IR 05000223/1988004
| ML20155G574 | |
| Person / Time | |
|---|---|
| Site: | University of Lowell |
| Issue date: | 09/28/1988 |
| From: | Eselgroth P, Denise Wallace NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20155G569 | List: |
| References | |
| 50-223-88-04OL, 50-223-88-4OL, NUDOCS 8810170207 | |
| Download: ML20155G574 (57) | |
Text
{{#Wiki_filter:. _ _. _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . U.S. NUCLEAR REGULATORY CORMISSION REGION I OPERATOR LICENSING EXAMINATION REPORT EXAMINATION REPORT N0: 88-04(0L) FACILI1Y DOCKET NO: 50-223 FACILITY LICENSE NO: R-125 LICENSEE: University of Lowell FACILITY: University of Lowell Reactor EXAMINATION DATES: August 3-5, 1988 i CHIEF EXAMINER: <d [V! [ 9 -/ S-S S David wad ace Date Operations Engineer (Examiner) . APPROVED BY: A d4 j y/-// P r D selgrothT CF ef Date ~ W Section, Operation Branch, DRS ./ SUMMARY: Written and operating examinations were administered to one Senior Reactor Operator (SRO) and two Reactor Operator (RO) candidates. All candidates passed the operating exan.inations.
The SRO and one R0 passed the , written examination, however, one RO failed Section G of the written ' examination.
! 8810170207 880930 PDR ADOCK 05000223 V PNU OFFICIAL RECORD COPY OL EXAM LOWELL 88-04 - 0003.0.0 09/27/88 k----- -
----------
- - - - - - - - - - -. - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
- . . ! TYPE OF EXAMINATIONS: Retake
EX's.INATIONS RESULTS: l RO l SRO l l FASS/ FAIL l PASS / FAIL l l l I l WRITTEN l 1/1 l 1/0 l l l l l l OPERXTING l 2/0 l 1/0 l l l-~ l I l OVERALL l 1/1 l 1/0 l , I l l l l 1.
Chief Examiner At Site: Divid Wallace 2.
Personnel Present at Exit Meeting: US NUCLEAR REGULATORY COMMISSION David Wallace UNIVERSITY OF LOWELL Tom Wallace 3.
Summary of Exit Meeting comments and conclusions based on written and i operating examination results: The candidates did not exhibit adequate knowledge of the ULR administrative radiation exposure limit.
The RO candidates were reluctant to use procedures, especially during emergency scenarios. Although no candidate failed the operating test because of this reluctance, the operator canoidates' use of emergency , i procedures was characterized by the Examiner as being one of using the i procedures only as a last resort.
None of the operator candidates had an adequate knowledge of the use of Safety Tags for control of maintenance and other work.
This weakness can be attributed to the absence of formal controls over safety tagging of equipment.
Attachments: 1.
R0 Written Examination and Answer Key 2.
SR0 Written Examination and Answer Key 3.
Facility Comments and NRC Resolution for RO and SRO Written Examinations
- . . U.S. NUCLEAR REGULATORY COMMISSION REGION I OPERATOR LICENSING EXAMINATION REPORT EXAMINATION REPORT NO: 88-04(OL) FACILITY DOCKET NO: 50-223 FACILITY LICENSE NO: R-125 8.ICENSEE: University of Lowell FACILITY: University of Lowell Reactor
EXAMINATION DATES: August 3-5, 1988 ' CHIEF EXAMINER: / /IM 9.29'60 cu Da v id Wa l l a'c'e Date j Operations Engineer (Examiner) i I APPROVED BY: M J I'A747 P 'er W. Ese groth, Chief Date - W Section, Operation Branch, DRS ' SUMMARY: Written and operating examinations were administered to one Senier Reactor Operator (SRO) and two Reactor Operator (RO) candidates. All candidates passed the operating examinations.
The SRO and one RO passed the written examination, however, one RO failed Section G of the written examination.
J , ) ' i .,
?
t ' . . . .
_- _ . . . _. _ _. _ -- ._.
_.
- . . TYPE OF EXAMINATIONS: Retake EXAMINATIONS RESULTS: l R0 l SRO l l l PASS / FAIL l PASS / FAIL l l l l T ' WRITTEN
171 l 1/0 l l l
l l MDEATINO l 2/0 l 1/0 l l l l l l OVERfCL l 1/1 l 1/0 l l .l I l ,
1.
Chief Examiner At Site: David Wallace ' , i 2.
Personnel Present at Exit Meeting: ' ' US NUCLEAR REGULATORY COMMISSION j David Willace UNIVERSITY OF LOWELL Tom Wallace , 3.
Summary of Eat Meeting comments and conclusions based on written and ' i operating examinction results: The candidates did not exhibit adequate knowledge of the ULR '
) administrative radiation exposure limit.
'
l The R0 candidates were reluctant to use procedures, especially durin0 I j emergency scenarios. Although no candidate failed the operating test i because of this reluctance, the operator candidates' use of emergency procedures was ;haracteri:ed by the Examiner as being one of using the procedures only as a last resort.
. None of the operator candidates had an adequate knowledge of the use of Safety Tags for control of maintenance and other work.
This weakness can be attributed to the absence of formal controls over safety tagging of equipment.
Attachments: 1.
R0 Written Examination and Answer Key 2.
SRO Written Examination and Answer Key 3.
Facility Comments and NRC Resolution for R0 and SRO Written Examinations
..
U.
5.
NUCLEAR REGULATORY COMMISSION
SENIOR REACTOR OPERATOR LICENSE EXAMINATION FACILITY: UNIVERSI TY OF LOWE L _--------_--___--__------ REACTOR TYPE: TEST ____--__---------_-----_.
DATE ADMINSTERED: 88/08/03 s} Fs-Q,n g r
_-____-_--------__-
iLil v ExAMINen, ROESENcR, s.
sV
_-----------_------_
CANDIDATE
__-------------------
INSTRUC.f!ONS TO CANDIDATE: --_--_-_---_-_-----_-_--_.
Use separate paper for the answers.
Write answers on one stde only.
Staple question sheet on tcp of the answer sheets.
Fotnts for each question are indicated in parentheses after the question.
The p.i s s i n q grade requtres at least 70% in each c a t e g'o r y. E x ami n at i on papers.v i l l - 3e picked up S1-x (6) hours after the examinatton starts.
- /. O F CATEGORt
% OF CANDIDATE'S CATE3 CRY VALUE TOTAL SCORE VALUE CATEGORY
-----_
-.--_-----_ --__---- -__-_-_-_--_ ---_---___---__----_-- 19.00 19.00 H.
REACTOR THECRY ---_---- -___-- _----__--__ .-_---__ 10.50 19.50 1.
RADICACTIVE MATERIALS HANCLIN3 --_----- _-----
_.
-_ ---__ DISPOSAL AND HAUHOS 22.50 22.50 J.
SPECIFIC OPERATING -- ---__ ---_--
__----
- _ - - -... CHARACTERISTICS 20.00 20.00 K.
FUEL HANDLING AND CCRE _------- ------ ---_-------
PARAMETERS 20.00 20.00 L.
ADMINISTRATIVE PROCEDURES.
__------ - -... - - ...--_-___- _.. _-- 100.0 % Totals _-----__ -__-__--__-
Final Grace , l All work done on thi s ex aminati on is my own.
I have neither given nor receivuc aid.
.k[ f ' [,, O . s l ' u,- J l L i l, v,vi
__---__--_-____---____-----___
Candicate s Signature >
_. - - _ - - - _ _- . . -. - - - -- ._ . _ - _ -. - - ._ ^ l ~~ \\ . l ! (, NRC RULES AND GU!DELINES FOR LICENSE EXAMINATIONS l During the administration of this examination the following rules appiv 1.
Cheating on the examination means an automatic denial of your application and could result in more severe penaltieo.
l 2.
Restroom trips are to be limited and only one candidate at a time may leave.
You must avoid all contacts with anyone outside the examination l room to avoid even the appearance or possibility of cheating.
i 3.
Use black ink or dark pencil only to facilitate legible reproductions.
I
Print your name in the blank provided on the cover sheet of the , examination.
> >
5.
Fill in the date on the cover sheet of the examination (it necessary).
{ o.
Use only the paper provided for answers, i 7.
Print your name in the upper right-hand corner of the first page of each i section of the answer sheet.
i . q 0.
Con secut i vel y number each answer sheet, write "End of Category __" as j appropetate, start each category on a new page, write only on one side
] of the paper, and write "Last Page" on the last answer sneet.
9.
Number each answer as to categcry and number, for example, 1.4, 6.3.
l t 10. Skip at least three lines between each answer.
! ! 11. Separate answer sheets from pad and place finished answer sheets face j ,
down on your desk or table.
' ! I l 12. Use abbreviations only if they are commonly used in facility literature.
l
13. The point value for each question is indicated in pt sntheses after the , d question and can be used as a guide for the depth of answer requirec.
l I { ]
Show all calculations, methods, or assumptions used to'obtain an answer l
- j to mathematical problems whether indicated in the ouestien er not, j
i . i 15. Partial credit may be given.
Therefore, ANSWER ALL PARTS OF THE l I QUESTION AND DO NOT LEAVE ANY ANSWER BLANA.
i i 16.
If parts of the examination are not clear as to intent, ask questions of
i the examiner only.
l 17. You must sign the st4tement on the cover sheet that indicates that the ' work is your own and you have not received or been given asststance in completing the examination.
This must be done after the examination has l been completed.
) ! i i
l . I - - - . - - . - - - - - -
. -.. - _ _ .. 18. When you complete your examination, you shall: a.
Assemble your examination as follows: (1) Exam questicns on top.
figures, tables, etc.
(2) Exam aids - (3) Answer pages including figures which are part of the answer.
l b.
Turn in your copy of the examination and all pages used to answer the examination questions, c.
Turn in all scrap paper and the balance of the paper that you did ' not use for answering the questions.
d.
Leave the examination area, as defined by the examiner.
If after leaving, you are found in this area while the examination is still in progress, your license may be denied or revoked.
[ . , c i l l . - -. - --_-- - -.
.. H.
REACTOR THEORY Pcgo
, QUESTION H.01 (3.00) a.
State the two reactions that produce neutrons in the installed neutron source.
Either a word explanation or an equation is acceptable.
(2.00) b.
If the installed source was removed, what TWO phenomena would be responsible for the continued production of neutrons in the core? (1.Qu) OUESTION H.02 (1.00) TRUE or FALSE 7 4.
As Keff approaches unity, a larger change in neutron populatten results from a given change in Keff.
, b.
As heff poproaches unity, a shcrter period of time is required to coach tt ?quilibrium neutron level fcr a given change in Koff.
QUESTION H.03 (1.50) What would the startup counter indicate with the control blades at 12 inches and the regulating rod at 10 inches? Assume that with all rods in the counter reads 30 counts per second and that the reactor tu shutdowr. by 9*4 Delta K/K.
Show all work.
CUESTION H.04 (1.00) Define the effective delayed neutron fraction.
. (***** CATEGORY H CONTINUED ON NEXT PAGE
- e)
_
_ _ .- .. H.
REACTOR THEORY Page
'
, QUESTION H.05 (1.90) If the reactor was operating at 1 MW when one of the control blades was droppec, the power would immediately drop to sbout 200 kW and then decay slowly to a final steady state value of a few hundred counts per second.
(Notes in answering the questions below, calculations are neither required nor desired.)
a.
The loss of what component of the neutron flux causes the sharp drop in power? b.
What determines the rate of power decrease at about five minutes after the rod is dropped? c.
Wny does the power stabilize after approximately one hour when Keff is less than 1.O? . CLESTION H 06 (0.50) Why is graphite a better reflectcr than water? CUESTION H.07 (1.00) The secondary side of the heat exchanger is designed to supply wa?.er at 80 F and "eturn it at 91.4 F with a flow rate of 1500 gpm.
Basec on these values, calculate the heat removal capacity of the heat eachanger in MW.
State all assumptions.
Show all work.
Assume 8 lbm/ gal.
(***** CATEGORY H CONTINUED ON NEXT PAGE
- )
- - - . - - -- -.
l .. I H.
REACTOR THEORY Pego
, . l QUESTION H.08 (1.00) Multiple Choice , The axial position in the core 6.here the peak clad temperature occurs fo" the forced convection mode is (SELECT best answer): a.
in the center of the core Where the highest heat flux occurs.
b.
independent of the flow rate through the core.
c.
independent of the specific heat of the fluid and the heat transfer coefficient.
d.
displaced slightly away from the core center in the direction of the flow.
t i
. CLCSTION r4. 09 (1.00) l Why is the differential worth of a control blade greater in the center of the blade's travel than at the beginning or end of its travel? o CUESTION H.10 (3.00) , The reactor is just critical (Keff=1) at an initial powe" of 1 kW steady state in preparation for rod worth caltbiations.
The regulating rod is then withdrawn a measured amount to place the reactor on a s positive period.
The doubling time from 1 kW to 2 kW ts 20 seconds and
, the douDling time from 2 kW to 4 kW is 35 seconds.
l I a.
Why is the first doubling time shorter than the second douDling ) time? .. b.
What 15 the reactor peri"d during the second doubling time? Show all work.
! c.
Why are the rod worth calibrations done in the watt or low ] kW range instead of the MW range? i i i i I i ' (***** CAiCGCRY H CCNTINUED CN NEXT PAGE eeses) .. .- -_ _ -. .- - _,., - _ _ - _ _ _
__ _ __ - . . I H.
REACTOR THECHY Pego S __________________ , , QUESTION H.11 (2.50) a.
What are the TWO processes that produce xenon during reactor operation? (1.00) , t b.
What are the TWO processes that remove xeron during reactor operation? (1.00i , after a weekend shutdown, the reactor is cperated for c.
On Monday, one hour at 1 MW and then shutdown.
How long af ter the Monday shutdown will peak xenon occur (+/- A hour)" (0.50) > t l CUELTION H.12 (2.00) Assuming and undermoderated core, what is the effect (INCREASE or DECREASE) of an increase in temperature ons , , ' a.
L (Fast non-leakage procaD111ty).
' f . m.
f (Thermal utili:ation factor).
t c.
p (Resonance escape probability).
Q.
keff.
! ) [ ' . t i ' i
I l l l
I . .l (***** END CF CATEGORY H $94**) .i ! ! . -. _ _ _. _ _. - -. - __ _~ - -.
.. . . .. -.. . 1.
RADIOACTIVE MATERIALS HANDLING DISPOSAL Pcge
--. -
,
I GUESTION !.01 (0.50) Why is the core end of a typical beamport plugged with a nitrogen filled canister? i OVESTION I 02 (0.50) What is indicated by the presence of Na-24 in the daily secondary sample? ' QUESTION I.03 (0.00) Wnat is the greatest source of gamma r a'd i a t i on in the primary :cciant
during operation? . CUESTICN I.04 (1.00) Mul tiple Choice I What is the typical contact rate of exposure of spent cleanup s/ stem ! resins?
I a.
Less than 1 mR/hr.
, b.
10 to 20 mR/hr.
,
, ! < 300 to 500 mR/hr.
J c.
" c.
Greater than 1 R/hr.
i i ! ' l , CUESTION !.uS (1.50) Answer the following questions for DOTH of the stack effluent menitors.
a.
What type of detector ts used? CO.50 each]
i D.
What is the high level trip setpoint? C0.25 eachl ' , . , I l l ! l
' (eeeen CATEGORY ! CONTINUED ON NEXT PAGE eeeoe) ! l.
. _. _, _.. . _. _. .. - - .. - I.
RAD 10 ACTIVE MATERIALS HANDLING DISPOSAL PcQo
______ __ __ ____________________________ , ___________ i QUESTION I.06 (1.50) State the location of the THREE meter readouts for the third floor constant air monitor.
QUESTION I.07 (1.00) ,
Multiple Choice '
l How song would it take the 3rd floor CAM to reach the high alarm set ! point if the airborne concentration of fission products in the contatnment was to jump immediately to 10 times MPC due to a fuel j element failure? ,
a.
I second.
c.
10 seccnds.
c.
1 minute.
d.
10 minutes.
CUESTION I.08 (2.50) i A 20 year old maintenance worker has accumulated a lifetime expcsuco
through last quarter of 40 REM as recorded on the worker's NRC Form 43 additionally, he has accumulated 1.0 REM so far this cuarter.
a.
Assuming the worker must perform maintenance inside the ULH containment in a radiation field of 650 MREM /hr gamma and _______ 20 mead /hr thermal and fast neutron, how long can the worker wces in ___.___
the area before exceeding a 10CFR20 dose limit? Consider all ! pertinent limits.
Show all work and state all assumptions, i ! b.
During a oeclared emergency, this individual volunteers to enter ' a high radiation area and perform work necessary to prevent further
affluent release.
In accordance with the Emergency Plan, nnat { is the maximum allowea whole body exposure? ' , ! i I
(***** CATEGCRV I CONTINUED ON NCXT PA3E seas *) '
1 - -
_.
.._ _ . ._ .. I 1.
RAD 10 ACTIVE MATERIALS HANDLING DISPOSAL Pago
l
--
, .-.-------- , . GUESTION l.09 (0.50) t t i An irradiation sample is to be removed from the pneumatic syst0m.
At what potential contact reading (MREM /hr) is Health Physics coverage required? ! , QUESTION 1.10 (0.50) What is the primary contributor to the dose rate at the pool surtace after a loss-of-flow scram? ! I CUESTION 1.11 (3.00) ! , a.
In accordance with Standing Order #o, "Sample Handling Procedures,' what are the THREE features of an acceptable "minimally sh i el d c'd container?" b.
Whet THICKNESS of shielding would be required to reduce an activated ! sample to below the limits required for transfer frem the facility l [ assuming that its unshielded radiation level was C5 MREM /hr at one foot? The shield material to be used has a tenth thickness of two j inches.
Show all work.
, , CUESTION !.17 (2.50) j i 4.
In accordance with 10CFROO, in addition to a Icck, what are tne TWC , alternative ways of controlling access to a permanent hign red'ation area 7 (2.00) { b.
In accordance with 10CFR20, in addition to the controls for a permanent high radiation area, how may access be controlled fcr a high radiation area that is to be established for a period of 30 days or less? (0.50) j , QUEST!ON 1.13 (1.50) l In accordance with the procedure entitlec, "Laboratory Ac c i d en t s what THREE actions would you take to "Confine tne ha: arc, ' ti you were to spill a dry arradiated kample7 (esese CATEGCRY I CONTINUED ON NEXT PAGE e*eoe) I
_ -. - .. f.
RACICACTIVE MATERIALS HANDLING DISPOSAL P4go
____.. __ _ ..______...o____________.... , ___.____... QUESTION !.14 (1.00) In accordance with Standing Order #8, "Installation or Removal of Flux Warus or Foils": a.
What special dosimetry is requirec in acdition to a TLD and a pocket dosimoter? I t I b.
When (at a mantmum) should the pcckte dosimeter be read ? i
1 ' CUESTION !.15 (0.50) - r In accordance with E.O.1, "Radiation Emergency," what CNE action shcule , you always take before exiting the containment if you are the on cuty SRO and you are in the plant when the e'vacuatton alarms sounds'
l
) ! i
, l l
I, ' l i l l l ,
! l l
o I ! ' t ) ! ' i i (**8** END OF CATECORY ! aeS4e) t '
> _ ._ _ _ _._ ___ _ _ . _ _.. _ _. - _ _., ,_ _. _. _. _ _. _, _ _. -. _ _ _
.- , _.
. _- -. , .. J.
SPECIFIC OPERATING CHARACTERISTICS Pago 10 . I J ! l QUESTICN J.O! (1.00) l If the reactor is operating at 1 MW when the SECONDARY pump trips, wnat { automatic scram will shutdown the reactor? Assume no operator action, j
, QUESTICN J.02 (1.50)
j Following a normal reactor startup at the beginning of the cay, with the
reactor crittcal at.01 watt, what behavtor/trenc woutc you e;t p e c t to
observe on the following instruments?
a.
Rod position incicaticns, i b.
Period meter, c.
Starutup channel count rate.
. f CUESTION J.03 (1.00) During a normal startup the reactor is taken to.5 MW on a thirty-five
' second period.
When the power level reading of the controlling ptccammeter matches the reading on the Power Schecule Meter the Auto switch is placed in auto.
Sketch the trace that would be created cn tne power level indicator in response to this transtent from the point of
placirs the red control system in auto to the point of steady reacter j l powe".
!
GUEST: CN J.04 (1.50) What infomation does the console operator need in order to Calculate the actual wceth of an emperimental sample which is anserted int, tne , reactor via the pneumatic system? ! , i t I i i t I ! ! I (4stoe CATEGORY J CONTINUED ON NEXT PAGE seese)
_ - l ' . j J.
SPECIFIC CPERATING CHARACTERISTICS Pega 11 ( ..............................-....... , , I QUESTION J.05 (3.00) On Monday morning, a normal start-up is performed such that by 0900 tne reactor is at 1 MW.
What change (INCREASE, DECREASE, or NO CHANGE) would you expect to see in the following paramoters aetween 0900 a and 1400 if the reactor is operated at a constant power of 1 MW with , normal console operator control? e a.
Control blade hetqht.
l b.
Primary flow, l j c.
Secondary flow.
I t d.
Pool temperature.
- OUCSTION J.0c (1.00)
i ! Fol l o.w i n g a normal shutdcnn after eight hours cf full p c e.e r coceattcn.
i what would be the abnormal indication of a compensated icn cnatae" that
was overcompensated" ' QuCSTION J.07 (3.00) j State FOUR of the FIVE control blace roc withdrawal interlocks * Inciace " the associated setpoints in your answer.
, '
" CLESTION J.00 (1.00) . ! ' i With the "MASTER SWITCH" in the "test" position and the regulatirQ Cl# e "CUT" light energized, what is the position of the r eg ul a t i ng o'. ac e?
, !
CUESTICN J.09 (1.00) t I j What is the relationship between the primary flow and the output of the primary flow transmitter' , I ! I I I
(*esee CATEGORY J CCNTINUED CN NEAT PAGE seees) z ) ,
. - _ , . - J.
SPECIFIC OPERATING CHARACTERISTICS Pego 12 ........_______.... ______..._________ , l
QUESTION J.10 (3.09) l 4.
State FIVE of the SEVEN scrams that are disabled by placing the range switch (755) in the "O.10 MW" position.
Setpoint e are i NOT desired or required.
(2.50) b.
What CNE scram is enabled by placing the range switch ( 71ib a in the "0.1 MW" position? (0.30) j !
. j i QUESTION J.11 (3.00) i 4.
In what position (OPEN, SHUT, or AS IS) do the f ollowing valves fail on a loss of air? 1.
Sanitary system vent isolation val,ve (G).
' 2.
Emergency exhaust isolatton v a l*v e (D).
j b.
In what position (CPEN, SHUT, or AS IS) ao the follontng valses +cti j en a loss of power? 1.
Ventilation supply bypass valve (F).
) 2.
Emergency exhaust isolation valve (D).
] J CUESTION J.12 (1.50) . Wnat is the series of events that takes place to cause a loss o+ p o r.e r I to the control blade magnets when the P-4 valve is openec with the cCre located in the stall? . d
CLESTICN J.13 (1.00) ! What ancication would the console operator have in tne control roem snat
the truck door seal had failed assuming that the associatea scram was
inoperable?
1
i l l
, (sesee END OF CATEGORY J $se8 ) i < ! '
l - .
. .. K.
FUEL HANDLING AND CORE PARAMETERS Pogo 13 _____________________________________ , I QUESTION K.01 (2.00) " Match the reactivity worth effect listed in Column B with the action that in Column A.
Each action listed in Column A has only one correct
response from Column B.
Column B responses may be used more than once.
i Column A Column G __________________.,_____________ ___________-__ a.
Adding one fuel element to core.
1.
-6.0 DeltaK/L b.
Flooding of one beam port.
2.
-3.4 DeltaX/K c.
Removal cf one graphite element.
3.
-0.2 DeltaK/K l i c.
Replacing center fuel element
+0.06 DeltaK/K with water.
' S.
+2.0 CeltaN/h i i GUESTION K.02 (3.00) In accordance with Technical Specifications, state THREE of the FCUR conditions that must be sattsfied for the reactor to ce constdered secured.
Assume a normal core loading and configuration.
) l GUESTIO*4 K.03 (0.50) Acccrding to Tcchnical Specifications, what is the ma<iaum 411caante worth of a single mov4Lle experiment? l QUC5T!ON K.G4 (0.50) Using the attached Figure 0-1, show wnere the following cceponents are locatedt a.
Proportional counter.
(0.50) b.
Startup ' source.
(0.50) c.
Regulating rod.
(0.50) d.
Fuel elements.
(1.00) i (eease CATEGORY K CONTINUED CN NEAT PAGE seees) l .
._.
. _.
. - _ _ _ ,4 .
' K.
FUEL HANDLING AND CORE PARAMETERS Pego 14 I ............................-........ i . t , QUESTION K.05 (2.00) d l Assume a core configuration is designated C-5-3.
According to Standing ! i
Order #3, "Core Loading Identification," which of the C-5-3 designation characters change ift ' ] )
two fuel elements are exchanged? i ! b.
the fuel configuration is enanced? I I
c.
a 9 e v. graphite element is added in place of a ractation basket? ! , d.
a fuel element is replaced with a new element? ' , i a QUCSTION K.06 (2.00) j i ] In accordance with Standing Ceder #12: !
! 4.
If a new fuel element is added in place of an old element, at what i j value of change in excess reactivity will tt be necessary to i perform a control blade worth caltbeation? (0.50)
, D.
What information is needed in order to calculste the excess reactivity for an altered core leading? t1.00)
c.
What as the mamimum number of replacements of old fuel with nou fuel
j allowed before a control blade worth calculation is recaired (0.50) j regardless of the change in excess reactivity? I ' ,
! i OUESTION K.07 (1.50) <
1 j In accoraance with R.O.1, "Critical Empertment," what THREC perscnnel ] are regatred to be present curing a crittcal experiment' ) i QUESTICN N.00 (2.00) , In accordance with R.O.1, "Critical Emperiment," what are the TWO acceptable methods for graphite element placement during initial ' loading? a
. j .
] (tost * CATEGORY K CONTINUED CN NEXT PAGE
- e)
l l d ) ! . . -
. . ... K.
FUEL HANCLING AND CORE PARAMETERS Pcgo 15 , ..................................... , r , a QUESTION K.09 (1.00) a.
In accordance with R.O.ll, "Handling of Irradiated Fuel," how many < ] irradiated fuel elements may be out of the core or storage at the same time? I b.
In accordance with R.O.10 "Receipt and Storage of New Fuel
Elements," what is the maximum number of new fuel elements that may be out of a mechanically controlled geometry at any ene time? " i !
} QUEST!CN N.lO (1.00) i A sample north 1.57. DeltaK/K is to be removed from a fixed experiment in ! j the core.
The Reactor Operator proposes to remove the sample curing a
reactor start-up while t.se reactor is still shutdcwn by 2%. He cites
R.O.4, "Adding or Removal of S a mp l e s f e,om t h e Cor e " which statast i i
"Any sample having or execcted to have a worth of + / - 0. l'. D el t n A / r.
! ce greater will only be added to or removed fecm the care if the reactor remains subcritical after the insertion or remesat.* l' ) The RO points out that the reactor will remain suberittcal by 0. 5 . ] DeltaK/K and anks for your permission to perform the sample removal.
! ' Should you allow it? Explain your answer.
, ,
i
i l CUESTICN K.ll (1.00)
- What TWO solid decay products. ire most likely to ce seen quicaly by the ed floor CAM tf a fuel cladding failure occurs? l l ^
} ' i GUESTION K.12 (1.50)
' a.
Assuming the ULR water reflected core has a critical mass of 0.3 Aa, now many fully loacea fuel elements would be requireo to reach i criticality with no graphite reflecters? State all assumptions.
Show all work.
(1.00) > b.
How many fully loaced elenents are required for criticality in a j graphite reflected core at the ULR? (0.50) i
) (stess END CF CATEGORY K tssse) I
.
__ .. _ _ ._. . .. ) i L.
ADMINISTRATIVE PROCEDURES, CONDITIONS Page 16
--- ggg-7q793773 g---------------------- . _______.,_______ i QUESTION L.01 (1.50) ! j In accordance with Technical Specifications: a.
When is an operator or senior oporator required to ce present at j the controls? i . ( b.
How many persons are requtred to De present whenever the reactor is i in operation?
I c.
Within what physical bounds ~st the Senior Reactor Operatcr be when the reactor is in operation?
i CUESTION L.00 (0.00)
,
Match the required approving Dody listed in Column S oith tne a perfcrmance request an Column A.
Each request listed tn Cclumn 4 nas l
cnly oae correct response +rcm Column D.
Column B respcnset may oc l ] usec more than once.
l l i Cslumn A Column B l I 4.
Request to perform a 1.
The USNRC.
l . , ) procedure with a temporary
change judged not to change 2.
The Reactor Safety I I the original intent.
Subcctmittee.
I b.
Request to perform a 3.
Tne Reacter Super visce.
l rout.no experiment.
Tne Raciatten Safety J c.
Request to perform a Of4teer.
I
non-routine emperiment l involving.rradiation of 5.
Doth the Roactor Suporvisor l ' l liquio nitrogen.
and the Radiation Sadety ! C44tcer.
d.
Request to perform operations I at less than 500 W with the 6.
The Sentor Reactor Cparatcr.)
, i source removed.
I, 7.
The Consol e Cperator.
. , i l
,i (seeee CATEGORY L CON'.'INUED ON NEXT PA3E * sets)
i ! . - .
- ,
-
..
L.
ADMINISTRATIVE PROCCDURES. CONDITIONS Pago 17
--- g g-{{ 7 gyJgq3---------------------- . > ............... ! l i QUESTION L.03 (2.00) . What are the FOUR interrelated variables associated with the core j thermal and hydraulic performance on which Technical Specific.tten ! Safety Limits fo< the the forced convection mode of operation are based? i , QUESTION L.04 (7.00) - What is the objactive of the Limiting Safety System Settings +or thet ! ' 4.
FORCED convection mode of operation? b.
NATURAL convection mode of operation? I . ! CLCSf!CN L.C5 (1.50) TRUE or FALSE 7 l 4.
NRC approval is required prior to criticality following the recovery , from an actual rod stuck condition? ' b.
The reactor (console) ope *ator is responsible +or the ve*1fication of completeness of all necessary approvals and autnericattens prior l to sample insertion into the reactor? i l c.
In accordance with Stwnding Cecer #4 "Sequence of Operattens During
Start-up and at Rated Pomer." if mere than a CY. discrepancy e s t.. t o ! Detween power indicatien on the two safety trannels the reactcr { shall be shutdown immediately.
i CUESTION L.06 (0.50) , If a setpoint listed in Standing Crcer all. "Setpoints fer Vartogs l Scrams and Alarms." needs to be adjusteo to a value cifferent fecm that l noted in the standing order, whose permi ssion is required? i l ! ! i l I (3:ees CATCGCRY L CCNTINUCD ON NEAT PAGE **see) I i t ! .
. . - - _ _ __ . . _ -.. __ - __. . . _. .. .,
L.
ADMINISTRATIVE PROCEDURES, CONDITIONS Pogo 10 l
q3--{--{-{{g g----------------------
. ............... ! I ,
. QUESTION L.07 (1.00) l
f Quring operation at 1 MW, the console operator nottces that inlet l J temperature is reading 111 F.
What immediate actio1 must the console
operator take? " , b , l GUEST!ON L.00 (0.50) What is the minimum time that a reactor operator or senior reactor operator must actively perform the functions of an operator during each i j calender quarter an orcer to maintain his/her operating Ilcense in an t
active status? , i . i f
i CUESTION L.09 (0.50)
! , t a.
In accercance witn 10CFR55, uncer wnat condattens 4a ar uniscersec ! j person allowed to operate the reactor controls? ( 1. 5W
> ' b.
In accordance with the ULR "4uthority," paper, who must approve the operation of the reactor controls by an unitcensed indtvidual'<C.50)
, c.
How does the console operator know wnich unitcensed inctvtcuals f have been approved to operate tne controls of the reactor' (U.5J) ! ! J i J J CUESTION L.10 (0.00) ! j In accordance with Technical Specifttations, fo11cwing a reacter scram ) causec by a process variable, what FOUR evaluettons mast be performec ! i beiere resuming operatten? l . QUESTION L.11 (0.50) ! J TRUE or FALEE? I ] The reacter may continue to be operated if the main ventilatton i exhaust backup isolatton valve is mechantcally blocked in the open
posttien previced that the primary isolation valve is <ert4tec c;erae;c j cv a stroke test.
t I letese CATEGORY L CCNTINUED CN NEAT PAGE
- s)
) ' i I ! i- - - - - -.
.. L.
ADMINISTRATIVE PROCEDURES, CONDITIONS Page 19
g-J 77 YiO'S
~~~~~~~~~~~~~~~~~~~~~~ .
. QUESTION L.12 (0.50) In Acco dance with Technical Specifications, what special measurement is . required in order to operate in the forced convection mode if an internal element is replaced by a radiation basket? CUESTION L.13 (3.50) In accordance with Technical Specification 3.4, "Radiation Monitoring Equipments" a.
State the FIVE monitors which must be operable during reactor operation.
(2.50)
b.
State how Icng reactor operation may Continue if one cf the area monitors falls and is not replaced.
(U.50) c.
State the limit on reactor power if a failed a ea radiation monitor is replaced by a temporary mon'.t or.
, l (s**** END OF CATEGORY L
- )
(eeseees*** END OF EXAMINATION
- )
k - - - - - - -
i . H.
REACTOR THEORY Paga 20 , __________________ ANSWER H.01 (3.00) a.
Americium 241 CO.503 decays by alpha emission [0.50]. Beryllium 9 absorbs the alpha CO.503 and decays immediately v.ith the emiss on of a neutron CO.503.
OR 241 237 Alpha C1.00]. i Am ---> Np +
12 Alpha ---> C + neutron C1.00]. (2.00) Be + b.
1.
Gamma,n reactions (photoneutrons).
- 2.
Spontaneous fission.
(1.u0) REFERENCE Introduction to Nuclear Reactor Operations, Burn, Section 5. 2.
l
ANSWER H.02 (1.00)
a.
TRUE o.
FALSE REFERENCE Introduction to Nuclear Reactor Cperations, Burn, Secticn 5.3.
. (esee* CATEGORY H CONTINUED ON NEXT PAGE
- e**e)
k
. H.
REACTOR THEORY Page 21 , __________________ ANSWER H.03 (1.50) Moving control blades from 0 to 12 inches adds 4.5% Delta K/K (+/-0.1).
[O.25] Moving the reg red from 0 to 10 inches adds.09% Delta K/K (+/- .0025).
[0.25] Equation of interest ts CR (1-K ) = CR (1-K ).
1
2 and p = (1-K)/K or K 1/(1-p) where p = rho (reacti vi t y). = Therefore K 1/(1 +.09) =.917 (+/- .001) [0.2S] =
1/(1-( .09 +.045 +.0009)) K = .958 (+/- .002) [0.25] =
. and CR 30 (1 -.917)/(1 -.950) 59 counts per second ( + / -- J ). [ 0. 5 0.' = =
REFERENCE Introduction to Nuclear Reactor Operations, Burn, Section 5.3.
Rod worth curves for core configuration C-7-3.
ANSWER H.04 (1.00) The ratio of delayed to total core neutrons [0.50] once tner have slowed down to thermal energies [0.50]. REFERENCE Introduction to Nuclear Reactor Operations, Burn, Section 3.2.4.
(***** CATEGORY H CONTINUED ON NEXT PAGE
- )
\\ ' k
. . . . _.... . __ ,. H.
REACTOR THEORY Pege 22 __________________ , . ANSWER H.05 (1.50) a.
The prompt component.
b.
After five minutes the power decrease is controlled by the decay of longest lived delayed neutron precursor (Br-87).
c.
Subcritical multiplication (of core source neutrons) causes the power to stabilize.
REFERENCE Introduction to Nuclear Reactor Operations, Burn, Section 4.6, 4.0 L 5.3.
ANSWER H.06 (0.50)
Because graphite has a significantly lower neutrcn absception crons section.
REFERENCE Introduction to Nucleat* Reactor Operations, Burn, Section 2.8.10.
ANSWER H.07 (1.00) From the equations sheett . . O=mC (Temp Temp ) - p out in
(1500 gal / min)(1 BTU /lbm/F)(91.4 F 80 F)(8 lbm/ gal) 136,000 DTU/ min = - (136,800 BTU / min)(.OOOO1750 MW/ BTU / min) 2.40 MW = (0.50 for the proper equation, 0.25 for the proper value of C and 0.25 , for the correct result).
p (s**** CATEGORY H CONTINUED ON NEXT PAGE
- 44)
J - - -
_ _ _ _ _ _ _ _. _ . -. - . . . .. H.
REACTOR THEORY Page 23 __________________ , . REFERENCE USAR, section 4.2.2.2.
Thermal-hydraulic Principles and Applications to the Pressurized Water Reactor, Chapter 5.
ANSWER H.08 (1.00) d REFERENCE USAR, section 9.1.1.4 . ANSWER H.09 (1.00) Decause the end of the control blade CO.50] i s moving through a reg:cn of higher flux [0.00] in the middle of its travel.
REFERENCE Introduction to Nuclear Reactor Operations, Burn, Section 7.2 and 7.5.
l . (see** CATEGORY H CONTINUED CN NEXT PAGE
- )
i
, . - . H.
REACTOR THEORY Page 24
, ANSWER H.10 (3.00) a.
Because the transient effects of prompt neutrons are present only in the first seconds following the reactiviti,' addition.
35 sec / Ln(4 kW/2 kW) = 50.5 +/ .S seconds.
b.
T = t / Ln(n /n ) =
O OR, from an understanding of doubling time, t/Ln(2) = 35 sec /.693 = 50.5 +/. S seconds.
T = [0.75 for correct equation.
0.25 for correct result.] c.
To avoid heating of the primary coolant.
OR . To avoid the reactivity effects of the moderator temper &ture coefficient.
REFERENCE Introduction to Nuclear Reactor Operations, Burn, Section 4.3, 4.4.1, 4.8, 4.11.8 and 7.2.
ANSWER H.11 (2.50) a.
1.
Fiasion.
2.
Iodine decay.
(1.00) b.
1.
Radioactive decay.
2.
Burnup.
(1.00) c.
7 hours (+/- 1 hour) (0.50) l REFERENCE Introduction to Nuclear Reactor Operations, Burn, Section 8.4.1.
l (***** CATEGORY H CONTINUED ON NEXT PAGE
- )
. - - _ - - _ _ _ _ _ _ _ _ _ _ _ . _. _.
. _ .. H.
REACTOR THEORY Page 25 __________________ , ANSWER H.12 (2.00) a.
DECREASE b.
INCREASE c.
DECREASE d.
DECREASE REFERENCE Introduction to Nuclear Reactor Operations, Burn, Section 6.4.1.
. I (***** END OF CATEGORY H
- )
J - . .
_ _ _ _ _ _ _ _ _ _ _ .
- ... .. . . .. I.
RADIOACTIVE MATERIALS HANDLING DISPOSAL Pago 26 _ __ , _ ____________________________ ___________ , . ANSWER I.01 (0.50) To reduce the production of Ar-41.
REFERENCE USAR, section 7.3.3.
ANSWER 1.02 (0.50) Loss of heat exchanger integrity.
REFERENCE . USAR, section 7.4.3.
ANSWER 1.03 (0.50) N-16.
REFERENCE USAR, section 8.1.3.
ANSWER I.04 (1.00) a.
REFERENCE USAR, section 8.1.3.
(***** CATEGORY I CONTINUED ON NEXT PAGE
- )
- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _
_ _ _ _. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___ .. - -. .. .. I.
RADIOACTIVE MATERIALS HANDLING DISPOSAL Page 27 ____ _ ___ ____________________________ , ___________ ANSWER I.05 (1.50) 1.
Particulate monitor.
a.
Scintillation detector CO.50]. b.
CAF, approximately 30,000 cpm OR 10 times MPC C0.253, 2.
Gas detector.
a.
G M detector CO.503.
o.
CAF, approximately 15,000 cpm DR 10 times MPC CO.25]. REFERENCE USAR. section 7.4.6(2) and Appendix 10.* ANSWER I.06 (1.50) 1.
At the monitor (Locally).
2.
In the centrol room.
i 3.
In the Health Physics Laboratory.
REF ERENCE USAR, section 7. 4. 6. ( 1 ). d ANSWER I.07 (1.00; , i b.
, i l ) l (***** CATEGORY ! CONTINUED ON NEXT PAGE **** ) j j . . .
. _ _ _ .. I.
RADIOACTIVE MATERIALS HANDLING DISPOSAL Page 20
AND HAZARDS
REFERENCE USAR, section 7.4.6.(1).e.
ANSWER I.00 (2.50) a.
5(N-18) SO REM (0.25) = Total lifetime to date = 49 + 1 = 49 REM (0.25) Total lifetime available = 50 - 49 = 1 REM (0.25) Total this quarter available = 3-1 = 2 RES (0.25) (Lifetime is more restrictive than' quarterly limit) 0.85 REM /hr + (.C3 rad /hr) (10 QF) 1.15 REM /hr cose rate = CO.25 for use of the conservative quality factor, 0.25 for appenpriately considering both gamma and neutron coroe3 (0.50) 1.0 REM /1.15 REM /hr = 0.87 HR = 52 MIN (0.50) b.
25 REM whole body one time exposure.
(0.50) REFERENCE 10CFR20.101(b) E Plan, section 7.5.1.
ANSWER 1.09 (0.50) , 1000 MREM /hr.
REFERENCE R.O.4, step 4.6.
(***** CATECORY ! CONTINUED ON NEXT PAGE
- )
_
. - - . I.
RADIOACTIVE MATERIALS HANDLING DISPOSAL Pega 29 ,
- --- - - ----------------------------
ANSWER I.10 (0.50) Na-24.
REFERENCE USAR, section 0.1.1-2.
ANSWER I.11 (3.00) a.
A metal CO.50], lidded can CO.50], with a handle CO.50]. b.
Must reduce dose to less than 10 MREM /hr at i foot CO.50]. -:< / T ("_ I I 10 (from equation sheet) = O I 10 MREM /hr = I = 25 MREM /hr O TVL = 2 inches Therefore x-2 inches X Log (10/25) 0.80 inch +/- 0.1 inch.
= = CO.75 for proper equation, 0.25.for correct answer based on the candidates assumed level of reduction.] REFERENCE ULR, Standing Order #6, "Sample Handling Procedures".
(***** CATEGORY I CONTINUED ON NdxT PAGE
- )
~ I.
RADIOACTIVE MATERIALS HANDLING DISPOSAL Pago 30 , ______ __ _ ____________________________ ___________ ANSWER I.12 (2.50) a.
Access to the high radiation area may be controlled by: 1.
A device Aowering radiation upon entry CO.50] such that it is less than the high radiation limit [0.50]. 2.
A warning device that upon entry audibly (0.25] or visibly CO.25] alerts the person entering LO.253 and alerts the licensee or a supervisor CO.253.
b.
By direct surveillance (to prevent unauthorized entry), to.50) REFERENCE 10CFR20.203.(c) . ANSWER I.13 (1.50) 1.
Cover the spill with a moist absorbent material.
2.
Call, do NOT go for help.
OR Don't track contamination around the lab while seektng assistance.
3.
Frisk when leaving the scene of the accident.
RCFERENCE ULR, R.O.4, "Adding or Removal of Samples to the Core," step 4.6.
ULR, Radiation Safety Guide, App.
V, Sec.
B.
l l ) ANSWER I.14 (1.00) a.
Ftnger rings.
O.
After each removal or ingertion operation.
(***** CATEGORY I CONTINUED ON NEXT PAGE
- )
.. 1.
RADIOACTIVE MATERIALS HANDLING DISPOSAL Pago 31 ____ _ ______________________ _____ , ________ __ REFERENCE ULR, Standing Order #8, "Installation or Removal of Flux Wires or Foils".
ANSWER 1.15 (0.50) Make a cursory inspection of the reactor building for personnel.
REFERENCE ULR, E.O.1, "Radiation Emergency".
. l l l , .
, (***** END OF CATEGORY ! ets**)
. ... -... . ._ . , . .. J.
SPECIFIC OPERATING CHARACTERISTICS Page 32 ______________________________________ , ANSWER J.01 (1.00) Primary coolant high temperatu: e.
REFERENCE USAR, section 4.C.15.
ANSWER J.02 (1.50) a.
No motion.
b.
Infini ty.
c.
Stable (or SLOWLY increas.ag).
- REFERENCE Introduction to Nuclear Peactor Operations, Burn, Table 4.4 and section S.3.
ANSWER J.03 (1.00) The sketch should show power starting at .5 MW, increacing to some power nbove this level but less than .6 MW CO.303 and then decr9asing back to .5 MW CO.503.
Some slight damped harmonic osci l l ati on about .5 MW is allowed.
REFERENCE ULR, RO-5, "Routine Start-up".
USAR, section 4.4.12.
ANSWER J.04 (1.50) Regulating rod worth curve CO.50] and the rod positions fer the same power level CO.50] before and after the insertion of the sample C0.50]. (***** CATEGORY J CONTINUED ON NEXT PAGE
- )
. -
. . ,. . J.
SPECIFIC OPERATING CHARACTERISTICS Page 33 ______________________________________ , REFERENCE s ULR R.O 4 "Adding o.- Removal of Samples to the Cor e, " step 4.7.
, ANSWER J.05 (3.00) a.
INCREASE b.
NO CHANGE c.
INCREASE d.
INCREASE REFERENCE USAR, section 4
ULR R.O.6, "Operation at Power and Adjustments in Power Level," stop 6.C.
ANSWER J.06 (1.00) The indication will read low off-scalre (and then slowly return *o an . on-scale reading).
OR LcWer than it would normally read.
REFERENCE CAF (***** CATEGORY J CONTINUED ON NEXT PAGE
- )
.-- -
.- . J.
SPECIFIC OPERATING CHARACTERISTICS Pega 34 ______________________________________ , ANSWER J.07 (3.00) Any four of the following: 1.
Low source count rate - 3 cps.
2.
High flux - 110%. 3.
Short Period - 15 seconds.
Low flux - 5%. 5.
Time delay block after "reactor startup" - 10 seconds.
(0.50 for each interlock and 0.25 for each setpoint) REFERENCE USAR, section 4.4.9 and table 4.4 ' R.O.9 "Reactor and Control System Checkout Procedures".
ANSWER J.08 (1.00) The regulating blade is fully withdrawn.
REFERENCE USAR, tables 4.2 L 4.3.
ANSWER J.09 (1.00) The primary flow is proportional to the square root of the transmitter outout.
REFERENCE USAR, table 4.5.
(***** CATEGORY J CONTINUED ON NEXT PAGE
- )
) . .
__ _ _, . _ . J.
SPECIFIC OPERATING CHARACTERISTICS Pega 35 ______________________________________ , ANSWER J.10 (3.00) a.
Any five of the following at 0.50 point each: 1.
Primary low flow.
2.
Reactor core low flow.
3.
Core inlet high temperature.
Core outlet high temperature.
5.
Coolant gates open. (Riser and downcomer).
6.
Coolant gate open. (Riser).
7.
Primary piping alignment established.
. b.
Picoammeter switch set at greater than 100 k W cange.
(0.5v) REFERENCE ULR Technical Specifications, section 3.3.
R.O.9 "Reactor and Control System Checkout Procedures", 9. 2. 2. ( d ). ANSWER J.11 (3.00) a.
1.
SHUT 2.
SHUT b.
1.
OPEN 2.
SHUT REFERENCC USAR, section 3.4.2.2.
(4 t:4 CATEGORY J CONTINUED ON NEXT PAGC esee4)
.. . . . . J.
SPECIFIC OPERATING CHARACTERISTICS Page 36 ______________________________________ , ANSWER J.12 (1.50) Opening the valve activates an attached microswitch CO.503 which in turn opens a relay in the safety scram chain [0.503.
Opening of the relay in the safety scram chain results in the opening of a relay in the control blade magnet circuit CO.503 thus removing power to the magnets.
REFERENCE ULR SP-23, "Scram Function Test Procedure".
USAR, Figure 4.20.
. ANSWER J.13 (1.00) , Containment pressure would be higher t h'a n usual.
REFERENCE USAR, section 3.3.
l .
(es:*e END OF CATEGORY J se ee) J _ ..
. .. K.
FUEL HANDLING AND CORE PARAMETERS Pega 37 _____________________________________ ,
. ANSWER K.01 (2.00) , ' a.
b.
c.
d.
REFERENCE USAR, section 4.5.8.
- ANSWER K.02 (3.00)
Any three of the following at 1.00 point each: 1.
The minimum number of control rods are inserted.
l 2.
The console key is in the off position CO.503 and the key is removed CO.50]. 3.
No work in progress involving are fuel Co.203, core structure . ' Co.203, installed control rods CO.20], or control red drives Co.203 unless the drives are physically decoupled CO.202.
No experiments in or near the reactor are being rooved or servi ed CO.503 that have a reactivity worth exceeding .SP. Deltar/h CC.503.
REFERENCE ULR Technical Specifications 1.10.
ANSWER K.03 (0.50) ' 0.1*/. Delta K/K.
i l i (***** CATEGCRY K CONTINUED ON NEXT PAGE **eo) i
- - - - - -
. _.. ,. , .. K.
FUEL HANDLING AND CORE PARAMETERS Pego 38 _____________________________________ , REFERENCE Technical Specifications 3.1.
ANSWER K.04 (2.50) See attached diagram A-1.
(0.50 points each for correct location in a,b and c.
Fcr d.
0.50 points for the correct number of fuel elements and 0.50 for the correct envelope).
REFERENCE USAR, figure 4.1 . ANSWER k.05 (2.00) a.
The 5 would change.
b.
The C would change.
! c.
The 3 would change.
d.
The 5 would change.
REFERENCE i ULR, Standing Ceder #3, "Core Loading Identification".
ANSWER K.06 (2.00) , l ) . 4.
O.25% DeltaK/K.
(0.50) ' b.
Need critical rod position for the new core leading CO 50] and rod worth curves from the previous core loading CO.50]. c.
3.
(0.50) (eesse CATEGORY K CONTINUED ON NEXT PAGE se**4) _
_.. _. .. M.
FUEL HANDLING AND CORE PARAMETERS Page 39 _____________________________________ , REFERENCC ULR, Standing Order e12.
l ANSWER K.07 (1.50) 1.
The Reactor Supervisor or other competent Senice Reactor Operator appointed by the Reactor Supervisor.
2.
One additional licensed operator.
3.
One other technically qualified scientific person (to act as an independent observer).
REFERENCE
ULR.
R.O.1, "Critical Experiment".
l ' i ' ANSWER K.OO (2.00) 1.
Load the graphite elements into grid positions appropriate to enclose (or ring) CO.SO3 each incremental loadtng of fuel CO.503.
2.
Load the graphite elements into grid posi tions appropriate to enclosa (cr ring) [0.30) the e<pected final core configuratton LO.303.
AE ERENCE ULR, H.O.1, "Critical Experiment," Stop 1.2.14 ANSWER K.09 (1.00) l a.
l b.
i i ' (eeese CATEGORY K CONTINUED ON NEXT PAGC eeee*) , . . .
_. - - _ _ _ _ _ _ _ _ _ _ _ . K.
FUEL HANDLING AND CORE PARAMETERS Pago 40 __________.._____________________.____ , REFERENCE ULR, R.O.11 "Handling of Irradiated Fuel".
ULR, R.O.10, "Receipt and Storage of New Fuel Elemente".
ANSWER K.10 (1.00) No.
Performance of experimental changes o' this magnitude are !!mited (0.503 (by R.O.3) to subcritical conditions of at least the full worth of the most effective control blade ( 3. 52 */. ) Co.50J.
CNo is proper answer but credit is given only fer correct explanation.] REFERENCE ULR, R.O.3, "Changes Which Can Affect Reactivity Other Than Moveman'c of Fuel".
. ANSWER K.11 (1.00)
1.
Rb (88) 2.
Cs (138) REFERENCE USAR, section 7.4.6.(1).c.
AN3WER K.12 (1.50) a.
3.3 kG/.135 kG per element 24.4 eleme.ts, therfore need 2S fully = ' loaded elements.
(0.50 for equation setup, 0.50 for correct answer.)
b.
(0.50) (eeaes CATEGORY K CONTINUED ON NEXT PAGE oseoe> , - - . .. . -. - - - . -
.. K.
FUEL HANDLING AND CORE PARAMETERS Pego 41 a , . HEFERENCE USAR, section 1.2.2.
Start Up Report, section 1.
. I ,
> '
,
(esase END OF CATEGORY >, asee4 i
- - - - - - - -
. . - - _ _ _ _ _ _ - _ . . . .. L.
ADM1WISTRATIVE PROCEDURES, CONDITIONS Pago 42 l _________________________________________
AND LIMITATIONS __.____________ ANSWER L. 0 '. (1.50) a.
Whenever the reactor is not secured, b.
One (SRO).
c.
Within the Pinanski Building (including the reactor c on t a i n tr en t ) OR Within the facility boundary (as defined in the emergency plan).
REFERENCE ULR Technical Specifications 6.1.4 & 5.
ULR Emtegency Plan, section 2.2.
, ANSWER L.02 (?.00) a.
b.
c.
i d.
REFERENCE ULR Technical Specifications 3.6 and 6.G.
ULR, R.O.5, "Routtne Startup," final P.O T E. 10CFR50.$9 l
'
l (e:eae CATEGORY L CONTINUED ON NExT PAGE a:aes>
. .
. .. L.
ADMINISTRATIVE PROCEDURES, CONDITIONS Pcgo 43
g------ 3-g------~~~~-------~~~~- s --- ----------- ANSWER L.03 (2.00) 1.
Reactor thermal power.
2.
Reactor coolant flow rate.
3.
RGactor coolant inlet temperature.
Hei git t of water above the center line of the core.
L REFERENCE Technical Specifications 2.0.
' . ANSWER L.04 (2.00) a.
To ensure that automatic protective action is initiated CC.50] in order to orevent a Safety Limit from being exceedec Co.50]. b.
To ensure that automatic protective action is initiated CO.5CJ in order to prevent undesirable radiation levels CO.25] on the surface of the pool CO.253.
REFERENCE Techntcal Specifications 2.0.
, l l ANSWER L.05 (1.50) 4.
TRUE b.
TRUE j c.
FALSE (eeeea CATEGORY L CONYINUED ON NEXT PAGE eee:e) l
__ -____ _ _____ ~ .. I .. L.
ADMINISTRATIVE PROCEDURES, CONDITIONS Page 44 i ___________________._____________________ ' AND LIMITATIONS __ ____________ - REFERENCE a.
ULR E.O.7, "Stuck Rod or Safety Blade".
' b.
ULR Standing Order #6, "Sample Handling Procedures".
c.
ULR Standing Order #4, "Sequence of Operations During Start-up and . ! at Rated Power".
ANSWER L.06 (0.50) The Reactor Supervisor.
i REFERENCE ULR Standing Order #11, "Setpoints for Various Scrams and Alarms".
, ANSWER L.07 (1.00) The console operator must immediately shutdown the reactor.
REFERENCE ULR Technical Specifications, section 6.5.
I AN3WER L.J8 (O.50) 4 hours.
REFERENCE i 10CFR55.53(e>. l ' '
) l (e448* CATEGORY L CONTINUED ON NEXT PAGE seass) ., ,
i . - - - . ..
_-. - _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ . L.
ADMINISTRATIVE PROCEDURES, CONDITIONS Page 45 ~~~~~~f~~}p"~~}{f~g~~~~~~~~~~~~~~~~~~~~~~ i _______________ b ANSWER L.09 (2.50) a.
When the unlicensed individual is under the direction Co.50] and in the presence of a licensed operator (RO or SRO) Co.50] and the operation is part of the individuals training (to qualify for a license or as a etudent) CO.502.
b.
Reactor Sut, visor.
(0.50) c.
Written approvals are required and are available to the consolo operator.
(0.50) REFERENCE , 10CFR55.13.
' ULR Authority paper, section 7.
. ANSWER L.10 (2.00) An evaluation to determines ~ 1.
if a safety limit was violsted.
2.
the cause of the scram.
3.
the effects of coeration to the scram point.
4 the appropriate action to be taken.
REFERENCE , ULR Technical Specifications 4.6.
l , I ANSWER L.11 (0.50) FALSE !
I (eoeoe CATEGORY L CONTINUED ON NEXT PAGE eese:)
l
. .. L.
ADMINISTRATIVE PROCEDURES, CONDITIONS Pcgo 46 _________.._______________________________
AND LIMITATIONS ! _______________ REFERENCE ULR Technicti specifications 3.5.
ANSWER L.12 (0.50) Flux measurement.
REFERENCE ULR Technical Specifications 5.2.
. ANSNER L.13 (3.50) a.
1.
Gaseous stack monitcr.
2.
Particulate stack monitor.
3.
3rd floor (reactor level) CAM.
4.
Experimental level area radiatior' monitor.
S.
Over pool area radiation monitor.
b.
15 minutes.
c.
Limited to steady state operatien.
REFERENCE ULR Techn';41 Specifications 3.4.
toeeoe END OF CATEGORY L
- e*
) (saseeee*** END OF EXAMINATION eeoeese
- e)
. . -
.. -- F;ya A-/ - , OXXXE X X'X 8^ B Q KN M RM C Q _- [ O
_ ' o X X e , , my - m o X X
X X ' ' r , @ X X X X X X X Go
2
4
6
8
Proportional Countar Startup Source Graphite Reflector Element Fuel Element Servo Control Element O Radiation Basket Compensated IoniL tian Chamber i j Contro' Eleawncs Figure 4.1. Core i-crangement
f
h h O(d
J O O ,- _ -- M __ __ __ __ - -- O O . .
. A l I J ri ga
- .
- r.
.En wi .. +. a., - j.. ..,
- , j,p.; p.a. n...
- .
. .. a -
- s p
- ,, r
..
lc , r, ,. - +- ..r
- .
- ... l?, m p' L J .i ,4 . n -,7. ~}. 9. s g.. , ! , .. . .... - . vn.< rtt - .. - -. -- .- -
- t
.a..j c.
..m , p ..I n u n. m t,,. . lo ', )c, . .i a m- , .J ,; ,,n.h. c ,m , .- .-
- . r
- 'i' lb- .-i - -. . .... , , !.N, ll ld fl 24 N% M Wd f' i' l I I'Ul !ll l% .l' il,l y ' i' ': . c y n,'N . .m.
, I.
lm . , . +m J , > l . 9,.
- - w%
r i - w. o. , n , .... . a: l.. >. . . L, c ., .... , ,Jii, et,o " m. :a.o ae im m
- h e ",
n la.7: .. - . n i .1, .o e , i
3ne *
-.+ n M r .: . . i. + mr ;m 'l' 'f. j T* 't**;**[ ~ 3; ~'I PE[ T7I 'i'~YN.ijk-l M - [~ ~~ ~ } IN.
- j~ 3:
- ! i -.
- . I
. . ng,.,i n, y d.i ej. l- ...wr..n l c c.- l~ q 0.. a m 4- 'b .- '?l : ]i.
in 'H:]U 'O ' b ' -reir . 1 a.
p .;o y:. -. m, - , i + - j$.{' .+ n u . " p-. .. N11-. i!'.. _ , '.!!.d.
+ 3' b W .. .- l - "' ,t ' i If 'i' ' b: h Ib A. .., . ~ . .., .lI . .. . i, 't ?- ,?
,
j I l'.I . 5.
NJ O '! 's.b 'll!M k.
L - .r h b h[N 5i 4.; m!'u.
6N g,[' h' *, ,o h.d - der H.
L., ;#r.n ' ' ' ,(
.. - ' . y'_ d.
h
- n U:
4. > . *
- ~ l l, ] o,! _ s, - r-- , n, .. a
- 7-
.. I; iW F 1T "t. a Y.
y ' . i - o . I , , ..n o.
n . n wn. uo .i.
i, ., , i.
na g . _.,' h qh 4 gL..S, W, qn.M M mpF rm, T m h k
. r,' ' . tb yj' l I.
9' i '). - - - i @!F :P.
al j didi: We :.4
"
M" .? tD@M .'"p1.Ihi' " M~1T 1T~ " D-~ "-l. M %,3tf*' hi *k-i .p e ^ ., '. c, - > , p u-i.. : ;
.e .- - r .: . .,4 -
4- '
- *
1' a-- + D,. .P" 9+ 1' r
. ,r..1 ..a.p - -- t. p.
. '
- - -
t
., y +,- - t- .. ' m,
- .'h-,L,
.. , _.. j i!* bi p.
ip l l , I' L L.. . a,i:
- I60 l:
. i t" . e p . _.
. n m.
m#n m*L1 . .. :- :ni a L Me.r 3 . - n.
a. n _t '.p.y a ., l.
, n,a L i u-
.r r I[:t ,< 2 +.
- . lur a
e .! '1 j ..h 1 > i u- +ay L
tm :_ y.4.
i c e i n .
- h (t,i,. m . ; a' : i.a. ni. - t .a. m
- u
. . L n, a i.: n: e.... ..~. a.
.u i.
m > i.
s .: .#+ e
l.
...!! -. - '. . , t . O.
,: N Pu
fa o@ t -. I a Lb.
l.
1 - i
- 4
% - .. .T-e
. o 2.. - , m"-
- .,
i.
1.. l*; - L: aq.
- q+
b .L.- j., md.m.. .n n .. n.
j j, ,,o
- .r!g u.
I: . a
- - 'a e.
uu
- n. -
. s.
s.
+, ia n ..., .. . + ,
- a
, .. ,, l N .,[,. 1:.,.. +2
- m%d
.-
( p U*:M ): at .p j "- t: . -r-x n . 1.l 1- - i
F t :i ., , l.
- .a. g m H .r.
. In. 4.m p - a.
a .r.; - . , . i; s cp .,i
- ..a v m r o ar
- ., -
. _L ... E . - ..../=,s
- a.il,i.~~l g n..n M m
.. . 1n 1-. r r + .i.
," L:n-zm .e m cG p in i ai - .. .a t, .. =. I ...ns . 4.b.
i p.
p.It s q (t< i t la h,a i e
- n.F..
lr Tit ,.o le $.III~. > 1, .4 - ' - -. - .- .- , ;[. -.c.4-=. f
i . ->=- . f b]'i .N:l 4I*d 'U ' '.. ,. l. d +t h..r '-ih. . 9 ]9 .;I h '; -- b r, -I: - l ' I_g p..r, i . 'o
7 - -
,' i.. M' , ,I , 'h - 4- .I l f.
i >
.- ..l.$.. 3 < e e i ++
-*+t- -e -
- -
. .... m _m p qP, ' n d eo ;n - p .
a
- 4
. I F , ' F' Jh 1,0.,fnblU hp Pi-7 j.T M.@ .I 8 NE
- l. i. h, ' {,
% HJ. m --l.
Ml,E--M.v. r- - a,1 ' ,.p o ?.. ; Q, J,.. n.e n,.p .r ' ' . ' .t 1' P +y n.r.urc-( H pn.. p ' ,e
- I. n.
n ign .... :o ni i nr 91".
c m '. :l -
.d . Q a.
la :H or r m i l . ..l..l.'~~f.i . U ' i., .,..ln p.
aA p, .i .,.g.-.. {.. g p p: i.
.- -9
, , , ,. ' '.._, g.. ,
.. . .p y< . -.l .l .t t p, ! E .i- ., , ,
, p.
p ' o i 2., 6 , . ~ . l l 'I I j
- i b'."
' l'f* : f l.,
f l,b,,, ~L L ' *I'f Ib ',l -. ' . L ' e, . .. .4, .,.. . 4.,' .. ; L P . ;. q.,
- aa y
! .... ,
- .
i.
s,. i.. m :.r ~. z, _ : n u .,.- -ei r. o,
. q-; i-. ' I 50 _ _. - _ .. . . _ -.. . lt.
- . awl.
.. ' ',,.... '...
h X 1'. l .l
- g I
I . I h,I u'.'..l'. - .' g (_' -- ' g, .,.,..9.. y i t i l .- q
, ,. J K !I.' ,.. i .. - - - ...:, th *.L [.
,. j . t o b i(o . .,,. ; 91.', j , i ' i , . ...a q .g s 1.:... n..o. v.,..L!,s m.e,e,.n.,
- > M.u Wp
- _. i, N_.,i ; 1. - qJa ip t ., I- .i., u., .u......, m
.
- -
. ... C i&
ma :eJ b-.e wa m. mb-i.n i.
i:. gr g.
' c u.
- . y tq;c m 3, m ...i. .+. W.s p .,..!. m..,., n+ ~y.,.. g .a.aq..,..m . se op n.. n m , ay..c, . .< m , - it.
- 1 d h
4td yt;.bi Ti .l D:' h1 l II l.
. ~. . t.. .e . ' , ._ . l. 3. i I.,. ' ,l;. 'q ' ' ,, d ', t1 l i! D ' ,, .,. . ..m p,.g.9.1 g..4a.y nyo4 9 3 von h, g,. r, ; . . ...A y 'a q.n e.gp, - . - i q#,1. m...p . .t . o , .H .O +. i i ,vi 2 di p,, nr . a.
_ a.} : i .., e o. @.n4-- m u m .e t.n -,+,. ,. i,. o p , , -+. o.
@. - .,.e n.
, o, o,. nl.n. F-nm "}. .ni .. Ne..n,,.: n.4m o.,. , 4, t K.,r m 1, j.- . i L,.
- a
.'k ..i .w.
". 7 . ni EL ! i ? i ,l p dij ' . .i. t.
.. l;', 'l .. g., -,.. . . m . i '
n - q, gD q i;} ..;; 1 ihs',gh ..' j 'M ) ([
- s
- .'.'.
'l ',, -, f.i.
' - , . , _ ' A'. e i.,.7 g.i.!,,'I.
, l p ' l., - 'Ill " ,, . h oT:. ,. . '., ;. ' :.a ,.Mr.1 y*.f I [
'I in ~. ~i, ~ , i. J ' '. a[ ', i , 1.' i .
a L . q g .t.
yl m n .op, e , n o n ,,1., ' , vpu .- . l ' s I' 4.
-. ., --- -
- ! u apa thh j.
. i j,. 7. 0.;..i,t.t 4,L..t...a.
+; ,.U .m c. laN,L : 'j+ W m ? , ... . <.. n.
i ., , y y.. 7.; . . p, I1 ~ - e.
, i - o e ,..
. ' ... .. .. . '. ' ,f.i1, ' '.p .I !.p: Ill l,.h.] I.'.b ief . .~ ! ' ..' l.' 1... L1.I4 lM., , ,, ,I-[ ,i'... . a.
., , .* l L; I {I{ .,' k g ,. .
..... - ,d u...y. @ fu, ' h.1 1 , ' - n ' i- .is % , s yullu ., , lJ; 1 pl ); I U.'pn ( .i
- .
i nn.
4; di.. ~~T,r.
f i i- ,4 r.. h .J-- q! .a (. p 1,t. . i.. ;
- i i
- p-p p j I I pm
, {. p,. ,.r..i g t u, . .. T...,..n.q,o.. m ..r.
.i im um s h. a.. n - a. : ii n.
,., , . , ,.
o . v.. - , . .m o y e o . . .. ....e., q,,,,.. ., g m: _,
,! . , l . i.
. ,n ..m.. g J.. . v.
._4 , ' , .l ' a: .m.
L .I en 1i ec,
l - .t y :- , , . .g
. d.' , . --. --. g .~.h .d_* ;. l l.
.
I
- ,'
. ..e .s_
- .._.
-- . 6.
q,. ,. w
l
- .
lli c }.; i.l' bu.
1t . ...P.,
i .. $.. Ib l. {b
l . ( .J, f , I ( r.r MI.
q.
j pt . s. * y.
- L.* ; ,&...i % yp:. ' : s I . l n '.N, ~
.. m ,vm . -. . ..,.:;, 7;. t .q t 4.i , - n 3 J, n ]. .y , l II ... .,. l . l j...t - . i.
) t., , .- _,... . O MQ g h [b
- '#
ek 0 . a ., , . , I i . -. - -
_ _ .O ' - -.: . -. i l i ' , t { l ' , M li j . ' l':1'; 1. l,i ,,i , t J ,_ ~
..I Elm u lo 6 h ',:, .,. .L.
,,,, '.l . ; .{.:D$" .. % r- !gg .,I r .L.._l._l.
j
' ..o.,... , , , 1 ;n > r '
. ..- , ._ .. _ i ' t
-.(. l r,,, 1.
.i } v%. . ) ; '.. l ' '.' !. l'.( , .. p .' J.i ' l..! q... i . lg r' 2.. n ' l'l I-
, t _,
ll! 'l.
,ld I l .1 i .j 'l. bl.,W I I
l.
j ! j l w ..h.
- ,
q. , d, . , ShU li
,h - .....M... t
- 1 ' N
, .w.
. _ . - , m.. . ..i j.,. . . . t ,
- e
. , .
v .- .- , , -m.
l l I - - ,i ...,. 'll.. l .. ,1.. '.. '_#..! .b.
- .]..b;
, ,jd.1 ".ulM h e, l . o . , , < h ~i
-
,7 .- .. .' '
'f ': J .i, h.
- I'
f .: .l ..d e. anneum., aanese mesen. rme seen.
.. - - - m - OS. p b}:;: {, t $ '- 'f
i d *k $ L f
- ;
~ ~ ,! - - .'.:.6 . t pib.
1'. p 4.* N g I . i
- i-l
, 1, t 'll!
. -, t l ~ ' d ll:. i.
. a '.!.,. y
! i . p .- I .'.l "h ' ,. . 4.h ';I' [ p .ii[ ... . y I i:t
... 'f yt ' l., --[ U.
. l It.4[t 9.J p
. c...% l1 [ f h.
p g , ... ...". l '.c . ]!'lpp! llt '!: i . I l h i lh d,' .' I ' !I
- 4!
d: i: Ul o '{;. ij 'l4 li f.igi[. i i i I . ,,,
- .
e J,. + 4...L .h n4.
g, .. , I.. {, l . ) , P h.f ll.
I C: .h 4! -p) '
4, ,f . l ..J ..
- d PP L.
- h
'.' W .-.m . 1 {lh.,P, , ,, ,. [ lh + 4 ' A ' ' tb t: $' y % i ~ + i . .. 't, y
li I t(pl , j ' l - l . 2' }.i.U). .h, a,d ., 'p; p' dl
- I.
G. H l "..]' O. ' -
. I ' . t< it' 't ', ! - 't,- .r.
hr.'.L.q ltn.
.i .. .9
L ? u.]{ D'. '.. ' ..h" ' .h i hh.i ' t' .! l@H .w I l , i.
'f idj h,a..,.1:,l.. 7.,, .. ,eh: l..
- M
.N..~.].,. 1 l.}. i -.U.. . ~. m 4". ;:, ) .., y j , 1." " r..'i - , l t i , ..in O: . p g t s_ .{ ..
I t .
- ._
.... ..j
- J
'. Y 4, IN Dia %, . I 'a i . .... .
,. _.; . , f.
. j , , ..
- I >
1 l ,. q ~ l,; pi p1 a ,, [, .1 . .,' ..4 . , , w --.,.'_ - , . ' ' .
.4i.. .. . , .4 - , ,. ., . i. . > ,< -., l' '} j . I- ' Ir .. ,.,f.l. ji a 4 '
....e.
' ,
.. .,n, ' ll.ilj .,'{lL L- ' .' : ' . l U.
, i lH f l.. ?iQ m . ...-.3 _.i.
._, %<.- - . D .p in f.' . , ' ,'1 > - - F-- -& -I- '* - 1 -, t. r'.g '- l i ' i l' . l Q1 "' j a - i., p. ,) l l ,"',l . l: -l. .I d tb pi.pi; = j i. i.' ,I , i - ... p ' 7.n . 1' . ll a f ,.. q,, ,',.r' ., I- , gl .j .p.. l [ l d- '(e '..
- d..
't'. M)Td I* l.
f '- I.l :. , ' t l j l- , 1-
, l 7.L, ' , p., . '..,(a I '
- fT
. lif j! g, I'
- ih!
. l i .,. .,.. j
- (-
g i { tp5-i' - '
i], r ' ' ' k "' ' [5 ' $.k .l_ e-ci
.,, . _,
..--- l l.
{ , i , 6 j' ' i - .. M, g . -. ,
- L y
p - b Idl I ! . '. '
iq
fM ..I.
l i . yt- ' yl1: c q-
- -
. L ' g f g .. - . l " ) l l ..M
... .L.
' l.
l' l ,l .. e,A . I j ... '. . .e { F1 .... h.. ' 4 '. l '. ....M ' .( , *t ', . .. . ..,.. t l l' ,, , . 1u ( ..._ y. , . .r . . -- H,.T.
--.- k' h ' ]' ..I '- 'th.. 1, $ ,i11L - '4 t. + h
g H- }( e ~ , p a;% . e } ! LL g . - I <
- ..P-
-'6 j . ! ' }. .. ....
. _. _$,
{ . P '. ,j' uy , - 4.--
, <. < ...l l, 1.M j j '.rh.
., ,.. , - i _.l.'. l
,*
r . t , ' , ) . , w i j [[_ . -. - - . i
.. hi .... ' ( .
i 'l' , j.
T'l' - TM l ?p 'i 0
i [, , ~ i i . _ , g. I I. I
, ) .{ -l ! ,.q.., .. a o . }. 'l I , d[.' !'. l..I. ) 4.
i _ , .I 4,, . u .L _, j .. l. _- m.
- !i . ', %. , %
. l - l[ i in i i. 1 ,' i. h i ~ l i
- - .,j o. {. ..'+) -
I . .y < I g
. .- . .. _ y g. J,: .. yF . l . T,.- ' l
- q lt t
. J.l. . L
.. K.L.J'.. p. l' _ _ . 4.J J.u , ..t.u [j i i i I I , { l [. 7 ' - .t. .% _.r .~_.
.i
,
s _iJa a.
, , i l w . __, _ _, .!.
== i I ,.. y _.
, l ll . g.
> t l
.i l lJ, t , ,
] .. .... ...
... { ' _[ . ,, ' ' .,t1 i
- l'
!' .. ' ' { i 1,
- l
[ _.. .
- l l.
i ,1, >Q , - i i, . t i4 '.,
- ..
' 3ip, [
.g.
, . 4 l { . I I.
i yl-p.
$, . .- If. g.
. i.
. p { t"
a i_ ' '.3 :. . 4,. d. -_.,,. , L., .,, l,i . i,,..._i_
i [j j. .g ..- . _.
.P . ,s_.. , ._ . a, , . h'. _ __ _,, _;_ ..- . . ' i
- .
t' l' , i.
- ..,
i.r ., .. _ , t
i
I .' t t : i i i.
i _. '.. -,L.. i i .l - j - .. I... F , .,. ,._.e i. . t q t - , ' , , i , , _,
, y [ , . p... . - << c.
, ,-
. i.
n ..
.-- y,
4 .
i ( i . p* p 7 r . { f- - p -, p- -g { ,, t i t.
r t,. < , . !. - ... _ _. _ . . .._ j , ;: ! q "*7 p j- . ,
i ,
i l l1 i .d .I; l d ... {;. i .. , i p.
i 4._. 4.. i i 1_.
, . i.._
. , .
,
lr ...i.. . _ _. _ , - . , .i . ..,,. , l l'. .i __.i .F - l., ..t.
.! LH.,. < , , , ., . 'I ,. l . { l l l.
I , i l l I., - l,...! ...) 7.
l.
T ' , ' . .t, '. ' j.
I (. it6 i l w.
-g.
, i ! > - , . , o - ... .. b Ndh b ( ' ! w _- i ! l__'5~! - _ w ]--_ F VI '.l T. " t 9 _F F ', ' E,N FF , l ". ni ' ' ,
r , t
i .. .~.
,
i '. m ;....'.. en
. j ,.. _. - - _. - -. . -.,. _ -. _- __ - _ _ _ _ - -. -.- .- - -.... - - -. - - - - - - -
.. , , . I '
.
EQUATION SMEET ' ,. - i f = ne v = s/t ' e ok c) -
Cycla efficiency = w = as s a v,t + at _ E = aC a = (vg - v,)/t -
A = AN A = A,e* E II = uv vg = v, + a t FI = ush w = e/c 1 = in 2/tq = 0.693/tg , W = v&P- } " (t,.)(q) .. AE = 931Aa (g+g) - 6=4C,47 , -rx x. I*e , ,,d=UAAT g, g,-vu 'Pwe = W' a" g I=I 10~"! . E I8I-F = P, 10 171. = 1.3/u ' P = P, a*II ' HYL * 0.693/u SUR = 26.06/7 i '
- ? = 1.44 DT SCR = 5/(1 - E'N)
f1 ge \\ c ',,, CR,-s/i1-x,gg,) SUR = 26
"1(1 ~ Kegg)1 = CR II ~ Ka f f)'2 T=lt*/o)< {(f ',)/x,g,,) ~~
T,= 1*/ (o - I*) M = 1/(1 - K,gg) = CR /CR ' g
T = (I - o)/ 1*ffo M = (1 - X,gg)o/(1 - x,gg)g i p = (Keff-1)/Keff = Axeff/x*ff .! SDM = (1 - Keff)/geff ! ( A*/TK.'gg 3 + [I/(1 + 1,gg )] t* = 1 x 10 aeconda ~3 ' 8* t , F=IiV/(3xIgo) ' 1,gg = 0.1 seconds A
I=W . j Idgg=Idg2 . UATER PARAMETERS Id2,gd2 g
1 gal. a 8.345 lba 1/hr = (0.5 CE)/d g,,,,,,)
2 1 gal. = 3.75 liters R/hr = 6 CE/d (g,,,) , 1 ft = 7.44 gal.
HTCC!tL WTOUS CONVERSIONS . Density = 62.4 lbs/f t 1 Curia = 3.7 x 1010dps ) Density = 1 ge/en 1 kg = 2.21 1ha
Heat of valorizatiou a 970 ttu/lba 1 hp a 2.34 x 10 ITU/hr
Heat of fusica = 144 8tu/lba 1 N = 3.41 x 106 Itu/hr 1 Ata = 14.7 psi = 29.9 in. I s.
1 Stu = 778 ft-lbf ' 1 f t. H O = 0.4333 lbf/in 1' inch = 2.34 es
T = 9/3'c + 32 , 'C = 3/9 (87 32) .... - - - - - --
r . . . ATTACHMENT 3 FACILITY COMMENTS AND NRC RESOLUTION FOR REACTOR OPERATOR AND SENIOR REACTOR OPERATOR EXAMS ADMINISTERED ON AUGUST 3, 1983 Question A.02c/H.11c Facility Comments: Since operatir.g cycles for the ULR are fairly short, Xe buildup is unappreciable and is not a factor during operation.
Operators have received generic training which has included the ranges specified in the training materials.
NRC Resolution: Because Xe effects are unappreciable at the ULR due to the short operating cycles, the generic ranges specified in the training material will be accepted.
However, more representative values should be used in future operator training.
Question C.06 Facility Comment: "Convection, radiation, and conduction" should be accepted as descriptive terms for the heat transfer mechanism.
NRC Resolution: The question has been deleted from the examination.
The question is not precise enough to elicit the required response.
Question C.10c/J.05c: Facility Comment: Although secondary flow can be controlled by a throttle valve receiving a signal frem primary , temperature, in reality, the cooling tower louvers ! are controlled by a secondary coolant temperature sensor which will regulate the air flow through the cooling tower.
In this mode, as is actually used, secondary flow will remain steady or decreasing is an accurate response.
' NRC Response: The question has been deleted from the examination.
The actual manner in which the secondary system temperature is controlled results in unacceptable question ambiguity.
Question D.11 Facility Comment: This question should be deleted from the test because it has never been addressed in training, nor does any faciltty staff member know the answer.
- - . - . - - -
. .. - - .
. ATTACHMENT 3
NRC Resolution: The question has been deleted from the examination because the answer is not known by ULR staff.
Question E.01/J.10 Facility Comment: Answers 5 and 6 are similar in that only one of these can be operative at one time depending on whether the downcomer or crosstall mode of cooling is being used.
In addition, sub trips such as Bridge Position should be accepted as correct.
, NRC Resolution: Comment noted, Bridge Position will also be accepted.
Question E.06 Facility Comment: Diagram 5.2 of the FSAR shows a rating of 75 kw, the
FSAR description states a rating of 70 kw.
Either - answer should be accepted.
NRC Resolution: Since the difference between the two ratings is small, either will be accepted. However, the precise c rating should oe used in operator training materials.
Question E.08 Facility Comment: "Trip" is nut the facility term for a scram.
This terminology may prompt the candidate to include the startup inhibit of 3 cps in the antwer and not to include the hi voltage scram. The answer depends or how the candidate interprets the word trip.
NRC Response: Comment noted, Control Blade Withdrawal Inhibit will also be accepted.
Question G.09 Facility Comment: The HP Lab and the Reactor Supervisor's offi e are the same.
NRC Resolution: Comment noted. HP Lab will be accepted in place of the Reactor Supervisor's offic i s
O &
as , + - l < e .
4 L . " }}