IR 05000272/1986026
| ML20207M509 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 12/29/1986 |
| From: | Barber G, Collins S, Keller R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20207M443 | List: |
| References | |
| 50-272-86-26OL, 50-311-86-31OL, NUDOCS 8701130198 | |
| Download: ML20207M509 (49) | |
Text
{{#Wiki_filter:_ -. -4 U.S. NUCLEAR REGULATORY COMMISSION
REGION I
OPERATOR LICENSING EXAMINATION REPORT EXAMINATION REPORT NOS. 86-26(0L) 86-31(0L) FACILITY DOCKET NOS. 50-272 and 50-311 FACILITY LICENSE NOS. DPR-70 and DPR-72 LICENSEE: Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 FACILITY: Salem Nuclear Generating Station EXAMINATION DATE: Septem e,r , 1986 CHIEF EXAMINER: /2 29 , GNer, Re tor Engineer (Examiner) 'date' ~ REVIEWED BY: [ /// / 2./2fh6 R.
M.' Keller, Chief, Project Section 1C date APPROVED BY: MYTTittt/ /dll///M 12/3D/% 3. J. Colliris,~ Deputy Director, Division of date Reactor Projects SUMMARY: The Salem Licensed Operator Requalification Program was evaluated to , ensure compliance with NRC rules, regulations and facility program require- ' ments. The Salem Requalification Program is being conducted in a satisfactory manner. One area reviewed was identified as needing improvement; the depth of knowledge required of operators on the Segment Examinations. Questions asked ' i were at the recall level and required stating memorized factors. There were l few questions that required the synthesis and evaluation of material that ( operators encounter on a day-to-day basis.
I .. V j
.
REPORT DETAILS TYPE OF EXAMS: Requalification EXAM RESULTS: l R0 l SRO l l l Pass / Fail l Pass / Fail l Evaluation l l
1 I l Written Exam l 5/0 l 6/1 l Satisfactory l l l l l l l Overall l S/0 l 6/1 l Satisfactory l l l l l l 1.
CHIEF EXAMINER AT SITE: S. Barber, NRC 2.
OTHER EXAMINERS: N. Dudley, NRC 3.
Segmented Examination A review was conducted of the facility provided Segment Requalification Examination in accordance with NUREG-1021, Operator Licensing Examiners Standard, Section 601 and the Pilot Program. The examination review considered the depth of knowledge required, the exam comprehensiveness and the applicability to the facility supplied learning objectives. This review resulted in changes to the examination. Questions were modified or substituted so that approximately 20% of the exam was changed.
The Segment Exam, as provided, was comprehensive and applicable to the facilities learning objectives. However, the depth of knowledge required was inappropriate for licensed operators. The exam questioned operators at the recall level of knowledge.
It did not emphasize the synthesis and evaluation of information, typical of what an operator encounters on a day to day basis.
In many instances, questions were just a restatement of the learning objectives. Questions replaced by the NRC examined the operators at a greater depth of knowledge. Because the NRC supplied questions were more difficult than the facility questions, the average grade on NRC questions was ten to fifteen percent lower than grades on the facility questions.
Proctoring and administration of the examination was performed in accordance with facility standards. When questioned by the operators during the examination, the facility proctor documented the questions asked and his resolution. His documentation was to be used to improve the warding and content of future examination questions. An exam review was conducted immediately following the examination.
It was conducted to provide prompt feedback to the operators on the correct answers to the questions asked.
m
. .
2 , After the proctor read the answer from the key, the operators tried to coerce the proctcr into believing their answers were equivalent to those in the key. These efforts tended to wear down the proctor to the point where he conceded to the class that their answer would be acceptable.
The need for prompt feedback to the operators is recognized. However, the operators' conduct during the exam review was inappropriate. Other feedback mechanisms should be investigated.
The candidate's examinations were graded by both the NRC and the facility. All but one of the facility scores were within 3.5% of the NRC examination scores. One exam question had an initial difference of 10%, but after a facility regrade, it was reduced to 5% difference.
The tolerance between the NRC's scores and the facility's scores was accep-table.
Of the five reactor operators and seven senior reactor operators that took the exam, one senior operator did not pass. He was promptly removed from shift duties and put into an accelerated retraining program.
4.
Requalification Program Requirements According to the Requalification Program, attendance is mandatory for all licensed operators, unless specific exceptions are made.
Contrary to this requirement, licensed operators wishing to make their licenses inactive are not attending scheduled requalification training. A specific exception should exist to allow their absence.
In addition, no mechanism exists to distinguish between operators missing scheduled training, because they wish their licenses to become inactive, and those who miss because of unavoidable circumstances.
Per the Requalification Program, if an operator fails a Segment or Oral Examination, a recommendation concerning his/her continuation in licensed duties is required.
No record was kept of this action.
Per the Requalification Program, Instructor participation in the program may be waived if they have received equivalent training through the ~ performance of instructor duties. Credit is given to instructors when they prepare for a given segment's scheduled training. However, a potential exists for an instructor to be waived from taking examinations , j-in two consecutive annual requalification cycles.
In keeping with the ! Denton letter requirements of March 28, 1980, instructors should be required to demonstrate their knowledge and ability for one complete annual requalification cycle within the two year renewal period by attending the training they do not teach and by taking the required examinations.
Generally, requalification program requirements are either met or exceeded. The licensee demonstrated a strong commitment to the proper conduct of licensed operator requalification training.
I . . - _ _ _ _.. - . - - _.
.
. . d
5.
Scheduled Training The training schedule for the first two week Segment was varied and comprehensive. Scheduled lectures covered theory, systems and procedures. The simulator was unavailable in the first segment due to the installation of a new high speed computer and the updating of various models.
Even though the simulator was not available, training on event diagnostics and E0Ps was scheduled for this segment. Training in this area could have been improved by delaying it until the simulator became available.
Licensee Event Report _(LER) training is being conducted to keep operators up to date on the lessons learned from facility and industry wide events. The Operations Department frequently selects the events it wants covered during Requalification training.
In many instances, these events have already been covered at shift briefings or by required reading.
Coverage of the lessons learned from industry wide events is unnecessarily delayed since plant related LERs take priority.
Scheduled training was challenging and presented a wide variety of topics. The training scheduled fulfilled training program requirements.
6.
NRC Personnel Present at the Exit Meeting S. Barber, Reactor Engineer (Examiner) 7.
Facility Personnel Present at the Exit Meeting R. Schaffer, Assistant Manager - Operations Training D. Seipel, Requalification Training Supervisor A. Orticelle, Operations _ Engineer R. Campanella, Licensing 8.
Summary of NRC Comments made at Exit Meeting , The preliminary findings were discussed.
Present industry initiatives require objectives to be written to define operator job responsibilities at their basic level.
However, the evaluation of the achievement of these objectives should be done at a more complex level.
Examinations should be written to incorporate and integrate many of the concepts required by the objectives and should not be a restatement of each objective.
Attachments: 1.
Written Examination and Answer Key (SRO) 2.
Written Examination and Answer Key (RO) -_ .-
, _. _. - LICENSED OPERATOR REQUALIFICATION ST768hn to / SEGMENT EXAM i zme: ANSWER REY Date: l l 11 work done on this examination is my own, I have neither given, nor received aid.
icensed: Senior Reactor Operator Examinee's Signature A licensed individual receiving a grade less than 70% on any segment exam or an overall grade of I-than 80% on the average of all segment exams shall be placed in a remedial requslification progras Read the entire test prior to starting.
Write answers on the test. If additional room is needed, use the back of that sheet.
l Answer each question completely, do not leave any question blank.
Points for each question of topic are indicated in parentheses. This point system is intended to indicate the depth of discussion and time required for each question. (This method can be used to , determine the time to spend on each question.)
Only one person may leave the examination room at a time! j Ensure your name, initials or SSN are in the upper right hand corner of each page of the exam.
g There is to be no conversation between examinees during the exam. Questions should be directe'd t- ] the proctor.
THIS IS A TIMED EXAM! {
r, s Segment
2
4 Total > c i i Test Possible ' I i } Pts.
15.*15 . l i - f ! i #!N bmitted: _ h4F
. viewed: ' or raining alem Opert(tio j ( / $1 W Y b h Assistant Manage /A7pe ati([s Tr ining M Yl/* $ fll0
. General Managd - Salem Operdions - ~ -- -- 1 __ _
. _.
EQUATION SHEET
i
- f = ma v = s/t Cycle efficiency = (Network i
, w = mg s = Vot + 1/2 at2 out)/(Energy in) ) ' E = mc2 a= (Vf - Vo)/t A=AN A = Ao -A t l ' e x = tn2/t /2 = 0.693/ti j KE = 1/2 mv2 w = 0 /t
PE = mgn m=Vv% ' a VF = Vo + at P= (E(V)/(3 x 1010) l' W = tap A=n D2 t /2ef f =.1.it1/2) (tg
1 + (tti ((t /2) A E_ = 9 31 a m
Ic -E X j E =aN I = e , , Q = mCha t RR = I$ I= IeUX l c I l0-x/TVL f h = xhg + (1 - x)hg I = o . Idli=Id22 ! Q = UM T S = xSg + (1 - x)Sg
' ! 2*Id22 Idl1 PWR = WgA h x=S-Se P = Po10sur (t) Sgg HVL = -0.693/ ' -. P = Poet /T TVL = 1. 3/p
, SUR = 26.06/T s=h-hp SCR = S/(1 - Kegg) CRx = S/(1 - K ggx) ) hgg e ' SUR = 26p/t * + (8 p)T CR1(1 - Keff1) = CR2(1 -kegg2
CR/CRok T
(t*/p) + ( (8 p ) /Ap ) M = 1/l(1 - Kegg)
( T = t / (p -S) M= (1 - Keggo)/(1 - Keggi) j T= (8 p ) / (Ap ) SDM = (1 - Kegg)/Kegg.
! o = (Kegg-1)/Kegg = a Kegg/Kegg t* = 10-5 seconds j = ( (t */(T Kegg)) + (g egg /(1 + A T)) _ j p A = 0.1 seconds -1 ( R/hr = 6 CE/d2 (feet) R/hr = (0.5 CE )/d2(meters)k Water Parameters Miscellaneous Conversions
l 1 gal. = 8.345 lbm.
1 curie = 3.7 x 1010dps i 1 gal. = 3.78 liters 1 kg = 2.21 lbm f 1 ft3 = 7.48 gal.
1 hp = 2.54 x 103 Btu /hr
Dansity = 62.4 lbm/ft3 1 mw = 3.41 x 106 Btu /hr Density = 1 gm/cm3 1 in = 2.54 cm i Heat of vaporization = 970 Btu /lbm OF = 9/50F + 32 Heat of fusion = 144 Btu /lbm OC = 5/9 (OF-32) $ 1 Atm = 14.7 psi = 29.9 in. Hg.
1 BTU = 778 ft-lbf [f H O = 0.4335 lbf/in.
.} 1 ft.
l l ~ ~ . , m._ mm-
... -. - - - - -... _. . .. _.... -. -. _. -... - - SYSTEM: Reactor Theory
, TASK ID.:
, I TASK: L.P. NO.: - 302/304-145.08-RXTH01-03 l (
OBJ. NO.:
- OBJECTIVE:
From memory, when provided with the appropriate
t percent abundance in nature and atomic weight of j
its isotopes, be able to calculate the average I atomic weight of any element.
j
Question-Natural uranium is composed of three (3) isotopes, 234U, 235U, and 238U.
Their abundances and atomic weights are given in the table below.
Compute the
} atomic weight of natural uranium.
(Show all work)
I / , ISOTOPE ABUNDANCE, % ATOMIC WT.
) ,1
234U 0.0057 234.0409 ~ j Y l - -3 235U 0.72 235.0439 ' ' 238U 99.27 238.0508 - i , . ? <- l i I (0.5 pts) ! ANSWER: ,j l (.000057)(234.0409) + (.0072)(235.0439) + (.9927)(238.0508) i =.01334 + l.6923 + 236.313 g . f 238.02 = (.45 pts for setup,.05 pts for math.
If work not shown.50 pts N , for answer.)
, - E . i
. i Y - 302-SRO-AK-0-1- _ _ ___ _ - - - , fl i i SYSTEM
Nuclear Mass and Stability Concepts TASK ID
TASK
, L.P. NO.
302/304-145.08-RXTH03-03 OBJ. NO.
3, 4 OBJECTIVE : State the equation for mass-energy equivalence and its 9j relation to nuclear reactions. Calculate the mass defect for a given nucleus.
Question: The binding energy from mass defect of a U-235 atom can be calculated as follows: (0.5 pts) E = [92(1.0078)+(235-92)(1.0087) - 235.0439] 931MeV i }[, amu . i y j E = 1.9178 amu x 931 MeV = 1785 MeV - . amu .
- j i
Considering the above calculation, why is,only 200 MeV of energy released from !
fissioning of one U-235 atom? ! ! !* h ) Answer: The fission fragments retain the difference in the energy released from l fission and the total mass defect.
.(0.5 pts) j; d ' i l ! l u ! Ii 'N I
- ~ -
%
" \\ n ki - - - - _ __ _ --
.. _ _ _ _ _ _.. _ _. Heat Transfer, Fluid Flow and Thermodynamics
SYSTEM
TASK ID.
TASK
L.P. NO.
r 302/304-145.03-HTFF04-01 > OBJ. NO.
OBJECTIVE : Define and give equations (where applicable) for the following thermodynamic terms: Boiling, Saturated Steam, Superheat, Moisture ' Content, Latent Heat of Vaporization
Question: Fill in the blank with the word or phrase which (1.00 pts)
most closely fits the description.
, The process which occurs when vapor pressure and a.
atmospheric pressure are equal.
b.
A vapor at the same temperature and pressure as the liquid from which it was formed.
The number of degrees between saturation temperature- <
c.
for steam and its actual temperature.
' ( d.
The amount of liquid present in a mixture of liquid $ and vapor.
The amount of heat required to change 1 lbm Of i e.
saturated liquid to saturated vapor.
(. $ i l t Answer-i a.
Boiling (0.20 each) , b.
Saturated (or steam) I - c.
Superheat (or degrees superheat) d.
Moisture content e.
Latent heat of vaporization C o+ \\s g . - E .- , I s, c $ 302-SRO-AK-0-2 _ _ _ _ -- __ -
. - t ! mJ) , i s SYSTEM
MTSC l
-d TASK ID
- !
TASK
L.P. NO.
302/304-145.17-MTSC-04-01 OBJ. NO.
2, 6 j OBJECTIVE : State Hooke's Law and define the Modules of Elasticity. Define
six general types of stresses found in the plant and give one ] example of each.
Question: j , What mechanical property allows a metal to return to its original shape a.
and size when an applied stress is removed? (0.25 pts) b.
Explain the mechanism by which a material may fail below its proportional
limit.
(0.5 pts) ' . $ Answer: .- y a.
Elastic deformation.
p q.g c, e e c ;by (0.25 pts) ' g a & + < Dulate 6 D ( l ", b.
Repeated or cyclic stresses,cause microcracks%c. ich reduce the strength i of material enough to cause failure below the proportional limit.
g (.5 pts) g b'k on k abe ex% h'M, o
u . ., i ! ! @ < , s
- - - _ _ _ _ __ . - - -
_ _ _ ,
SYSTEM:
- .
ECCS
TASK ID.
006-519 i' TASK
< L.P. NO.
302/304/305-145.07-ECC-02 ', OBJ. NO.
8/9.3 g OBJECTIVE : List the five (5) signals, including setpoints and
j logic, that will initial a safety injection.
! , Question:
List the five (5) signals that will initiate a safety injection.
(1.25 pts)
t -
i
l !
' . . I
'
ANSWER:
(.25 pts each j g ' part) l.
Manual 2.
RCS Pressure 1765 psig 3.
Containment Pressure of 4.0 psig )il 4.
Any one Steam Generator 100 psig Lower than any two other I j ' Steam Generators.
6 #/hr 0.20% load, 5.
Variable Steam Line Flow (1.46x10 ' 6 t/hr at 100% load, in coincidence with increasing to 4.0x10 Low Tavg 5430F or Low Steam Pressure of 500 psig.
> (Or, High Steam Flow coincident with Low-Low / Low Tavg or Low , Steam Pressure) s A . @ b - - - _ _ ^"^ - - & 4.
, _
.. _ -... _.
., SYSTEM:
ECCS TASK ID.
006-510 TASK
- .
State the boron concentration requirements of the following 302/304/305-145.07-ECC-02 L.P. NO.
OBJ. NO.
1.5 State the boron concentration requirement of the OBJECTIVE : following.
1.
RWST 2.
BIT 3.
Accumulators Question: I State the boron concentration requirements of the following: (0.75 pts) 1.
RWST 2.
BIT 3.
Accumulators , . ( ANSWER:
(0.25 pts each ' part,.125 pts . for high limit, ! .125 pts for i low limit) b ii I 1.
RWST 2000 ppm to 2200 ppm i 2.
Unit 1, BIT-20,100-21,800 $ Unit 2, BIT 20,000-22,500 g if 3.
Accumulators 1900 ppm to 2500 ppm (JuJ.*r SL M > Moo %Wi
It ] ' $
2 i G ( ,- -i ! , ~ - r - 302-SRO-AK-0-5 __ _l - -
.. -. - -- . SYSTEM:
ECCS TASK ID.
006-509 I TASK
L.P.
NO.
r 302/304/305-145.07-ECC-02 ! OBJ. NO.
1.1 i
OBJECTIVE : List the three (3) purposes of the ECCS.
Question: List the three purposes of the Emergency Core Cooling System.
(0.75 pts) , o i
.
t I s ) ANSWER: Y (0.25 pts each I Part) j i 1.
To provide emergency core cooling in the event of a major i loss of primary coolant by iniecting large quantities of primary grade borated water into the RCS, g - i 2.
To provide a rapid increase in boron concentration of the $ coolant in the event of a major steam line break, overcoming i ! the positive reactive added by the rapid cooldown of the RCS , under the worst initial conditions, hot standby, to f limit the power escalation to an acceptable value before the j boric acid causes subcriticallity.
g I 3.
To provide Lona-Term core cooling following a Primary Loss pl of Coolant Accident.
? (Underlined portions for full credit) $ k i g o o l k
302-SRO-AK-0-6_ , _ - -
_ _. _,, .. _. - - - - - - -. _ _ , ., $ \\
' i SV EM
MCD/Po:t Accident Cooling TAS
i TASK
L.P. h0.
302/304-145.15-POST-00 OBJ. NO.
! OBJECTIVE. List the ECCS acceptance criteria and state the purpose for l each criteria.
! Question: During a LBLOCA, w will the operator verify that the following ECCS ! acceptance criteri are being met? (0.75 pts) I a.
Clad temperhtur less than 2200* F.
b.
Hydrogen generati less than 1%.
. c.
Coolable geometry preserved.
, j G } Answer: g' t o a.
Incore thermocouples.do no 1 icate superheat or RCS is subcooled under t i forced circulation. (F p e_m g m s (0.25 pts) I i b.
Containment hydrogen content s ble at low levels.
(0.25 pts)
A
c.
Incore thermocouples show a norma post trip temperature distribution.
'. Effects of safety injection seen o incore thermocouples in NC.and RTDs in FC.
(0.25 pts) H c.FSN
j M - p a& A Lf, . ' Ok ECCS %.es $ e s ' E i I %~ha CAed ~N.eg.
i m sco ,
-- $ ,
' ^ - 's .. % g o__, _ m os % _o m ~ e %,,s h . N - _ . .- _ _ me< o "~ '
c - ... . - ~. -. -. , I SYSTEM: RHR ' TASK ID.
005-504/$08
f TASK: Fill, vent, and align the RHR system for power r o'peration L.P. NO.: 302/304-145.07-RHR-02 OBJ. NO.: 1/2.11 y OBJECTIVE: Describe the interlocks associated with the (1.5 pts) ?
following valves: (Include any unit ! !. differences) i i . f ANSWER: I Describe the interlocks associated with the following valves: J a.
RH1 and RH2 g
C' ' RH1 - open int ik < 390# (.125 pts ! j each) , auto. closure > 570# , RH2 - open intlk < 390#(and Key (.125 pts ! each) ,3
auto. closure > 5703 (
b.
SJ - 44's (both units)
p b'... 12SJ-44 - cannot open SJ-44 until its (0.25 pts) ! 11 & associated RH4 is fully closed 21 & 22SJ-44 - RII4 will stay open until its (0.25 pts associated SJ44 is fully open ! i J (duringsemiauto,swapover)/ ' bnd then RH4 will close. & $ t ~ 2/q f_st)S7-Lo Lo c.
SJ - 45's gg
OI Associated SJ44 must b'e open and SJ67 or (0.125 pts ' ... each part) / SJ68amust be closed.to openthe SJ45.
- U M #-6fL er. E 4 2 cl W '4__ i d.
CS - 36's s+#E ' - (0.125 pts . - - - C.6 h RH1 or RH2 fully closed and each part) , associated SJ44 fully open.
(Underlined portions for full credit)
% n_Q Y' Je,- w e . lt h ' e2 v 'S m J w s 4i - _302-SRO-AK-0-8 ~ ~ . . = __ - -
-== M W r- ' . , . _ - - - -.. - - - - -...... i ! d
SYSTEM
RHR M
TASK ID
TASK
.
L.P. NO.
302/304-145.07-RHR-01 OBJ. NO.
11/12.3
OBJECTIVE - State how the semi-automatic switchover system operates.
i g Question: i Bhat is the purpose of each of the following design features in accomplishing f the semi-automatic switchover in Unit 2? a.
RHR pump suction line check valve.
(0.5 pts) b.
Latching relay.
(0.5 pts) m , hMN5 6(( f$h . Answer: _at-Prevents both RHR pumps from drawing a suction _ from the same pump suction * -j a.
line in tne event an SJ-44 valve fa1.ls to op~en on switchover.
(0.5 pts) } 6 ?y,w Gbw m " h tv e, c b.
' Retains the SI signal for switchover when the SI signal is reset at.. .! . e1thir train "A"'or "B" befel.
(0.5' pts) { ~ ~
_ '
g . l ' . I l , k ' o
> _ _ - - m __ w '
,~ , , I SYSTEM
MS j TASK ID.
005-507 TASK
- .
Assess the implications of a failure to comply t with an Action Statement.
L.P.
NO.
302/304/305-145.11-MS-01 OBJ. NO.
3.2 , OBJECTIVE : State the bases for Technical Specification j 3/4.7.1.5.
e Question: Technical specifications require that each main (1.0 pts) i steam isolation valve be operable.
What is the basis for this spec?
. . ANSWER: Ensures no more than one S/G will blowdown in event (0.5 pts) of steam line rupture to: [ p 1.
Minimizes the positive reactivity effects (.125 pts due to RCS cooldown.
each part) 2.
Limit the pressure rise within containment (.25 pts) if rupture occurs in containment.
, { e ": .i . .... c . W H - 302-SRO-AK-0-9[[ [~ .. _ ' - w
. <--- SYSTEM
MS TASK ID.
039-503 ~ Operate the main steam stop valves ! TASK
L.P. NO.
302/304/305-145.ll-MS-01 ! i OBJ. NO.
1.4
OBJECTIVE : State the conditions that will initiate an Emergency Closure Signal.
Question: State the conditions that will initiate (0.75 pts) an Emergency Closure Signal to a main steam isolation valve.
(MS-167) 25 S scP'i Mi - Hi CerAtd^* N" l ANSWER: ' ' 1.
Maiti Steam Line Isolation from SSPS gi 1299p (.25 pts ,! py each) . , , 2.
Safeguards bezel pushbutton f_o - Qg h1 SW5'F) Una i 3.
Steam generator isolation bezel pushbutton D) (Underlined portions for full credit) { $ 4i
.. . > .!
& kr %
e I
- .
bW
5 k ~ - 302-SRO-AK-0-10 _l - _
_-_ _-_ Bleed Steam and Miscellaneous Drains ', SYSTEM
! TASK ID.
039-516 Direct subordinates in aligning the bleed steam TASK
- system for normal operation.
L.P. NO.
302/304/305-145.ll-BS-02 OBJ. NO.
1.3 OBJECTIVE : List / State the system and major components supplied by the Bleed Steam System.
> ! Question: ! Column A contains the components supplied by (1.0 pts) ! the bleed steam system.
On the line at the left of each component, write the letter of the component in Column B that is the source of steam.
Each component in Column B may be ' used once, more than once or not at all.
Column A Column B 1.
16(26) Feedwater Heaters A.
The low pressure turbines 2.
15(25) Feedwater Heater B.
The high pressure turbines i . , 3.
14(24) Feedwater Heaters C.
The Main Steam
System j i 4.
13(23) Feedwater Heaters ? ?
5.
12(22) Feedwater Heaters 6.
11(21) Feedwater Heaters 7.
Heating Steam System 8.
Bleed Steam Coil of the MSR ANSWER: (0.125 pts each)
L 1.
B 5.
A h' 2.
B 6.
A 3.
A 7.
B ' 4.
A 8.
B .. - 302-SRO-AK-0-ll _ __ __
_ , _ _ _.. _ _. - SYSTEM
Heater Drain j TASK ID.
039-520 Direct subordinates in aligning the Heater Drain TASK
System for normal operation.
L.P. NO.
302/304/305-145.ll-HD-02 OBJ. NO.
1.3 OBJECTIVE : Recall the Drain Flowpath for each Feedwater Heater and the Feedwater and Moisture Separator Reheater Drain Tank.
- l Question: ! Select the correct answer (s) (.5 pts) !/
Drains from the 16(26) Feedwater Heater are directed to:
h a.
The 15(25) Feedwater Heater.
b.
The Feedwe.ter Heater and Moisture Separator Reheater - Drain Tack.
c.
The Main Condenser.
d.
The 14(24) Feedwater Heater.
. , _ ANSWER: , " b,c (.25 pts each.
! Subtract.25 pts for each incorrect choice)
' , -c . h\\- ! p,0 _ , s -
i i i i ~ ~302-SRO-AK-D-12 c - __ -- - _
..- SYSTEM
Heater Vent TASK ID.
039-526 TASK
- .
Direct subordinates to close all of the shell vents to condenser bypass valves at 15% power.
L.P. NO.
302/304/305-145.ll-HV-02 OBJ. NO.
2.3 OBJECTIVE : Recall the flowpath or the shell vents.
Question: \\ ' Select the correct answer (s).
The shell vent path for the 15(25) feedwater (0.5 pts) ' heater is from the heater to-a) The Main Condenser b) The 14(24) Feedwater Heater c) The Feedwater Heater and Moisture Separator Re-heater j Drain Tank W d) The 16(26) Feedwater Heater , -
. tj ANSWER: ' a - The Main Condenser (0.5 pts) b , k , i E i f . ~ - - 302-SRO-AK-Q-13_
m -
....n.
- - - . - -. -_ _ _. _ _ _ _ _ _ _ _ _.. _ _ ... SYSTEM: Miscellaneous Condensate y TASK ID.: 113 502 TASK: Direct subordinates in operating the MC System.
L.P. NO.: 302/304/305-145.ll-MCOl-00 OBJ. NO.: 1.4 OBJECTIVE: Describe the purpose of stem sealing and why it is used for valves under a negative pressure.
. >
Question: } d The Miscellaneous Condensate System provides (.25 pts) q valve stem sealing water.
What is the purpose
of the valve stem seals? f . h1 ! .4 ' d . q~ j
- - , e , , .' i Answer: Valve steam seal water is provided to eliminate / minimize air
leakage into the feed and condensate system.
(or, help maintain condenser vacuum) (Either for full credit) - (0.25 pts) ,
I %
$ i
i ' j ~ - - 3 0 2-SRO-AK-0-14 s
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _,, _ _ _ _ _ _.. _ _ _. _ _. _ _ _ _ _ _ _ _. _._ _ SYSTEM: Reactor Vessel Level Indication System j , TASK ID.: 002 537 j TASK: Operate the Reactor Vessel Level Indicating System (RVLIS) y > L.P. NO.: 302/304-145.12-RVL-01 ' < OBJECTIVE: State where the RVLIS differential pressure ! detectors are located and why they are located as they are.
!
l List the process input signals utilized by , RVLIS.
, , Describe the indication (s) provided on the
RVLIS display screens which denote when ' j abnormal conditions affecting the indicated < i values are present.
Answer the following true or false concerning (.75 pts) l the RVLIS.
l l a.
The RVLIS AP cells are located outside containment to ! minimize inaccuracies due to the possible containment environmental conditions.
j
b.
" Invalid" means the hydraulic. isolator is overranged.. ~ , e f c.
Density compensation is required since the.RCS pressure could be between 0 and 2485 psig.
. t Answer: (.25 each) a.
True b.
False c.
False . 302-SRO-AK-0-15 _ _ _ __ __ _
. _.---_ _ - -.. - - - - - -. -. -.. . .. - - ---. - , , ' s A SYSTEM
Mitigation of Core Damage / Post Accident Cooling - , TASK ID
TASK
L.P. NO.
305/145.15-POST-00 OBJ. NO.
OBJECTIVE : Describe the effects of non-condensable gases present in the
RCS during a small break LOCA on natural circulation flow.
j i i Question: }
a.
Analysis of a 2 inch SBLOCA shows that 1648 ft (at standard temperature
and pressure) of non-condensable gases are produced in 4050 seconds.
' Each model 51 steam generator has a tube bundle volume of 760 ft', 100 l ft' of which is contained in the bend space. The conclusion reached was that natural circulation flow would not be blocked or impeded for this S8LOCA, how is this possible? (0.5 pts)
e . Answer: ,' f . I e ! l The gas volume is significantly lower (50 ft') for the actual plant i l temperature and pressure.
(0.5 pts) . I h .
-. w- - . - - - -. " -
___________--- ,
' O SYSTEM: Mitigation of Core Damage / Post Accident Cooling . TASK ID.: ? TASK: , M L.P. NO.: 305-145.15-POST-00 OBJ. NO.: 4.0 OBJECTIVE: State the hydrogen concentration in air, required , for combustibility (including explosions).
' , Question: . . I Fill in the following blanks.
(0.25 pts) e Hydrogen in various concentrations in air can be either a t.! combustible or explosive hazard.
In air, hydrogen is neither j f l - combustible nor explosive below
% and above
%. ' . l - (0.125 pts ' each part) . i
, s . ? - l
,
' I i , . !' ) i . ~ ! . i l ' ' - - ' - 4W,, _..,.,, - - - -
.... .... _ _ _.... _ -.. - - _ _ _ _ k SYSTEM: Refueling Operation j < TASK ID.: 034-514 TASK: Perform Refueling Surveillance Procedures in
4 accordance with Tech. Spec.
I L.P. NO.: 302/304/305-145.10-RO-01 OBJ. NO.: 14.0 & 3.1 OBJECTIVE: Determine the more restrictive reactivity . condition in Mode 6.
l t ' i Question:
Circle the letter of the condition (s) which (0.5 pts) i would require a halt to fuel loading: } r a.
The most recent boron concentration is 12 ppm less than the previous (3) samples.
b.
One channel of Source Range Instruments increased from 17 cps to 48 cps after the initial (8) fuel assemblies are - { loaded.
,, k l The Maintenance Supervisor reports that the last 31 days c.
surveillance requirement for containment integrity was i performed 2 days late.
I ] T d.
Boron concentration is 1975 ppm with Kegg = 0.96.
j { t i t l t i,
Answer: d.
Boron concentration is 1975 ppm with Kegg = 0.96. (0.5 pts) , - _ _ _ __ OOO m-4 e aa &
_ , ,, - -. _ _ _ _ _, _ , ! . I
i SYSTEM: Refueling Operation g l m TASK ID.: 034-530 ' TASK: State the immediate corrective action for a High . ' Flux at Shutdown Alarm.
L L.P. NO.: 302/304/305-145.10-RO-01 '
OBJ. NO.: 30.0 + 8.0 OBJECTIVE: State the immediate corrective action for a High g j Flux at Shutdown Alarm.
g ,
' Question: s W <
State the proper response by the Control (1.0 pts) .
Operator to a "High Flux at Shutdown Alarm".
y ,
h i f $ - s g Answers-d 1.
Verify count rate increase on control console (0.125 ! for both source rance NI's.
each part) 2.
Rapid borate.
(0.25 pts) 3.
Announce on P.A. System High Flux Alarm (0.125 and instruct all personnel to evacuate each part) the containment immediately.
. 4.
Calculate shutdown margin.
(0.25 pts)
- 1 (Underlined portions for full c,redit)
! ' l .
- - _ p - - _
'
LICENSED OPERA REQUALIFICATION SEGMENT EXAM $ eme: ANSWER KEY Date: ' 11 work done on this examination is my own, I have neither given, nor received aid.
l l i < cznsed: Reactor Operator P . ' Examinee's Signature
! .. A licensed individual receiving a grade less than 70% on any segment exam or an overall grade of 1-than 80% on the average of all segment exams shall be placed in a remedial requalification progran j Read the entire test prior to starting.
, i ' Write answers on the test. If additional room is needed, use the back of that sheet.
Answer each question completely, do not leave any question blank.
, Points for each question of topic are indicated in parentheses. This point system is intended to I indicate the depth of discussion and time required for each question. (This method can be used to determine the time to spend on each question.)
- i Only one person may leave the examination room at a time! 5li-Ensure your name, initials p_r SSN are in the upper right hand corner of each page of the exam.
1I .. There is to be no conversation between examinees during the exam. Questions should be directed t;_
. _ 1, the proctor.
j) f THIS IS A TIMED EXAM! f i 1 . h F } l Segment
2
4 Total a' Test-Possible 3j ,
Pts.
15. 6 I " g, ] ' '
- I [ ~ a _Q bmitted: 9,, rt - _+ __ o l - _, - viewed: - M M [ asfdP@pe %/97.
alem Operations / ining r- ~ A , l Assistaiit Manager Wperatl% raining
- ~ '
?b fhl5 General Mana(er -3alem O ferations - _ - r -. - t >
__ . ..- . ,. U l EQUATION SHEET b
- J
' d H
- 'j-f = ma v = s/t Cycle efficiency = (Network
. w = mg s = Vot + 1/2 at2 out)/(Energy in) f E = mc2 a= (Vf - Vo)/t A=1N A = Ac -A t ( e KE = 1/2 mv2 w = 0/t A = tn2/t1/2 = 0.693/t ,, PE = mgn m=Vav50 ' VF = Vo + at P= (E (V) / (3 x 1010)
W = YA P A=n D2 t /2ef f = !.it1/2) (tbd i
1 (t' ((t /2) + aE = 931 am
E =aN I = Ic -EX q e , , Q = mCp A t RR = E$ I = Ic 11X e Io10-x/TVL h = xhg + (1 - x)hg I = . Idlt=Id22
Q = UA6 T S = xSg + (1 - x)Sg 2=1d22 ,f j
Idl1 PWR = Wg h x=S-Sr P = Pol 0sur (t) Sfg HVL = -0.693/p ' f j - P = Poet /T TVL = 1.3/p j l
{ SUR = 26.06/T s=h-hp SCR = S/(1 - Keff) y j n hgg CRx = S/(1 - K ggx) ( l e ' SUR = 2 6p /t * + (3 p)T CR1(1 - Keggi) =CR2(1-kegg$ ' T= (t */p ) + ( (g p ) /A p ) M = 1/1(1 - K gg) = CR /CRo
< e T = t / (p -g) M= (1 - Kef fo)/(1 - Keggi) T= (3 p ) / up ) SDM = (1 - Kegg)/Kegg ' = (Kegg-1)/Kegg = AKegg/Kefg g* = 10-5 seconds ' p p = ( (t */(T Kegg)) + (S egg /(1 + A T)) _ 0.1 seconds -1 A = R/hr = 6 CE/d2 (feet) R/hr = (0.5 CE )/d2(meters) Water Parameters Miscellaneous Conversions 8.345 lbm.
1 curia = 3.7 x 1010dps 1 gal.
= 1 gal. = 3.78 liters 1 kg = 2.21 lbm 1 ft3 = 7.48 gal.
1 hp = 2.54 x 103 Btu /hr l Density = 62.4 lbm/ft3 1 mw = 3.41 x 106 Btu /hr g Density = 1 gm/cm3 1 in = 2.54 cm g Heat of vaporization = 970 Btu /lbm OF = 9/50F + 32 g Heat of fusion = 144 Btu /lbm OC = 5/9 (OF-32) fe 1 Atm = 14.7 psi = 29.9 in. Hg.
1 BTU = 778 ft-lbf g H O = 0.4335 lbf/in.
I 1 ft.
-- -- t - _ _ _ __ _ ~- - --.... _
.. - -. ... - _. _ -- . , -- SYSTEM: Reactor Theory , TASK ID.: ,
TASK: L.P. NO.: - 302/304-145.08-RXTH01-03 f OBJ. NO.:
t ? l OBJECTIVE: From memory, when provided with the appropriate ' percent abundance in nature and atomic weight of
its isotopes, be able to calculate the average ! , atomic weight of any element.
! i Question: Natural uranium is composed of three (3) isotopes, 234U, 2350, and 238 Their abundances and atomic U weights are given in the table below.
Compute the - ! '[ atomic weight of natural uranium.
(Show all work) c I s f I ISOTOPE ABUNDANCE, % ATOMIC WT.
s i) 234U 0.0057 234.0409 [ 2350 0.72 235.0439 $ - j 238U 99.27 238.0508 - h ' s (0.5 pts) & ANSWER: .) ' t (.000057)(234.0409) + (.0072)(235.0439) + (.9927)(238.0508) .01334 + 1.6923 + 236.313 = = 238.02 Y (.45 pts for setup,.05 pts for math.
If work not shown.50 pts f q for answer.)
g M b i_W eea d.s i
i - 302-SRO-AK-0-1 - _ _ --
_ d ( l ' ' I ( SYSTEM
Nuclear Mass and Stability Concepts l TASK ID
TASK . L.P. NO.
302/304-145.08-RXTH03-03 OBJ. NO.
3, 4 ,
OBJECTIVE : State the equation for mass energy equivalence and its i relation to nuclear reactions. Calculate the mass defect for a given nucleus, h I Question: ' The binding energy from mass defec; of a U-235 atom can be calculated as follows: (0.5 pts) l E = [92(1.0078)+(235-92)(1.0087) - 235.0439] 931MeV amu
- .
, E = 1.9178 amu x 931 MeV = 1785 MeV f . amu , Considering the above calculation, why is only 200 MeV of energy released from fissioning of one U-235 atom? I e . Answer: If I h The fission fragments retain the difference ~ in the energy released from $ fission and the total mass defect.
(0.5 pts) L , , ' r ii e '
%
ng vi l l ~ } - - E __ ~ ^ ^ _
- ., _ _ _ _ _. . -. , , - - - SYSTEM
Heat Transfer, Fluid Flow and Thermodynamics
! TASK ID.
i TASK
- )j L.P. NO.
302/304-145.03-HTFF04-01 OBJ. NO.
{ OBJECTIVE : Define and give equations (where applicable) for ' , the following thermodynamic terms: Boiling, Saturated Steam, Superheat, Moisture i Content, Latent Heat of Vaporization } } ! Question:
l Fill in the blank with the word or phrase which (1.00 pts) l .aost closely fits the description.
l j The process which occurs when vapor pressure and " a.
atmospheric pressure are equal.
b.
A vapor at the same temperature and pressure as the , liquid from which it was formed.
L
1 Thenumberofdegreesbetweensaturationtemperaturej c.
for steam and its actual temperature.
_';; d.
The amount of liquid present in a mixture of liquid
and vapor.
{ f . \\ The amount of heat required to. change 1 lbm Of $ e.
saturated liquid to saturated vapor.
eI ' ! . i > f l , ' Answer: J l l a.
Boiling (0.20 each) I
1 F{ j i ! b.
Saturated (or steam)
c.
Superheat (or degrees superheat) ?; d.
Moisture content ,a e.
Latent heat of vaporization (p g . p .. g - - . n M e
1 N . l { l - - - 302-SRO-AK-0-2 -
E -- ? l
- ..
MTSC
302/304-145.17-MTSC-04-01 nts and i df) ' f Modules of Elasticity. Define IE!'its 2, 6 , t:'jf State Hooke's Law and define thesix general types of stresses found in th I D - 'M example of each.
' pad tion.
. W R {.Q,,, }
chanical property allows a metal to return to its original shape t (0.25 pts) I 'd&It'ie when an applied stress is removed? l }[ lain the mechanism by which a material may fail below its proportional - d , (0.5 pts) E p amit;.~
n %a, , ;, feg N.h t
- (0.25 pts) }.'e, ehsW Nf I,cdQcdeformation.
che %.9.~ W%< t eptated or cyclic stresses *cause microcracks which reduce the strength { u
pfGy frmaterial enough to cause failure below the proportional limit.(0.5 pts)
N j$ e .s, qu+) ach fj jjp (."2,.1,.Q .) ,,
- t
! F 1; % er s
g e
with { , ' g, . E ! ! Low f US/ i ON_ .
% .# ... h . I __ - -_ _ -.
h _
- ..__ _ ,
SYSTEM:
ECCS j , J > TASK ID.
006-509
TASK
L.P. NO.
i 302/304/305-145.07-ECC-02 ] 'd OBJ. NO.
1.1 OBJECTIVE : List the three (3) purposes of the ECCS.
j
- 1 Ei
$ Question: List the three purposes of the Emergency Core Cooling System.
, j '
' (0.75 pts)
i
!
i , f J
h ~l .- P I
- p i ANSWER: J - lf (0.25 pts each Part) ! 1.
To provide emergency core cooling in the event of a major I loss of primary coolant by iniecting large quantities of l primary grade borated water into the RCS.
2.
To provide a rapid increase in boron concentration of the i coolant in the event of a major steam line break, overcoming !' the positive reactive added by the rapid cooldown of the RCS under the worst ini~tial conditions, hot standby, to ,limit the power escalation to an acceptable value before the boric acid causes subcriticallity.
3.
To provide Long-Term core cooling following a Primary Loss of Coolant Accident.
(Underlined portions for full credit) , { . . - l?r
I k
- 30_2-SRO-AK-0-6 _.
- - - - - + _ _.
_
. - -... _. -. - - -. , - ! !
SY3T
MCD/ Post Accident Cooling ] l q TASK -
TASK
L.P. NO.
302/304-145.15-POST-00 OBJ. NO.
- OBJECTIVE.
List the ECCS acceptance criteria and state the purpose for each criteria, j 1i ' Question:
During a LBLOCA, h will the operator verify that the following ECCS i acceptance criteria re being met? (0.75 pts)
a.
Clad temperature ss than 2200* F.
b.
Hydrogen generation ess than 1%. j f c.
Coolable geometry pres ved.
.i . . Answer: }t a.
Incore thermocouples do not dicate superheat or RCS is subcooled under j [ forced circulation.
(FC) L WD (0.25 pts) } $ b.
Containment hydrogen content sta le at low levels.
(0.25 pts) { a c.
Incore thermocouples show a normal ost trip temperature distribution.
l Effects of safety injection seen on incore thermocouples in NC and RTDs in FC.
(0.25 pts) , k, h ! j l.
em l . t
.- - a _ - _ - i, _. _ -
! ~
__-_ _ _ .. . ,- - _ _ SYSTEM: RHR i TASK ID.
0.05-504/508 ' TASK: Fill, vent, and align the RHR system for power ' operation L.P. NO.: 302/304-145.07-RHR-01 a OBJ. NO.: 1/2.2 j OBJECTIVE > List the four factors which lead to the production of
residual heat.
, 1, QUESTION: List the four factors which lead to the production of residual ! i heat.
(0.5 pts.)
i , I -
. j i - l,
1
. ANSWER: (0.125 pts. ea.)
_ i l.
Decay of short-lived fission products
2.
Decay of long-lived fission products ! 3.
Fission caused by delayed neutrons emitted by certain l fission products i l
' 4.
" Sensible" heat remaining in the fuel /RCS.
(Underlined portions for full credit.)
. ~ ~ _ '302-RO-0-AK-7 _ __ _-
- _ _ _ _ _ _ _ _ _ , _ ____ ! SYSTEM: RHR TASK ID.
005-504/508 TASK: Fill, vent, and align the RHR system for power operation L.P. NO.: 302/304-145.07-RHR-02 OBJ. NO.: 1/2.11 ( OBJECTIVE: Describe the interlocks associated with the (1.5 pts) ' following valves: (Include any unit l differences) i $ ANSWER: j t Describe the interlocks associated with the following valves: i l a.
RH1 and RH2 - RH1 - open int ik < 390# (.125 pts each) auto. closure > 570# , RH2 - open intlk < 390#(and Key ,{[ g (.125 pts
each) -j auto. closure > 570# .- 3
$ b.
SJ - 44's (both units) !? 11 & 12SJ-44 - cannot open SJ-44 until its (0.25 pts)
associated RH4 is fully closed g 21 & 22SJ-44 - R tay open until its (0.25 pts ' associated S74 bis fully open (during semi auto, g nd then RH4 will close M " .. c.
SJ - 45's .e Associated SJ44 must be open and SJ67 or (0.125 pts $ SJ68 must be closed to openthe SJ45.
each part)
%o RAN qe_ Q.n the f {f & d.
CS - 36's (0.125 pts RH1 or RH2 fully closed and each part) p associated SJ44 fully open.
(Underlined portions for full credit) -
mw-
== &
e_ ~ 302-SRO-kK-0-8 __-- __ s
_ _ - _ _ - - - - - _ - - _ _ - - ..- _ - -. - - -- -- - - h i4 I l l SYSTEM
'RHR ! TASK ID
TASK
L.P. NO.
302/304-145.07-RHR-01 OBJ. NO.
11/12.3 OBJECTIVE : State how the semi-automatic switchover system operates.
l Question-t! hat is the purpose of each of the following design features in accomplishing l ) the semi-automatic switchover in Unit 27 , a.
RHR pump suction line check valve.
(0.5 pts) b.
Latching relay.
(0.5 pts)
- p.,43 swr TW f
Answer: O' .2rpe _ Prevents both RHR pumps from drawino a wtion_ from the same pur::p suction . a.
_- . line in the event an SJ-44 valve fails to open on switchover.
t (0.5 pts) . b.
Retains the SI signal for switchover when the SI signal is reset at I either train "A" or "B" bezel.
(0.5 pts) .. l
i I ' ' , ! e j _ _.
_ . -,.. - - -, - - ______ . . - - - - - - - - -
_ _. _. _ i SYSTEM
MS , , i
TASK ID.
039-503 Operate the main steam stop valves i TASK
L.P. NO.
302/304/305-145.11-MS-01 li OBJ. NO.
1.3.1 OBJECTIVE : State / explain the mechanical operation of a Main Steam Isolation Valve.
f QUESTION: Explain how an emergency closure signal causes a Main Steam -'
Isolation valve (MS-167) to close.
Include; solenoid valve, dump valves and how the closing force is generated.
(1.0 pts.)
(A drawing may be helpful.)
' . .. ! -h . - , . ) ! ?! ? b ANSWER: j b 1.
Solenoid valves energize, bleed air off the dump (.2 pts.)
y ( valves.
I I 2.
Dump valves reposi tion. / 'r# (.1 pts.)
f 3.
Steam from top of lower piston vents to (.2 pts.)
i atmosphere.
4.
Oriface between upper and lower side of lower (.2 pts.)
{ k piston can't keep up.
5.
Pressure below lower piston greater than above.
(.2 pts.)
}
,,ince force = pressure x area, closing force (.1 pts.)
{ S 6.
is generated.
,, i
(Underlined portions for full credit.)
i ' 302-RO-0-AK-9' _ _ _.
_ _ -. -
- - - - - - - _ _-______.
i SYSTEM
MS
TASK ID.
039-503 Operate the main steam stop valves TASK
L.P. NO.
- ~
302/304/305-145.ll-MS-01 OBJ. NO.
1.4 OBJECTIVE : State the conditions that will initiate an Emergency Closure Signal.
i ( l Question:
State the conditions that will initiate (0.75 pts) ! ? an Emergency Closure Signal to a main steam isolation valve.
(MS-167) i a ANSWER: 1.
Main Steam Line Isolation from SSPS (.25 pt.s [ each) " '! 2.
Safequards bezel pushbutton p - 3.
Steam generator isolation bezel pushbutton (Underlined portions for full credit) d . b Sh Roe w0%
9 f's tew -uou h~ c o-Lw b7% 9.e t en%J ^* ODb . , y --, e- . l I, f4 302-SRO-AK-0-10 .,_ _ _ _ _
- __ - Bleed Steam and Miscellaneous Drains SYSTEM
, < TASK ID.
039-516 Direct subordinates in aligning the bleed steam i TASK
system for normal operation.
l L.P. NO.
302/304/305-145.11-BS-02 i OBJ. NO.
1.3 OBJECTIVE : List / State the system and major components supplied by the Bleed Steam System.
Question: Column A contains the components supplied by (1.0 pts) the bleed steam system.
On the line at the
left of each component, write the letter of the component in Column B that is the source of steam.
Each component in Column B may be used once, more than once or not at all.
Column A Column B 1.
16(26) Feedwater Heaters A.
The low pressure turbines 2.
15(25) Feedwater Heater B.
The high pressure- . turbines , 3.
14(24) Feedwater Heaters C.
The Main Steam System Y 4.
13(23) Feedwater Heaters .c h ~$ 5.
12(27[FeedwaterHeaters.[ .
g - - _ _ _ '.
- ,..
._- 6.
11(21) Feedwater Heaters
Heating Steam System , E 8.
Bleed Steam Coil of the MSR . ANSWER: (0.125 pts each) 1.
B 5.
A
l g 2.
B 6.
A , ' 3.
A 7.
B ' 4.
A 8.
B
- - 3_0 2= SRO-AK-0 -l_l - y-: - _ _ _
. - ., , - SYSTEM
Heater Drain N ~ TASK ID.
039-520 , ' TASK Direct subordinates in aligning the Heater Drain System for normal operation.
i L.P. NO.
302/304/305-145.ll-HD-02 OBJ. NO.
1.3 OBJECTIVE : Recall the Drain Flowpath for each Feedwater Heater and the Feedwater and Moisture Separator f Reheater Drain Tank.
Question: $ . Select the correct answer (s) (.5 pts) l Drains from the 16(26) Feedwater Heater are directed to:
a.
The 15(25) Feedwater Heater.
b.
The Feedwater Heater and Moisture Separator Reheater Drain Tank.
c.
The Main Condenser.
g .n d.
The 14(24) Feedwater Heater.
.- , , d o lf ANSWER: . . b,c - (.25 pts each.
-- - Subtract.25 pts for each-incorrect choice) ,.C g l/ l , -' o ! ! t I, - ~ - 302-SRO-AK-0-12_ 22:~ -
___ _ _ _. _ _ _ _ _ _.. _ _ _... _ _.
._ _ _ _ _ SYSTEM
Heater Vent , TASK ID.
039-526 , , TASK
Direct subordinates to close all of the shell
vents to condenser bypass valves at 15% power.
j , L.P.
NO.
302/304/305-145.ll-HV-02 j.
OBJ. NO.
2.3 ~ OBJECTIVE : Recall the flowpath or the shell vents.
j, , Question: , Select the correct answer (s).
- - l The shell vent path for the 15(25) feedwater (0.5 pts) i i heater is from the heater to: 'l i a) The Main Condenser l ' b) The 14(24) Feedwater Heater c) The Feedwater Heater and Moisture Separator Re-heater Drain Tank (
- {
d) The 16(26) Feedwater Heater ,
- , ! ! s
l.
l h
ANSWER: ' ! a - The Main Condenser (0.5 pts) } - - .. i % ~ h +:: _ , ~O Y l , . e l C l
,. $. , j __ 302-SRO-AK-0-lL_ _ _
-__ _. _ _. - -. - - - . _ _ -. =. _ -.. - - -. SYSTEM: Miscellaneous Condensate ,
TASK ID.s 113 502 I TASK: Direct subordinates in operating the MC System.
L.P.
NO.: 302/304/305-145.ll-MCOl-00 ! GBJ. NO.: 1.4 'j OBJECTIVE: Describe the purpose of stem sealing and why it is ' used for valves under a negative pressure.
Question: The Miscellaneous Condensate System provides (.25 pts) ! valve stem sealing water.
What is the purpose ! , ' of the valve stem seals? .
! k I $ i i b , i , .- !
. . Answer: Valve steam seal water is provided to eliminate / minimize air leakage into the feed and' condensate system.
for, help i maintain condenser vacuum) (Either for full credit) (0.25 pts) l . i i I 302-SRO,AK 0-14 _ ..
- _____ - c SYSTEM: Reactor Vessel Level Indication System 002 537 TASK ID,: , Operate the Reactor Vessel Level Indicating TASK: System (RVLIS) L.P. NO.: 302/304-145.12-RVL-01 OBJECTIVE: State the purposes of the Reactor Vessel Level Indicating System.
! QUESTION: State the three (3) purposes of the Reactor Vessel Level Indicating System.
(.75 pts.)
! ! .s . - ANSWER: (.25 pt. ea.)
Assist in detecting the presense of a qas bubble or void in a.
the reactor vessel.
b.
Assist in detecting the approach to Inadequate Core Cooling i ' (ICC).
Indicate the formation of a void in the RCS during forced c.
flow conditions.
(Underlined portions for full credit.)
_ _:QO2-RO-0-AK-15 - - - w F s
SYSTEM
Mitigation of Core Damage / Post Accident Cooling TASK ID
TASK
L.P. NO.
305/145.15-POST-00 OBJ. NO.
OBJECTIVE : Describe the effects of non-condensable gases present in the RCS during a small break LOCA on natural circulation flow.
,
Qu2stion: Analysis of a 2 inch SBLOCA shows that 1648 ft' (at standard temperature a.
and pressure) of non-condensable gases are produced in 4050 seconds.
Each model 51 steam generator has a tube bundle volume of 760 ft',100 ft8 of which is contained in the bend space.
The conclusion reached was that natural circulation flow would not be blocked or impeded for this SBLOCA, how is this possible? (0.E pts) ? Answer: ' - y Tha gas volume is significantly lower (50 ft') for the actual plant temperature and pressure.
(0.5 pts) . : e s ! !
- - _ . -
- . - - - - - _ _ SYSTEM: Mitigation of Core Damage / Post Accident Cooling , TASK ID.: l l TASK: - L.P. NO.: 305-145.15-POST-00 l OBJ. NO.: 4.0 i OBJECTIVE: State the hydrogen concentration in air, required for combustibility (including explosions).
}
Question: Fill in the following blanks.
(0.25 pts) ... Hydrogen in various concentrations in air can be either a combustible or explosive hazard.
In air, hydrogen is neither combustible nor explosive below
% and above
%. (0.125 pts
each part) j .' I < - ! [ - ! l . I .'} t
e - . _ N
__ _ -- , , i j ? SYSTEM: Refueling Operation I 1> TASK ID.: 034-514 TASK: Perform Refueling Surveillance Procedures in
- accordance with the Technical Specifications.
l
L.P. NO.: 302/304/305-145.10-RO-01 ! t OBJ. NO.: 32.1 & 3.0 l OBJECTIVE: Perform Refueling Surv. Procedures in accordance ' with Tech. Specs.
4 !
QUESTION: i Define the term " Core Alterations".
(.5 pts.)
- ! l ~ l
-I { Ii ' l-4 . - l ' !. , E, .
0
ANSWER: ' The movement or manipulation of any component within the Reactor p Pressure Vessel with the vessel head removed and fuel in the j i I vessel.
p
(0.1 pts. each underlined portion)'
- , i i f $ I a N ! jl
, I.
' 302-RO-0-AK-18 _ _
- a - , l SYSTEM: Refueling Operation TASK ID.: 034-530 TASK: State the immediate corrective action for a High Flux at Shutdown Alarm.
L.P. NO.: 302/304/305-145.10-RO-01 OBJ. NO.: 30.0 + 8.0 OBJECTIVE: State the immediate corrective action for a High Flux at Shutdown Alarm.
Question: { State the proper response by the Control (1.0 pts) ' Operator to a "High Flux at Shutdown Alarm".
! I L -
! ! Answer: 1.
Verify count rate increase on control console (0.125 for both source range NI's.
each part) 2.
Rapid. borate.
(0.25 pts) 3.
Announce on P.A. System High Flux Alarm (0.125 g and instruct all personnel to evacuate each part) the containment immediately.
4.
Calculate shutdown margin.
(0.25 pts) (Underlined portions for full credit) i s I i % - _ _ _ _ - _ - _ _ _ _ _ }}