCE . Techni cal Soec2 fications, pg 2-1 002000G005 ..(KA's)' . ANSWER 3.12 (2.00) (0.25 each) ' 1. 15o 2.- 157 3. 143-4( '244 REFERENCE 3 System Description, Ch 4, pg.129, obj 10e'- .062OOOR410. ..(KA's) ANSWER 3.13 .(1.50) a.- (anv three at o.25 each) i 1.- Zirc-wat er reaction 2. RCC 2nventory 3 -L} 3. Corrosson of p1ent mater 2als Radiolytie decomposit2 on of water j.l-(0.25) if hydrogen sho+. tid ? b.. 1. Explosi ve/ flammable ha::ard would ex2 st ,[- rise above 3.9% (+/- O.2) (0.25) ') 2. Post-LOCA purge system (0.25) 1:y (***** CATEGORY 3 CONTINUED ON NEXT PAGE
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"l, Face 40 L PLM4T S YST pj$ _j,Z.Q'f L6ND_EL AtJT-WIDG_ GEL!EBlG ? ,t SEkE09SIF16111ES_JJQ31 REFERENCE Svstem Description. Ch 41, pp 4.6.42, objs
- 1. 5. 8 02BNwf.~.'.C 1 0280001.503
..(KA's) At45WER U.34 (1.00) 10.5 each) 3. Mer e uni t orm dif f erential tod worth v. More un2 + or m antal flux distribution REFEPENCE Ey st ee Descr 2 pt i on. Ch 28. pg J 0, obj 19b OO1000K558 ..(KA's) ANSWER 3.15 (1.00) (0.25 esch) a-b. S/G H2-Hi Level SI c. Reactor Tr2p d. Low Tavg REFERENCE System Descr2ption, Ch 25 Fig 25-6A. obj 60 0 11 059000K419 - ..(KA's) ANSWER 3.16 (1.00) w (0.25 each) a. closed b. cIcsed c. coen d. closed REFEREfJCE Syste.1 Description. Ch 26. po 40, obj 20 061OOOK107 .. (KA's) I l (***** CATEL, DRY 3 CONTINUEl.: GN NEXT PAGE
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l Fage 41 (3831_AL!D_PLAr T;WlDE_@ENERIG j ,f.. PL A'; T SYSTEM 5 EhiFQNSJRlbillES.11931 ANSWEh 3.17 (2.00) a. l^.25 each) 1. Stoo valves closed 2. Low emergencv trip header pressure b. Nc,e (removed in a recent facility modification) (0.5) c. 1. 6 valves ( t r i pped) open 60.5) 2. 3 valves modulating (0.25) 3 valves shut (0.25) REFERif C E E vst er Descript2cn. Ch 24. pp 49 & 50. obj 3& 4 041 cOK41E 041020A406 ..(KA's) ANSWER 3.18 (2.00) (0.5 each) 1. Actuates a turbine trip 2. Emuts the feed reg v61ver 2f Tevg 2 s less than or eaual to Sea deg.F the MFW valves wh2cn were closaec 3. Locks an circust to prevent reopenino
- o. wither an SI actuatico or a H2gh-High S/G 1evel.
4, weavides :s signal to tne SI block and reset logic circuit. REFERENCE Systen Description, Ch 61. pp 34 to 35 012OOOK610 ..(KA's) ANSWER 3.19 (1.00) 1. Turbi ne first st age pressure 1e's than 15% (C-5) (0.5) s 2. Control bank.) greater than 223 steps (C-11) (0.5) i REFERENCE Svetem Descr 2 ct s on. Ch 28, pp 72 & 73. oby 14 001OOOK407 ..(KA's) I s 3 3 4 I (***** CATEGCRY 3 CONTINUED ON NEAT PAGE 44***) 1, l
2t_ _E(6NI _ SI@lhD$_128Z1_@ND_E(@NI WIDg_GEt9EBIG Pegn 42 SEE Ep NS I M L LTJEg_J M Z.1 ANSWER 3.20 (1.25) a. (.a n v 3 at 0.25 each) 1. Containment At mosphere Area Radiation Mcni tor High alarm 2. Manual Phase A isolation 3. SI 4. Manual Containment Soray Actuation b. (0.25 each) 1. containment nurge i sol ati on val ves close 2. containment mini purge isolation valves close REFERENfd System Description. Ch 61, pg 32. obj 79 103OOOK406 013OOOK101 .. WA's) ANSWER 3.21 (1.50) a. PMG output bretker must be trapped locally because control pcwer is I c st. (0.75) 6. Feed reg vel ves,z,nd bypasr valves f ail closed. (0.75) REFERENCE Svater Description. Ch Ba. pg 22 063000K302 063OOOK201 ..(hA's) ANSWER 3.22 (1.50) a. The EDGs will start but their output breater remains open (0.5). All safety related loads start at once. " (0,5) b. At the end of the secuence (when all other l oads have secuenced or, (0.5 about 40 sec) REFERENCE Syst em Description, Ch 9, pp 63 & 64, obj 9 064 ~)OOK 411 ..(KA's) { l l l l (***** CATEGORY 3 CONTINUED ON NEX1 PAGE
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(, ' . s; Paos 43. b Qi__Eb6NI_ METEf1S_1;S31_6ND_E66N1;W1pg_GgyEB1C b EEEECJASlkl(IIJ E@.11931 (1.00)- 'ANSWEF 3.23 supp12ed to the static.2nverters:tO.8) through a blocksng dacer ~ 12*.o VDC i =- (0.2). concucts.because the-AC. source. voltage dropoed .that now REF5RENCE- [ Svstem: Description..Ch 4..pg 52, obj 14a ~ 06?OOOK30;. ..(KA's)- ANSWER. 3.24 (2.00) err ors a n the. DEHC. 120 VAC power source (0.25) or v2tal a.- Loss of (O.25); cause the DEHC -system to automat 2 ealIv transf er 'tc: computer manual- (0. 5). (0.4).for').5 b ~. A. runback occurs at 200% load reduction per. minute seconds f or every 30 seconds ( O'. 2 ) until the runback condit2cn is c eared ' (0. 4). REFERENCE Systen Description,.Ch 37a, pp 20 t o 22, 36, 93..objs 9 &.
- 12. F 2 g . ' a - 3 5 -
0450GOA305 -045000k412 .. GA's) AN3WER-3.25 (2.00) an error signal is. a. As_the auct. NIS power starts its upward ramp, mismatch circuit that causes rods to insert generated.in the power (1.0) resultmg'in Tavg decreasing. hiaher A' change in auctioneered NIS power causes an anticipation of b. reactor power by the S/G feed bypass valve control system. This causes-the bypass valve to open more and raise S/G 1evel. REFERENCE System Description. Ch 28. pg 27, obj 3 System Description, Ch 27, pg 27, obj 11b i System Description, Ch 33, Fig. 33-1, obj ic 015000A303 ..(KA's) f I 1 1 1 i . -}
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[ 3r PLAN *_SySltyS,j @31_@ND_EL9NI:WJDE_ GENERIC Paga 44 i i; F.55[0951ML1IJgS_,11921 ANSWER -3.26 (O.00) a. (Fed) Urgent f ailure l ernp lit on the 1AC power cebanet t v. 5i (1.0) b. The N50 can dilute ( 0. 5 / l. c. Aonly DC Hc]d Power to the effected rods. REFERENG System !escr2pt2on. Ch 28, pp 40,67.82. objs 9.13.14 0010SOA2OI. ..(hA's) ANSWER 3.27 (2.00) (0.5 esch) -a. 12ne of sieht b. cbtain2 no relief by a qualified (licensed) operator c. ECRE (Conteel Room Superviser) d. one day REFERENCE EwnP 300-1. pp 5. 11, 12 194001A103 .. ( KA * :r - ANSWER 3,28 (1.00) d REFERENCC Bw2P 100-1. pg 2 BwAP 300-1, pa 3 194>O1A116 ..(KA's) ANSWER 3.29 (2.001 j (0.5 each) 1. d l 2. ,a 3. b j 4. c i( l (2**** CATEGORV 3 CONTINUED ON NEXT PAGE
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( _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _. _ _ _ _ _ _. _ _ _ _ _ _. _ _. _ _ _ _ _. _ _ _. _ _ _ _ _. _ _. _ _ _ _ _. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___.___.____________________________._________________i
s, Pcga 45 .u ;2__EL6NI_gySlEMs_f}BZl_699_ELBUI:MIDg_EENEBIC ' SEEEOUSIBILIIIEE_II' '41 2 REFEhENCE .DwAP 330-1, po 3 1040011t 102 ..(KA's) ANSWER 3.30 (2.00) o. (0.25 each) 1. 3 rem 2, 18.75 rem 3.
- 7. 5 r em 4.
3 rem b. 45 rem 10.5) c. Radiation Area (0.5) REFERENCE Radi ol ogi c al Protectson L.esson Plan. Ch 2. pp 10 & 22, obas 2 & 9 144001K103 ..(KA's) ANSWER 3.31 (2.00) e. The i ndi vi dual (0.5) b. (0.25) 1. Ma ns mite exposure t i me 2. Maximi:e distance form the source 3. Shielding the source (anv three at 0.25 each) c. 1. Pre-planning 2. Organization of materials ( t ol l s, parts, etc.) 3. Mock-up training 4. Task rehearsal REFERENCE Radi o] ogi cal Pr ot ec t i on, Ch 5, pp 9 to 11, objs 1 &2 194001K104 ..(KA's) (***** CATEGORY 3 CONTINUED ON NEXT PAGE
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Pago 46 t Sf 5]EL1S_j]@Z1_ AND_F,$AN1-L4]DE_QgNEBlG 3a. _ PLAN 7 EENEOLJ.s1H L II1gg_114232 AN5bfEF 3.32 (1.00) EXCERSTS FRDM CONTROL ROOM LOGS. ERAIDWOOD UN]T 1. 12/5/88 1145 Completed borating for load change 12 ) *> Completed ramp down to 75% power 1230 Restored 75 gpm letdown 1250 Loop 1D Accumulator Low Fressure alarm. entered LCD4R ano commenced pressura:ing the accumulator 130u Pressur2:ed Accumulator 1D to 547 psig (547 should be l i ns=d-t hr ough and initteled and 647 should be written an) (0.5) J : a ', sec ur c-d 1A EDE attre satisiactcry 1 hr operability test 12e LATfi ENTRY. Started 1A EDG operability test (0.5) REF F AE r.4 7 bw,C 250-1. pg 2 1940u1A106 (RA's) 9 l l l' : ( i-i (444** EtJD OF CATEGORY 3 *4*44) i (*******4** END OF EXAMINATION 44********) e l
i 2 t.' TEST CROSS REFERENCE Page. 1 .go - 9955IIOt! _YG695 BEEgBENGE_ 1.01 1.00 90000u4 1.02 1.00 9000068 1.03-1.00 9000017 1.04 2.00 9000018 1.05 1.00 9000019 1.06 1.00 9000072 1.07 2.00 9000005 1.08 .1.00 9000006 1.09 1.00 9000007 '1.10 1.00 9000011 1.11-O.00 9000012 1.12 O.75 9000013 1.13 1.00 9000020 1.14 1.00 9000001 1.15 1.00 9000002 1.16 1.00 9900003 1.17 1.00 9000009 1.18 1.00 9000010 1.19 1.50 9000014 1.20 1.50 9000015 1.21 1.50 9000016 -- 1.22 1.50 9000021 23.75 2.01 2.00 9000022 2.02 1.00 9000023 2.03 1.00 9000024 2.04 1.75 9000025 2.05 2.00 9000026 2.Oe 1.50 9000027 2.07 1.50 9000028 2.08 2.00 9000029 2.09 1.25 9000030 2.10 1.00 9000031 2.11 1.00 9000032 2.12 1.50 9000033 2.13 2.00 9000034 2.14 1.00 9000035 2.15 1.00 9000036 2.16 2.00 9000037 2.17 1.50 9000038 2.18 2.00 9000039 27.00 i 3.01 1.00 9000043 3.02 1.00 9000044 3.03 2.50 9000045 3.04 1.50 9000046 3,05 1.00 9000047 j 3.06 2.00 9000048 3.07 1.50 9000049 3.08 1.50 9000050 3.09 1.50 9000051 I f i
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~g - TEST CROSS REFERENCE Paga 2 99ESI1QN _y@Lyg EgEgBENgg_ 3.10 0.75 9000052 3.'11 2.00 9000053 3.12 1.00 9000054 3.13 1.50 9000055 3.14 1.00 9000056 3.15 1.00 9000057 3.16 1.00 9000058 3.17 2.00 9000059 3.18 2.00 9000062 3.19 1.00 9000063 3.20 1.25 9000064 0.21 1.50 9000066 3.22 1.50 9000067 3.23 1.00 90000s8 3.24 2.00 9000069 3.25 2.00 9000070 3.26 2.00 9000071 3.27 2.00 9000040 3.28 1.00 9000041 3.29 2.00 9000042 3.30 2.00 9000060 3.31 2.00 9000061 3.32 1.00 9000065 t 48.00 _ _ Eup 98.75 1 t j, ~ - _ _ _ _ _ _}}