IR 05000057/1989001
| ML20245C963 | |
| Person / Time | |
|---|---|
| Site: | University of Buffalo |
| Issue date: | 03/30/1989 |
| From: | Eselgroth P, Denise Wallace NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20245C952 | List: |
| References | |
| 50-057-89-01OL, 50-57-89-1OL, NUDOCS 8904280047 | |
| Download: ML20245C963 (200) | |
Text
{{#Wiki_filter:- - _ ._ ______ - _ _ _ _ _ _ V.S. Nuclear Regulatory Commission Region I OPERATOR LICENSING EXAMINATION / INSPECTION REPORT EXAMINATION REPORT NO: 50-57/89-01(0L) FACILITY DOCKET NO: 50-57 FACILITY LICENSE NO: R-77 LICENSEE: State University of New York at Buffalo l
!
FACILITY: Buffalo Materials Research Center i I EXAMINATION DATE: January 30 - February 1,1989 ) CHIEF EXAMINER: - M 3-8%S9 avTd Wallace Date ! Operations Engineer (Examiner / Inspector) f APPROVED BY: // 8 3 -30 - 6 9 Peter W. Eselgroth, Chief
~
Date PWR Section, Operation Branch, DRS SUMMARY: Written and operating examinations were administered to one Senior Reactor Operator (SRO) and one Reactor Operator (RO) candidate. The SRO candidate passed both portions of the examination. The RO candidate did not pass either portion of the examination (written and operating).
The Licensed Operator Requalification Program was determined to be . effectively administered by the facility. Facility action regarding l the suspected cheating on a 1986 facility administered requalification v examination has been determined to be adequate to minimize any such future possibility. l O h h oo , PNu
,
k___________
_ - _ - - _ - - . _ _ _ _ _ _ - _ _ _.__. _ .__ ___ ..
-2-I. OPERATOR EXAMINATION SUMMARY TYPE OF. EXAMINATION: Initial EXAMINATION RESULTS l R0 l SRO l l Pass / Fail l' Pass / Fail l l 1 l l Written 1 0/1 l 1/0 l l l l l l Operating l 0/1 l 1/0 l l l l l l Overall I 0/1 l 1/0 l l l l l . 1. Chief Examiner At Site: David Wallace 2. ' Personnel Present At Exit Meeting, US Nuclear Regulatory Commission D. Wallace, Operations Engineer M. Sullivan, SONALYSTS M. Daniels, SONALYSTS Buffalo Materials Research Center L. Henry P. Orlosky T. Vargas 3. Summary Of. Comments'At Exit Meeting The BMRC personnel listed above discussed the written examinations with the NRC at the exit meeting. NRC resolution of these comments is documented in Attachment 3.
No'further comments were made concerning the operator examinations.
Attachments:
1. R0 Written Examination and Answer Key 2. SR0 Written Examination and Answer Key 3. Facility Comments and NRC Review for R0 and SRO written examinations 4. Buffalo Materials Research Center Letter Dated February 9,1989
___._________m____.___m_.______._-___.._.____._.___._____m_m____m.-_..m____m_
-
. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ . . , . . _ _ _ _ _ , _ _ . _ _ _ . _ _ _ -
-
._______._._.____-m_________-.___m _-__ _ m . _- J
_ - - _ _ - __ . _
-3-II. LICENSED OPERATOR REQUALIFICATION PROGRAM REVIEW A review was conducted in order to determine the effectiveness of the licensed operator requalification program at the facility and to ascertain whether the facility has taken appropriate actions in response to suspected cheating on a 1986 requalification test.
An indepth review of the Requalification Program by the inspector indicated that the program is well controlled and is being documented in an a
REGION 1 FACILITY: State Univ. of N.Y.
REACTOR TYPE: PULSTAR DATE ADMINISTERED: 89/03/30 INSTRUCTIONS TO CANDIDATE: Use separate paper for the answers. Write answers on one side only.
Staple question sheet on top of the answer sheets. Points for each question are. indicated in parentheses after the question. The passing grade requires at least.70% in each category. Examination papers will be picked up six (6) hours after the examination starts.
,
% OF CATEGORY % OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY 20.00 ;0.00 2 H. REACTOR THEORY 20.00 20.00 I. RADIOACTIVE. MATERIALS HANDLING DISPOSAL AND HAZARDS 20.00 20.00 J. SPECIFIC OPERATING CHARACTERISTICS 20.00 20.00 K. FUEL HANDLING AND CORE PARAMETERS 20.00 20.00 L. ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS 100.0 % TOTALS FINAL GRADE All work done on this examination is my own. I have neither given <
nor received aid.
. Candidate's Signature i _ _ _ . . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
- _ _ - - _ _ _ _ . _ _ _ _ _ _.
.
NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS e.
During the. administration of this examination the following rules apply: 1.. Cheating on the' examination means an automatic denial of your application and could result in more severe penalties.
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 room to avoid even the appearance or possibility of cheating.
~ 3. 'Use black ink or dark pencil only to facilitate legible reproductions.
4, 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 (if necessary).
6.- Use only the paper provided for answers.
7. Print your name in the upper right-hand corner of the first page of each section of the answer sheet. > 8. Consecutively number each answer sheet, write "End of Category __" as appropriate, start each category on a new page, write only on one side of the paper, and write "Last Page" on the last answer sheet.
9. Number each answer as to category and number, for example, 1.4,-6.3.
10. Skip at least three lines between each answer.
11. Separate answer sheets from pad and place finished answer sheets face down on your desk or table.
12. Use abbreviations only if they are commonly used in facility literature.
13. The' point value for each question is indicated in parentheses after the question and can be-used as a guide for the depth of answer required.
14. Show all calculations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or not.
15. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLANK.
16. If parts of the examination are not clear as to intent, ask questions of the examiner only.
17. You must sign the statement on the cover sheet that indicates that the work is your own and you have not received or been given assistance in completing the examination. This must be done after the examination has been completed.
_ - _ - _ _ _ _ - _ _ _ _ _ _ _
__ - - _ . - l t .
'~
s 18.cWhen you complete your examination, you shall: a. Assemble your examination as follows:
(1) Exam questions on top.
(2) Exam aids - figures, tables, etc.
(3) Answer pages including figures which are part of the answer.
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.
. _ . _ _ _ _ _ - . _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _
_ _ _ _ _ _
.
H. REACTOR THEORY page 4 )
:
i I QUESTION H.01 (1.50) At time zero the reactor was observed to be at 50 KWt. Five (5) minutes later the power was observed to be 1.5 MWt.
What stable reactor period was required to have reached this power level in the five (5) minute time period? t i . O
,
(***** CATEGORY H CONTINUED ON NEXT PAGE *****)
- _ - - - - _ - . - - . - - - _ --______J
._ . - - - _ _ _ - . - _ _ _ - . _ _ - - - _ . _ _ _ . . . _ - . _ . _ _ _ _ - - _ . - _ _ _ _ _ .. _ _ _ _ . - _ - - ,
j'
,
-liJ REACTOR THEORY.. Page 5
.
;
. QUESTION H.02 (1.50)
~
The fuel in.a reactor is enriched with 352 grams of U235,- Assuming no fissions from any other. fuel and complete fissioning'of all-the U235, how- . much power (MWt) would be produced.by the fissioning of the U235?
'(Avagodros Number = 1.22 E23 atoms, One fission'= 3.23 e-11 Watt Seconds)
d. QWrh
.
.
(***** CATEGORY H CONTINUED ON NEXT PAGE *****)
_ _ _ _ _ _ _ _ _ _ _ _ _ _. - -
_ _ _ _ - - _ -
,H . NEACTORTHEORY Page 6 e
QUESTION H.03 (1.00) Which one of the following statements correctly defines the Thermal f Nsutron Diffusion Length? a. The distance a fast neutron travels until it becomes thermalized.
b. The distance a thermal neutron travels before it is absorbed in the fuel.
c. The distance a thermal neutron travels before leaking from the Core.
d. The distance a thermal neutron travels from the time it becomes thermal until it causes fission.
. l (***** CATEGORY H CONTINUED ON NEXT PAGE *****)
. _ _ _ _ - - - _ _ _ _ _ - - - . _ - - _ - -- j
_-_ _ -- - _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _
. ' ) ; ]]. REACTOR THEORY' Page 7 .,
I QUESTIONL H.04 (2.00) ' Tha; reactor is' operating.at one (1) MWt steady state, when the Primary Coolant. Pump is shutdown.
Assuming no' automatic or operator actions,.what is the effect'on the following? a) Reactivity,' relative to'present value. (Positive, Negative or
.No Effect) .b) Metal-to-water ratio. (Increases, Decreases or Remain the >
Same) c) Average Thermal Neutron Energy. (Increases, Decreases or Remains the Same) d) Resonance Escape Probability. (Increases, Decreases or Remains the.Same)
. (***** CATEGORY H CONTINUED ON NEXT PAGE *****)
_ _ _ _ - - - - - - _ _ _ - _ - _ . _ _ - - _ _ - _ _
< .
H. REACTOR THEORY Page 8
. . QUESTION H.05 (1.00) .From the statements listed below, select the .ONE - (1) which correctly defines the characteristics of Primary Coolant Pump.
a Throttling the discharge valve increases the amount of current drawn by the pump.
b The starting current of the pump is greater with the' discharge valve closed, than with it open.
c Increasing the level in the Holdup Tank, increasr :the pump discharge pressure.
d The power required by the pump is inversely proportional to the
' flow.
.
(***** CATEGORY H CONTINUED ON NEXT PAGE *****)
- - - _ - - . _ - _ _ _ _ _
_ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ -
. -,
I
{
J. REACTOR 1 THEORY Page; 9 R
..
I
QUESTION H.06 (2.00) j Construction of a new core is in progress in accordance with OP #4, Fuel Configuration Management.. Criticality has been predicted when 17 fuel elements.have been loaded.
In accordance with procedure, eight (8) fuel elements have been '
. loaded and the rods withdrawn to 100%.
Additional fuel-elements are loaded, one at a' time, and rods withdrawn to 100% after each loading.
, The following count rates have been recorded from the scalar.
ELEMENTS LOADED. COUNTS 8 500 9 568
-
10 684~ 11 833 12 1110-a) Utilizing the 1/M plot provided, plot the curve for predicted criticality. (1.00) b) Predict the number of elements that need to be loaded for criticality. ( 1. 00),
.
)
i
.(***** CATEGORY H CONTINUED ON NEXT PAGE *****)
_ _ _ _ _ _ _- _ _ _ _ - -
. _ _ _ . , _ - - - _ _ - _ - _ - . '
.
,
8 9 10 11 12 13 14 15 16 17 18 19 1.0 - 1.0 0.9 0.9 O.8 O.8 0.7 0.7 9/M O.6 O.6 0.5 0.5 O.4 O.4 0.3 0.3 O.2 O.2 O.1 O.1 O O 8 9 10 11 12 13 14 15 16 17 16 19 ASSEMBLIES LOADED FIGURE 1 _ _ - _ _ - _-
_ _ _ _ _ _ . - - _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _.
- Ha' REACTOR THEORY Page 10
.: -QUESTION H.07 (1.50)-
Light-water moderated' reactor cores are either UNDER MODERATED,^ or OVER MODERATED.
a)' Is the SUNY core over moderated or under moderated? b) BRIEFLY EXPLAIN the effects on the SUNY core. power (MWt)for an
' increase in moderator temperature, during operation
.
(***** CATEGORY H CONTINUED ON NEXT PAGE *****)
__________.___ _ _ _ . . _ _ _ _ )
, _ - _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ - _ _ _ - _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ H. REACTOR THEORY Page 11
.
QUESTION H.08 (1.50) i A reactor startup has been completed from an extended shutdown.
Reactor power is increased to 2 MWt and held for fifty (50) hours, when the reactor is shutdown. Nine (9) hours after shutdown the reactor is started up and returned to 2 MWt.
a) What is the critical rod position for the second startup as compared to the first startup? (More rod withdrawn, less rod withdrawn or no change in the critical rod position) EXPLAIN your answer.
b) After the return to 2 MWt, what action is required by the operator to maintain the power at 2 MWt? WHY? (Assume manual reactor control)
.
(***** CATEGORY H CONTINUED ON NEXT PAGE *****)
_ _ - - - _ _ - -- _
_. _ - . H. NEACTORTHEORY Page 12
.
QUESTION H.09 (2.00) To equalize fuel burnup, fuel assemblies are shuffled to move some j of the peripheral assemblies to the center of the core and the ,1 central assemblies to the periphery. Assuming that only original fuel elements remain in the core, and no nat fuel addition or subtraction took place, WOULD it be safe to assume that no change in core excess reactivity took place? EXPLAIN.
.
(***** CATEGORY H CONTINUED ON NEXT PAGE *****)
- _ _ - - _ _ _ _ _ _ _ _ _ _ _ __ _
, . - - _ _ _ _ _ _ _
{I . hEACTORTHEORY Page 13
.
QUESTION H.10 (2.00) Drain lines exiting the containment building contain 24 inch " drip legs" to maintain containment integrity. HOW much internal pressure would be necessary to empty these drip legs and break containment integrity? SHOW all work. (Density of water at 70 degrees F = 62.3 lb/ft cubed)
. (***** CATEGORY H CONTINUED ON NEXT PAGE *****)
- _ _ - _ _ _ - _ _ _ - - __
- _ _ _ _ - _ _ _ _ - _ _ _ _ _ _ _ - . _ -
i
. ,H. -REACTOR THEORY Page 14 , .- .. j . QUESTION .- 'H.11 (2.00)
a) Concerning the heat transfer from nuclear fuel to the moderator, DEFINE the following terms: 1. Critical heat Flux (CHF). (0.50) 2. Nucleate Boiling.- (0.50) ' b) Why does the heat flux transferred to'the moderator,-from a fuel rod, decrease as the fuel cladding temperature increases past the Critical Heat Flux? .(1.00)
.
.
(***** CATEGORY H CONTINUED ON NEXT PAGE *****)
l _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ . . _ _ _ 1
_ _ - _ _ .
.
U. REACTOR THEORY Page 15
.
QUESTION H.12 (2.00) a) From the energy listed below, select the ONE (1) which represents the amount of energy released by the fission of one atom of Uranium 235.
(1.00) 1 5 -10 MeV 2 50-70 MeV 3 100-120 MeV 4 180-200 MeV b) Which ONE (1) of the following contributes the majority of the energy released due to Uranium 235 fission? (1.00) 1 The kinetic energy of the fission neutrone 2 The kinetic energy of the fission fragments 3 Prompt Gamma energy 4 Beta decay energy i l
.
,
I
I I
(***** END OF CATEGORY H *****)
i ~ ~ ~ _ - _ _ - - - - - _ _ _ . - _ - - _ . _ . -
.. .I . RADIOACTIVE MATERIALS HANDLING DISPOSAL Page 16 .
AND HAZARDS
.
l
.
(***** CATEGORY I CONTINUED ON NEXT PAGE *****)
- - - - _ _ _ - _ - - _ _ . _ _ - _ _ _ _ _ -
_____._________ _ i : i, l ,I . RADIOACTIVE' MATERIALS HANDLING DISPOSAL Page 17' AND HAZARDS
..
l l l
~ QUESTION I.01' (2.00)
l AnLopen vessel contains an unknown pure substance. Two.(2) meters from the l .. container, the gamma radiation level is 1.5-R/hr.
How'many curies of the unknown substance are in-the container?
. (***** CATEGORY I CONTINUED ON NEXT PAGE *****)
_ _ _ _ _ _ _ _ _ -
_ _ _ _ _ _ _ _ _ _
.I.
,'- RADIOACTIVE MATERIALS HANDLING DISPOSAL Page 18 AND HAZARDS.
, QUESTION I.02 (2.50) A seven (7) curie Cobalt source has dropped from a radiographer L shielded container.- The source has been' located.and must be replaced in the shielded container.-
.
It is estimated that it will take three (3) minutes from the' time the source is grasped.until it.
is deposited in the container.
How far must the retrieving. device end by from the' retrievers body for the retriever to receive a maximum does of 100 mr? e
.
I i I (***** CATEGORY I CONTINUED ON NEXT PAGE *****)
!
L i
___________ ,
* I
?: . RAblOACTIVE MATERIALS HANDLING DISPOSAL Page 19 AND HAZARDS
' l i
I1 QUESTION I.03 (1.25)
!
What are the current State and Federal regulations concerning the radiation exposure limits per calendar quarter for the following? a) Whole body (State two (2) limits and explain the difference). (0.75) b) Skin of the whole body. (0.25) d) Extremities. (0.25)
, . (***** CATEGORY I CONTINUED ON NEXT PAGE *****)
-_ _ - _ _ _
, ,I . RADIOACTIVE MATERIALS HANDLING DISPOSAL Page 20 AND HAZARDS .
QUESTION I.04 (1.50) A sample of Chromium 51 has been removed from the reactor and placed in a lead container one (1) inch thick. The reading at the surface of the shield is 10 mr/hr What is the intensity of the radiation at the unshielded source?
[The density of lead is 11.35 gm/cm3. u (mu) = .937]
i
.
l (***** CATEGORY I CONTINUED ON NEXT PAGE *****) l _ _ _ _
i l l
' ,I . - RADIOACTIVE ' MATERIALS HANDLING DISPOSAL Page 21 AND HAZARDS .
QUESTION. I.05 (2.25)
.Several different devices are.used at SUNY to obtain radiation exposure to personnel. .Briefly explain the following devices.
Include CONSTRUCTION, DETECTION and how radiation exposure is obtained.
a) Pocket dosimeter.
i i b) Thermoluminescent Dosimeter (TLD). ! c) . Film Badge.
(Three' required at 0.75 ea)
.
!
(***** CATEGORY I CONTINUED ON NEXT PAGE *****)
l - _ - _ _ - _ _ _ _ _ _ ._. _
. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _
JJ..' RADIOACTIVE MATERIALS HANDLING DISPOSAL Page 22'
.AND. HAZARDS ..
t QUESTION I.06 (1.50) Fill'in the blanks in the-following table wit
-
he proper radiation levels.
LABEL MAXIMUM DO RATE AT MAXIMUM DOSE RATE ANY POIN .ON THE SURFACE ONE (1) METER OF TH ACKAGE FROM THE-SURFACE OF THE PACKAGE RADIOACTIVE WHITE'I . __ ( a ) -(b)
-RADIOACTIVE YELLOW II (c) (d)
RADIOACTIVE YELLOW III (e) (f) f
\ /
&
\
.
l l l ,
; (***** CATEGORY I CONTINUED ON NEXT PAGE *****)
_ _ _ _ _ _ _ _ _ _ _ I. $1RDIOACTIVEMATERIALSHANDLINGDISPOSAL Page 23 AND HAZARDS
.
QUESTION I.07 (1.00) I LIST two (2) of the three guidelines, as recommended in the Radiation Protection Manual and Training Guide, used to control radioactive contamination which could lead to internal radiation exposure. l
.
l l l I
t (***** CATEGORY I CONTINUED ON NEXT PAGE *****) o i
_ __ _ _ _ _ _ _ - _ _ _ _
.-
. I '. ' RADIOACTIVE MATERIALS' HANDLING DISPOSAL Page 24- . AND HAZARDS
..
' QUESTION I.08 '(1.00)
.Which one of the following statements 'is true concerning the disposal of radioactive waste?-
a) Radioactive acids should be neutralized with a base prior to disposal.
b) When possible, radioactive aqueous liquids should be mixed with organic' liquids prior to release, c) Biological waste should contain a sufficient amount of preservative and absorbent to prevent decomposition.
d) Precautions should be taken not to auto clave radioactive bichazardous waste prior to release.
.
. (***** CATEGORY I CONTINUED ON NEXT PAGE *****)
_ _ _ . - _ - - _ . - - - . _ - - _ - _ _ i
. 'I.'. RADIOACTIVE MATERIALS HANDLING DISPOSAL Page 25 ,'AND' HAZARDS i
QUESTION. I.09 (1.50) LIST three (3) of the four special precautions, in accordance with the Radiation Protection Manual and Training Guide, to be observed when working with radioactive materials, which are highly radioactive, to minimize exposure.
,
. (***** CATEGORY I CONTINUED ON NEXT PAGE *****)
, - _ . . - _ - _ _ _ - - _ _ , - l: .
.I.
'
' RADIOACTIVE MATERIALS HANDLING DISPOSAL Page 26 AND HAZARDS ,
l
,: QUESTION I.10 (1.00)
An' individual is exposed to a radiation field for one hour. He receives 100 MREM of gamma radiation, 60 MRAD OF SLOW NEUTRONS AND 70 MRAD of beta.
Which one of the following is the individuals dose equivalent? a) 910 MREM b) 350 MREM c) 370 MREM d) 230 MREM
,
.
(***** CATEGORY I CONTINUED ON NEXT PAGE *****)
_____:-____________-_______ _
_ _ _ _ _ _ _ _ _ _ _ _ __ e 1
'
I. RADIOACTIVE MATERIALS HANDLING DISPOSAL'
'
AND HAZARDS-
'Page 27 ,
' QUESTION I.11 (2.00) A sample is removed from the Beam Tube and is surveyed to be 100 MREM at a distance of ten (10) feet. Six (6) hours later a survey i
.raveals'the radiation level at ten (10) feet is 70. MREM. I a) What is the radiological half life of the material?
b)HIf the-material cannot.be shipped until the radiation level is" ten (10) MREM at one (1) foot, how long, after removal from the Beam Tube, will it_be before the material can be shipped?
.
(***** CATEGORY I CONTINUED ON NEXT PAGE *****)
)
--_ _ _ _ _ - _ _ _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - --- - - - - - -- -
_ _ _ _ _ _ . l.
,I . RADIOACTIVE MATERIALS HANDLING DISPOSAL Page 28 AND HAZARDS
.
QUESTION I.12 (1.00) List four (4) of the radioactive decay modes.
, l
.
I
> (***** CATEGORY I CONTINUED ON NEXT PAGE *****)
_ _ _ _ _ _ _ - _ _ _ _
_. - _-_-_ -_ _ . .
;I. RADIOACTIVE MATERIALS HANDLING DISPOSAL. Page 29 ' -AND HAZARDS .
QUESTION 'I.13 '(1.50) a) State why.a Geiger Muller counter (GM) is not normally'used
'to measure exposure rates. (1.00)
b) Explain what needs to be done in order to use a GM for determining exposure rates. (0.50).
.
.
l I.
(***** END OF CATEGORY I *****) w__________-_-_ _.
'J.
. SPECIFIC OPERATING CHARACTERISTICS Page 30 i
.
.
.
(***** CATEGORY J CONTINUED ON NEXT PAGE *****)
m_____..________________ - . . _ . _ - - _ - - - - - - - -_ -- i'
_ _ - _ _ _ - J. SPICIFIC OPERATING-CHARACTERISTICS Page 31 ,
'
j ' I QUESTION J.01 (1. 50) a) LIST the condition (s) which will initiate an automatic closure of the Containment Ventilation System automatic dampers. (0.50) b) What four (4) AUTOMATIC ACTIONS occur as a result of the damper closure? (1.00)
. (***** CATEGORY J CONTINUED ON NEXT PAGE *****)
. _ _ _ _ _ - _ .'sT . SPICIFIC OPERATING CHARACTERISTICS Page 32 .
QUESTION J.02 (O.70) Operating Procedure OP 45, Hot Cel'1.and Manipulator Operation, contains'the following caution "Never close the tong fingers at the tong assembly (slave'end)". What'is the REASON for this caution?
,
_
.
! 1 . l-l (***** CATEGORY J CONTINUED ON NEXT PAGE *****) .
!
u___.______-__-__-__.___--_-_ _
- - - _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _
r--
-- - - - - . _ _ _ __ _ - - - - - -
l ,J . SPECIFIC OPERATING CHARACTERISTICS Page 33
QUESTION J.03 (1,00) How are the neutron detectors positioned for a high residual Xenon concentration as compared to a low residual Xenon concentration (cold startup) when performing a reactor startup? l l l
l
.
l l l l ll l t
!
I
. (***** CATEGORY J CONTINUED ON NEXT PAGE *****)
- - _ _ _ _ _ ,
l'
'J. SPECIFIC OPERATING CHARACTERISTICS ,
page 34
'
! ! QUESTION J.04 (2.00) A loss of the 5000 volt power supply supplying the facility has occurred.
a) How is emergency power supplied to the essential loads at the facility? (1.00) b) LIST four (4) of the loads which are AUTOMATICALLY supplied from the emergency power source. (1.00) l
. (***** CATEGORY J CONTINUED ON NEXT PAGE *****)
- -- __- -_--
- - - - - - --
7.- ' 1 SPECIFIC OPERATING CHARACTERISTICS ;page 35-
.. :. QUESTION J.05- (1.50) i i
f Answer theJfollowing questions concerning the Primary Cooling Subsystem. ! a) How is heat removal from the core maintained if the primary coolant pump stops? (0.50) b) What is the purpose of the holdup tank on the discharge of'the outlet plenum? (0.50) c) How is the reactor pool temperature maintained during reactor operation? (0.50)
. (***** CATEGORY J CONTINUED ON NEXT PAGE *****)
_ _ _ _ _ _ _
_ _ _ _ - . - _ _ _ _ _ - _ _ _ - _ _ - iJ.' SPECIFIC OPERATING CHARACTERISTICS- ~ Page 36.
L ..
. QUESTION . J . 0'6 (1.75),
Th'e facility design provides for control of tae containment atmosphere to prevent uncontrolled leakage of radioactive gases to the environs.
.a) How is this control maintained during normal reactor operatlon?
(C.50)
b)~ BRIEFLY DESCRIBE how' leakage is prevented during accident conditions (1.25)
!
*
)
l (***** CATEGORY J CONTINUED ON NEXT PAGE *****)
' --
_ _ - _ _ - _
_ - - - _ _ _ _ _ - _ _ __ _ _ _ - - - _ _ . . - _ _ _ _ _ _ _ _ - _ _ _,J. SPECIFIC OPERATING CHARACTERISTICS page 37
..
QUESTION J.07 (1. 00) Precaution II.C in OP 23, Filling and Draining the Reactor Drain Tank, states magnet current must be disabled".
"Whenever water is drained below the dashpots of the control rods, a) What is the reason for this precaution? (0.50) b) What could be the consequences of having the water below the level of the dashpots? (0.50) i l l (***** CATEGORY J CONTINUED ON NEXT PAGE *****) 1 l
- _ _ - _ _ - _ _ - - - _ _ _ _ _ - - - _ - - _ - - _ - _ - - - . _--_ _ - - - - - - .-
_ _ _ . - _ _ - _ - _ . gr . SNECIFIC OPERATING CHARACTERISTICS Page 38 J l
* I QUESTION J.08 (0.75)
Concerning the ventilation system dampers, will failure of the hydraulic pumps cause immediate loss in hydraulic header pressure? BRIEFLY EXPLAIN.
.
(***** CATEGORY J CONTINUED ON NEXT PAGE *****)
_ - _ _ _ _ _ _ _ _ _ - _ _ _ _ - _ _ - _ _
- _ _ _ _ . _ - - _--_;._. _ _ - . _ _ . _ _ _ _ , _ . _ _ _ __ . - - - - . _ _ - - . - - ._ _ _ - - - _ _ _ - - . _ - - . l - J;- SPECIFIC OPERATING CHARACTERISTICS _Page 39
-QUESTION-- .J.09 :(1.50)
a) How is the core coolant. activity monitored?
~
I' b) At.what point in the system does the monitoring'take place?- 1 lL c) Why is the activity monitored at this point? l
.
(***** CATEGORY J CONTINUED ON NEXT PAGE *****)
_ _ _ _ . _ _ _ - - - - - _ _ _ _ _ _ - - - - - - - - - - - - _
-__ _ -_ ___ - _ _ . J
,J. S$ECIFIC OPERATING CHARACTERISTICS Page 40
,
:
i l QUESTION J.10 (1.00) )
{
i would loss of air to the air compressors supplying air to the primary coolant flow transmitter prevent monitoring primary coolant flow? EXPLAIN l
.
.
l l
(***** CATEGORY J CONTINUED ON NEXT PAGE *****)
E__
_ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ,
' ;J. SPECIFIC OPERATING CHARACTERISTICS Page 41-r
) QUESTION J.11 (2.30) For the follcWing instrument channels, LIST the FUNCTIONS (Scram, Alarm,
' Inhibit, Indication or Reverse) provided by the instrument.
NOTE: There may be more then one function or setpoint for each
. channel.
INSTRUMENT CHANNEL FUNCTION SETPOINT Power Safety a (0.20 b (0.20 Log Count Rate c (0.20) d (0.20) Dry Chamber Door e (0.10) f (0.10) Primary Flow g (0.20) h (0.10) Flapper Position i (0.10) j (0.10) Water Level k (0.30) 1 (0.30) Pool Temperature m (0.10) n (0.10)
.
(***** CATEGORY J CONTINUED ON NEXT PAGF *****)
- _ _ _ - _ _ _ _ _ - _ - _ - - _ _ _ _ - - - _ _ _ - . _
, _ _ _ - _ _ _ _ _ _ _ _ _ - _ _ _
J< SPNCIFIC OPERATING' CHARACTERISTICS .Page 42-
. . QUESTION J.12 (2.00)
In'accordance with the Safety Evaluation Report,-a maximum startup' accident.
has been postulated for the SUNY reactor.
STATE the FOUR (4) assumptions made which' place the reactor in this accident condition.
.
(***** CATEGORY J CONTINUED ON NEXT PAGE *****) . - - _ - _ _ _ - _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ - _ _ _ _ _
. - _ - - _ _ - _ _ . . _ _ _
_ _ _ _ . . _ _ _ _ , - _ _;______._,
.
!,
.J. bPE'CIFIC'OPERATINGCHARACTERISTICS Page 43.
, i-l1 1 QUESTION. J.13 (1.50)
~ .' FILL IN THE BLANKS l~ s For reactor' power-in excess of- a KWt, the plenum flapper valve will ba ' ~b .(Openi Closed) and the primary coolant flow will be~at least c gpm.
.
(***** CATEGORY- J CONTI!!UED ON NEXT PAGE *****)
__ _ _ ____ _ - -__ _ _
- - - _ - - _ _ _ - - - _ _ _ _ . .. . _ - ,J . : SPECIFIC' OPERATING CHARACTERISTICS Page 44 .
a , , JQUESTION J.14 (1.50)
' LIST ' the chemistry : limits ' for the: following: :a) PoollPh
, b) Pool conductivity c) Demineralized Effluent Resistivity I
. (*****~END OF CATEGORY J *****)
1. . E_ __ =_ z _ __ - - _ _ _ _ _ - _
__
,. ._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
,
, , w I 'E' ~FtfEL HANDLING AND core PARAMETERS Page 45 s. I I
i
!
l~ i
. (***** CATEGORY K CONTINugn on NEXT PAag &,,,,y
_ _ _ _ _ _ _ _ _ _ _
-. _-- ,K . FdEL HANDLING AND CORE PARAMETERS Page 46 ,
QUESTION K.01 (0.75) DESCRIBE the method 'ased to irradiate a SINGLE sample in the IF Tubes.
. l l l l
(***** CATEGORY K CONTINUED ON NEXT PAGE *****)
u_-__
_ - . _ , _ _ - - - _ _ _ _ _ . --- - _ _ _ _ _ _
' ,K . FU'EL ' HANDLING AND CORE PARAMETERS Page 47
- <
<
l .QUESTION K.02 (2.50) The. requirement to meet the Technical Specification shutdown margin, limits
.the excess reactivity which may be loaded into the core.
'a) What is.the shutdown. margin required by the Technical Specifications for the SUNY core? (0.50) b) What negative. reactivity effects must be overcome by loading excess reactivity into the core? .(Include for each negative reactivity.
effect WHEN it is at its most negative level) (1.50) c) What is.the maximum excess reactivity allowed to be loaded into the core, including the worth of all experiments? (0.50)
.
(***** CATEGORY K CONTINUED ON NEXT PAGE *****)
-- _ - _ _ _ _ _ _ _ _ _ _ _
_ _ - _ _ _ - _ _ _ _ _ _ _ _ - _
,K. F8EL HANDLING AND CORE PARAMETERS Page 48 .-
QUESTION K.03 (1.00) LIST the two (2) methods by which a fuel assembly which is under water and irradiated, can be identified.
. I i
!
(***** CATEGORY K CONTINUED ON NEXT PAGE *****)
_ _ _ _ _ _ _ _ _ _ _ _ - . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___ . - - - __ _ _ _ _ _ _ _ _ _ ______J
_ _ _ _ - - . _ - _ -. - - - _ _ _ . - __-_ _
-. _ _ - . - -- -.
j( . - DEL HANDLING AND' CORE' PARAMETERS Page:49-
, \
QUESTION K.04 (1.00) f- What_ prerequisites must be met,. prior to removing'a safety control blade for maintenance?-
,
,
(***** CATEGORY K CONTINUED ON NEXT PAGE *****)
_ _ _ ________:___._ -
- _ _ _ _ - _ - _ _ - .- _ _ - _ _ . __ _ . _ _ _ _ . . _ _ _ _ _ _ _ _ _ - _ - . _ _ _ _ . . _ _ _ . - _ _ .K .- FU'EL HANDLING AND CORE PARAMETERS' Page 50 ,
QUESTION K.05 (1.50)
, .
LIST the THREE (3) criteria that are used to' determine if double encapsulation is required for.. experiments and samples that are to be irradiated.
,
,
.
.
(***** CATEGORY K CONTINUED ON NEXT PAGE *****)
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___ _ ___ _ _ _ _____ _ _ __ ____________ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _
_ - _ - . _ _ _ - _ - _ _ --. -_ - __. - - _ - _ _ - . _ . _ _ _ _ _ - - _ _ _ _ _ . - _ _ _ _ _ _ _ _
.K . FUhL! HANDLING AND~ CORE PARAMETERS Page 51 *
QUESTION K.'06 (2.00) FILL IN THE BLANKS Samples or experiments known to be-less than a- delta K/K may be loaded with the reactor in operation. If the operation results in a.
positive reactivity change, reactor power should be lowered to below b MWt, before operation. Experiments that are, or may be worth greater than c delta K/K, must be loaded with the reactor subcritical.
by at-least d delta K/K/. . l
_
.
(***** CATEGORY K CONTINUED ON NEXT PAGE *****)
- - _ - - - _ _ _ _ _ - _ _ _ _ _ _ _- __
_ _ _ .
- - _ _ _
K. FUbL HANDLING AND CORE PARAMETERS Page 52 s QUESTION K.07 (1.00) One of the postulated fuel cladding failures is known as " waterlogging".
DESCRIBE the conditions which could result in waterlogging, and the EFFECT created by this phenomenon.
!
.
(***** CATEGORY K CONTINUED ON NEXT PAGE *****)
- - - - - - - - - - - - - - - - - - )
- - _ - _ , - _ _ - - _ - _ - . _ . - _ _ - _ - _ _ _ _ - - _ - - _ _ . _ - _ . . - - - _ - _ _ _ - _ _ _ _ _ _ _ - _ _ ._-__ - _ _ .* ., .K.- . FUEL HANDLING AND CORE' PARAMETERS .Page-53 s
QUESTION K.08- (2.50)
.The- Technical Specifications define the requirements for storage of " cold .
fuel, a) DEFINE cold fuel (0.50) b) HOW is the fuel stored?'(Include location, containment and spacing).
( 1. 0 0 )'
~
c). Where'can the fission plate be stored (1.00)- t
-
.
(***** CATEGORY K CONTINUED ON NEXT PAGE *****)
- - ____ - _ - -. __ _ . - - _ _ . _ . _ _ _ . _ _ _. __ - _ _ . _--- . _ _ _ - . -g s .,
l i: :K. FUEL HANDLING 1AND CORE PARAMETERS Pagel54
. V.
t, QUESTION K.09 -(1.00) f. . Irradiated fuel'is normally stored-in.the reactor tank.'on the grid plate or-
~in storage racks.
, a)- In the event that repairs are required in the lower pool, where may
.the fuel be stored? (0.50)
C
.b) The calculated K Eff for the storage array, for fuel stored out of the tank, must be less than 1 for.the 2 (Flooded,.
Unflooded) condition.
.
(***** CATEGORY K CONTINUED ON NEXT PAGE *****)
_ _ _ _ _ _ _ _ - _ _ _ _ - _ . _ - . __.
. - _ - _ _ _ . _ _ - - . . - - - - _ - . z.
p4 . 1
;.K. FUEL HANDLING AND CORE PARAMETERS- Page>55
'
t QUESTION K.10 (1.75) l Argon 41'.and Nitrogen 16 are two radioactive isotopes normally produced at
.the facility..
a)- What are the reactions in the reactor that result in the production of these two (2) isotopes? (1.00) b) How are the hazards.from these isotopes minimized at SUNY? (0.75) l
.
,.
(***** CATEGORY K CONTINUED ON NEXT PAGE *****)
, - - - _ _ _ - _ _ _ __ K. FUhL HANDLING AND CORE PARAMETERS Page 56-( QUESTION K.11 (1.50) Two (2) secured experiments have been installed in the core. The first experiment has a reactivity of -1.3 delta K/K. The second experiment has a reactivity of +1.2 delta K/K. An unsecured experiment with a reactivity worth of -0.4 delta K/K has also been installed. Would the Technical Specifications allow the insertion of an experiment in the the pneumatic tube of -0.2 delta K/K? BRIEFLY EXPLAIN.
.
. (***** CATEGORY K CONTINUED ON NEXT PAGE *****)
_ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ - -
___ E. FUEL HANDLING AND CORE-PARAMETERS Page 57 t QUESTION K.12 (2.00) Pnnumatic tube systems are used at the SUNY facility for dry irradiation of camples.
a) Where are the controls for the PNC's located? (0.50) b) How can the operator determine if the sample (Rabbit) is in the reactor? (0.75) c) The PNC operates at a 40 oz .r acuum while transferring. Is there any danger of draining the pool, if a leak develops in the PNC tubing under water? BRIEFLY EXPLAIN. (0.75)
. (***** CATEGORY K CONTINUED ON NEXT PAGE *****)
L_____________ __
- _ - _- - -_ -_- - --_- - _ __-_ -_ _-_ -_ ._. . _ _ _ _ - - _ _ - _ _ _ _ _ _ _ _ - - - _ - - _ - - - .K . - INL HANDLING AND' CORE PARAMETERS Page 58 ,
QUESTION'- K.13 (1.50)
.
' The physical design of the beam tubes minimizes the effects of gamma and-nautron radiation.
a)' What physical-design prevents / minimizes streaming? (0.50) b) What prevents high radiation levels in the area where the tubes terminate? (0.50) c)1 'What design feature prevents the concrete plugs from failure due to-pressure buildup? . (0. 50)' l l !
.
J
(***** END OF CATEGORY K *****)
L (. :__-_--_-________-____
.___ ______ _
I -i h. . f -' .Le ADMINISTRATIVE U R E S ,' CONDITIONS AND LIMITATIONS Pa9e 59 l l
l \ !
. (***** CATEGORY L CONTINUED ON NEXT pAGE *****y
- - - _ _ _ _ _ _ .
. _ _ - - _ _ _ - _ - _ , - - _ '
g L. - D'MINISTRATIVE PROCEDURES, CONDITIONS Page 60 K . AND LIMITATIONS
QUESTION L.01 (1.00)
-In accordance with SUNY Operating Procedure OP 57, Facility Security:
a..What action is to-be'taken if a~ security key.is lost or stolen?
(0.50)
b. What action is to be taken if an access card'is lost?' '(0. 50) - f
.
.
(***** CATEGORY L CONTINUED ON NEXT PAGE *****)
1' __--_m____u___-..m._. - - - - - - - - - - - - - -
_ _ _ ._
l l j ,L . ADb1NISTRATIVE PROCEDURES, CONDITIONS Page 61 I AND LIMITATIONS
l l l QUESTION L.02 (1.00) In accordance with the Technical Specifications, when must a licensed operator, RO or SRO be present in the control room? i
! l l
'l l
l I
'
i i I
l I
(***** CATEGORY L CONTINUED ON NEXT PAGE *****) l l
. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ . _ _ _ _ _ . _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
- - . _ _ _ _ _ _ - _ . .. ._ - _
-. - - _. . _ . .-
-*'i , . . .
.L. ' ADMINISTRATIVE PROCEDURES, CONDITIONS Page'62.
tAND LIMITATIONS s QUESTION L.03 '(2.00)
~
List:four (4)1of the.five-(5) operations which must be supervised by an SRO, according.to Technical Specifications.
, !
. (***** CATEGORY L CONTINUED ON NEXT PAGE *****)
- :: _ _
. _ - _ _ - _ . - - _ --_ - _
..
:.
_
' ,e l , . .L . ADMINISTRATIVE PROCEDURES, CONDITIONS Page 63 ;,AND LIMITATIONS ,
l
:
QUESTION. .L.04. (1.25) Concerning the Operating Procedures for SUNY: a. What'is the MAXIMUM amount of time that an Operating Procedure may be used without being reviewed? (0.50) b. What must be_ completed, from an administrative perspective,before a new or revised Operating Procedure can be used? (0.75) l l
.
I (***** CATEGORY L CONTINUED ON NEXT PAGE *****)
: _ - _ - _ _ _ - _ _ _ _ _ _ - -- -
._
_ _ _ _ _ _ _ _ - _ _ - _ - i
. <
L. ADMINISTRATIVE PEOCEDURES, CONDITIONS Page 64
,AND LIMITATIONS QUESTION L.05 (1.50)
From the following list, SELECT the reportable occurrences which require filing Reportable Occurrence Reports.
a. A medical emergency requiring transport of contaminated personnel.
b. A tornado causing loss of normal AC power to the facility.
c. Release of fission products from a leaking fuel element. j I d. Radiation exposure of personnel in excess of 10CFR limits.
o. A trip of the Primary Coolant Pump results in a reactor shutdown (scram) ] f. A channel check reveals that a Power Safety channel high flux trip set point is 2.6 MWt. j
. (***** CATEGORY L CONTINUED ON NEXT PAGE *****)
- - - - - - _ _ _ _ _ _ _ _ - - - . - .
_ _ - _ _ _ _ - L. ADh4INISTRATIVE PROCEDURES, CONDITIONS Page 65
,AND LIMITATIONS l
l l l QUESTION L.06 (2.25) List the three (3) alarm or notification systems used to initiate a prompt evacuation of the facility. (Include, if applicable, how long the alarm / notification is active, and how it is terminated)
. (***** CATEGORY L CONTINUED ON NEXT PAGE *****) - _ _ _ - _ _ _ _ - _
_ _ _ - - - - - _ _ _ _ _ - - . _ _ _ _
-K_
j; ; L. - AD INISTRATIVE PROCEDURES, CONDITIONS Page 66 ' q AND LIMITATIONS ! l I. QUESTION L.07 (2.00) List four (4) of the six (6) actions to be taken by personnel in the
.cVent.of a known spill of radioactive materials. (Exclude those actions
.to be taken by Health Physics personnel)
,
.
.
I (***** CATEGORY L CONTINUED ON NEXT PAGE *****) __ _ ___ _ _ _ -
- - _ - - _ _ _ _ - _ _ _ - _ - - .
J.,i AD INISTRATIVE PROCEDURES, CONDITIONS Page'6'7 y AND LIMITATIONS
1
-
. . QUESTION L.08 (1.75) In accordance with Emergency Procedure EP 4, Reactor Loss of Coolant
. " Accident, LIST'seven (7) of the eight.-(8)-operator actions to be~taken-on the loss of primary. coolant accident. .
_
.
-
(***** CATEGORY L CONTINUED ON NEXT PAGE *****)
____- ___ ___--___ - _ . _. _
_ - - _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ - _ - _ _ - _ _ _ _ - _ - __ .__. _ - __ _ _ _ _ - - . . _. . l
N , L; ADMINISTRATIVE PROCEDURES, CONDITIONS Page 68 L AND LIMITATIONS t, i l QUESTION L.09 (2.50) Preparations are being made.to pump the 10,000 gallon radioactive waste
. storage tank.
l a. List the three_(3) flow paths available using the pump discharge (0.75) from the tank.
b. With flow established to the sanitary sewer, the flow indicator (0.75) is reading zero flow. Does this indicate that the flow indicator is malfunctioning? BRIEFLY EXPLAIN.
c. How is transfer of sludge fr'm the bottom of the tank to the (1. 00)
. sanitary sewer prevented. Include DESIGN FEATURE (S) and ADMINISTRATIVE CONTROLS.
<
.
(***** CATEGORY L CONTINUED ON NEXT PAGE *****)
. _ - _ _ - -
_ _ _ - _ - _ _ _ _ _ _ _ _ - _ - _ _ eg-L.' ADMINISTRATIVE PROCEDURES, CONDITIONS Page 69
.,AND LIMITATIONS ,
l QUESTION L.10- (1.50) ' For each of the action level in column I, identify the proper Emergency-
' Classification in column II (Note: Emergency Classifications in column II may be used more than once)
COLUMN I' COLUMN II 1. The projected. level of radiation a. Notification of Unusual within ten (10) meters of the Event Emergency Planning Zone Boundary is 100 mrem / hour whole body. b. Emergency Alert I s c. Site Area Emergency 3. Receipt of a bomb threat 4. A tornado is observed in close-proximity to the reactor. facility.
~
.5.. Severe failure of the fuel cladding with the containment intact.
6. A demonstration in progress, with threatened entry into the facility.
'
.
) (***** CATEGORY L CONTINUED ON NEXT PAGE *****)
- - - _ _ - - _ _ - .
_ _ _ _ _ _ . _ _ _ _ _ _ - - - _ _ - - _ _ - - _ - - - - - -- - - --
, Il.' ADMINISTRATIVE PROCEDURES, CONDITIONS Page 70
,
.t.'AND LIMITATIONS-l QUESTION L.11 (1.50)
.The Emergency Plan and the Emergency Procedures require periodic review..
'
.a. What facility organization is responsible for review and revision.of.the Emergency Plan and the Emergency Procedures? (0.50)
b. What-facility organization is required to approve Emergency Plan changes? (0.50) c. What state organization is responsible for review and comment'on revisions to the Emergency Procedures? (0.50)
.
(***** CATEGORY L CONTINUED ON NEXT PAGE *****)
_ _ - - - - - _ _ _ _ _ - - _ - - - . .- - _ - .
. _ _ _ _ _ - - _ _ _ _ _ _ . - - _ . . _ _ - - _ . _ - .--- - - - - - - - - - -- - -
-- - - - - - -- -
- - - - - - - - - - - - - - - - - - - - - ---- - -
'Li N MINISTRATIVE PROCEDURES, CONDITIONS Page 71 # --[*ANDLIMITATIONS-QUESTION
_ L.12 (1.75) In the event of an emergency at the facility:' !
:a.- How is the determination made for the assignment of the Emergency-Director? (0.50)
b. LIST two-(2)~ responsibilities which the Emergency Director may not delegate.
(1.00) c. Who, by title, is responsible for the radiological assessment during an emergency? (0.25)
.
(***** END OF CATEGORY L *****)
(********** END OF EXAMINATION **********)
- _ _ _ _ - - _ - - - - - _ - - _ . . -_ - --
- , _ _ _ _ _ _ _ , - _ - _ _ - - - - - _ _ _ . .- - _ - . - - _ _ - _ - - - _ _ _ _ - _ _ - _ . . _ _ _ _ - _ _ _ - _ _ _ - _ _ _ - _ - - _ _ _ _
'. )
*
3- ,
]H.- %3 ACTOR' THEORY- Page-72'
]
.{
.,
JANSWER H.01' '(1.50)-
-
l P=Po e t/T (0.50) 1. 5...X .10E6 = . 5 ' X J 10E4 -'e * * (t/T)
' '1.5 X:10E6 / 5:X 10E4'.= e **(30'0/T) .In'30_= 300/T (O.50) , .T = 88, Seconds (+/*,2, seconds) , .(0.50) - R' EFERENCE '
Nuclear Physics:Made Very Very Easy l pg 12' . ANSWER- H.02 (1.50)-
'352 grams of U235 = 9 X 10E23 atoms of U235. (0.50)
, -
-# atoms U'235 X n tt/;cevuds/ fissioii = Power (MWt) (0.50).
/s/x W R cccQ
. . +w.oe .
9 ' X 10E23 X . 3.23 X 10E-11 = : 2. 9 X 10E13 watt / seconds = 8- X 10E3 p- MW hours. .(0.50)
,.
l REFERENCE -]
.i : Nuclear Physics Made Very Very Easy pg 11 i>
I-l (***** CATEGORY H CONTINUED ON NEXT PAGE *****)
'
L_____-________~_
_ _ _ _ _ _ . s ',g.
- RbACTOR THEORY
,
Page 73
.
ANSWER H.03 (1.00) d (1.00) REFERENCE , Nuclear Physics Made Very Very Easy pg III 12 ANSWER H.04 (2.00) a) Negative b) _Docreasss /ee /ro /<C ' c) Increases d) Decreases (4 required 0 0.50 ea) REFERENCE Nuclear Physics Made Very Very Easy pg III28 ANSWER H.05 (1.00) c (1.00)
.
REFERENCE Gsneral Electric BWR Academic Series 1985 Heat Transfer and Fluid Flow pg 6'100 (***** CATEGORY H CONTINUED ON NEXT PAGE *****)
____ s
* .H. REACTOR THEORY Page 74 ,
ANSWER H.06 (2.00) a) See 1/M plot (.2 for each point plotted) b) 15 fuel elements. (1.00) REFERENCE OP #4-Fuel Configuration and Management Section II Safety Evaluation Report Section 4.2 ANSWER H.07 (1.50)
*!
A.
a) Under moderated. )T' 3. f u/ b) Increasing moderator tedpe ature, decreases moderator density increasing Rasonance-decape-Probabi-1-ity (0.50) reducing the probability of fission. (0.50) REFERENCE Nuclear Physics Made Very Very Easy III.9 ANSWER H.08 (1.50) a) More rods will have to be withdrawn for the seconds startup, (0 25)due to the buildup of xenon in the core adding negative reactivity. (0.50) b) Rods will have to be inserted, (0.25) to compensate for the burnout and decay of xenon. (0.50) l (***** CATEGORY H CONTINUED ON NEXT PAGE *****) _ - _ _ _ _ _ -- . _ . _ _ -
,-. _- --
* * I o . ,
l 0 9 10 11 12 13 14 15 16 17 18 19 1.O 1.0 0.9 ,, 0.9 l O.8 O.8 0.7 - 0.7 1/M O.6 0.6 O.5 Nb O.5 O.4 O.4 O.3 -'N O.3 O.2 \N 0.2 O.1 O.1 O N O 8 9 10 11 12 13 14 15 16 17 18 19 ASSEMBLIES LOADED FIGURE 1 KEY l j
}
_ _ _ - _ - -- _ - - - - - - - -- - - - . _ - - - - - - - _ - - - - - - .- _ - - ___------_-----_----_-_----_--------_---_-J
- _ _ . _ _ - _ _ _ _ - _ - _ _ _ - _ _ _ _ _ - _ . _ _ _ _ - _ _ _ _ - - _ - _ _ _ _ _ _ - _ . _ _ _ _ - _ - - - _ _ _ _ _ _ _ - _ _ _ ..
5 ,H. 'bEACTOR THEORY Page 75 , , l .o
ANSWER H.09 (2.00) l No (0.50). ' Moving the fuel elements could significantly affect core excess reactivity,(0.50) due to a possible net change in the macroscopic cross
.section for the uranium. (0.50) Net fuel may have been shifted toward or away from regions of higher potential neutron flux. (0.50) : REFERENCE SUNY: OP No. 4, p. 5.
ANSWER H.10 (2. 00) Pressure = (Density) (height) =
(62.3 lb/ft cubed) (2 ft) (1.00)-
= 124.6 lb/ft squared = 0.87 psi (+/ . 01 psi)
(1.00)
REFERENCE SUNY: OP 81, -Containment Building Leak Test. Qual Card IV.10d, p. 6.
ANSWER H.11 (2.00) a) 1..The heat flux at, or just prior to Departure from Nucleate Boiling. .
(0.50)
2. The' formation of vapor bubbles on the cladding imperfections (nucleating points) as fuel cladding temperature increases past the convection heat transfer region. (0.50) b) A vapor film forms on the surface of the fuel cladding resulting in poor heat transfer (0.50) and less heat flux is transferred to the moderator as fuel cladding temperature increases. (0.50)
(***** CATEGORY H CONTINUED ON NEXT PAGE *****)
_ _ - - _ _ _ _ _ _ - _ _ _ __.
_ _ _ _ _ _ _ .
'
H.
, R$ ACTOR THEORY Page 76
-
REFERENCE Lamarsh, Introduction to Nuclear Engineering. Section 8.5 ANSWER H.12 (2.00) a) 4 (1.00) b) 2 (1.00) REFERENCE Nuclear Physics Made Very Very Easy p. III-14 (***** END OF CATEGORY H *****) - _ _ _ _ _ _ _ - - _ .
_ _ ._ . _ - _ _ _ _ _ _ a j.
' 46
lI.-
RADIOACTIVE MATERIALS HANDLING DISPOSAL Page 77 ,
. AND HAZARDS
'
,
k.
i ANSWER I.01 (2.00) G C.6
'(Il 1)2 = (I2).(di) 2 SAfr --
.
(0.50)
1 curie = .1 meter QL-
/hr a (0.50)
M g- .I
:Il = (I2) (d 2/(d1 = 6R hr'at 1 meter [C- C -(0.50)
bb h_ ~ i
[-l =1 '-
hr at 1 meter /ci = b K ies (0. 50) REFERENCE b 2.b (vAd/ Radiation Protection Manual.and Training Guide pg 54
, ANSWER I.02' (2.50)
6CE = R hr at one (1) foot (0.50) 6 X'7 X 2.5 = 105 R/hr at one (1) foot- (0.50) 100 mr in three (3) minutes = 2 R hr ,0.50).
(d2)2 =.1 X 105/2 = 52.5 square root of 52.5 = 7.25 feet from retriever (0.50)
.
REFERENCE Radiation Protection Manual and Training Guide pg 55 (***** CATEGORY I CONTINUED ON NEXT PAGE *****) _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ - .__
_ _ _ - - --_
..,
I. RADIOACTIVE' MATERIALS HANDLING DISPOSAL Page-78-AND HAZARDS
- ' ' ' ANSWER 'I.03' (l'. 2 5)
a) 1. 25 R ..(0. 25) L 3 R (0.25) with NRC' Form 4 not to exceed 5 (N-18). (0.25)_ b) 7.5 R (0.25).
3) 18.75 R (0.25)
. REFERENCE Radiation' Protection Manual and Training Guide pg 4 0
' ANSWER I.04 (1.50) Cd<~ n $2
'I = Io e Aux- -
g g[ [ h 4 (0.50)
.01 = Io e 9.37'x //h(C/~ (,2'[ M U N/ M (0.50)
in .010 = .937 x / 2.3/.937 = 2.45 R hr I (0.50)
'
REFERENCE
/ l C 't S Y ( ffdf/ 'SUNY Radiation Protection Manual and Training Guide pg,56 0y hf' dol.JGdf k34 (Cc' fft CMEW _
A. -= Z ~a 2 ' A y c (***** CATEGORY I CONTINUED ON NEXT PAGE *****)
- - _ - - _ - _ - _ _ _ - _ _ _ _ - _ _ _ - . _ _ _
_ _ _ _ _ _ - _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ . - _ _ _ _ _ _ _ _ _ _ _ _ _ -. _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ .
. _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ - . * '
I. RADIOACTIVE MATERIALS HANDLING DISPOSAL Page 79 AND HAZARDS
.
ANSWER I.05 (2.25) a) A small pocket carried device with a sensitive chamber which i is charged to zero prior to use. (0.25) Radiation passing through l the chamber dissipates the charge causing a needle to move upscale.
(0.25) The exposure can be read directly by the wearer by looking through the viewing window. (0.25) b) TLD's are small chips of Lithium or Calcium Fluoride encased in a holder. (0.25) The materials in the chips absorb energy from radiation, exciting the atoms to higher energy levels. (0.25) The chips are read by heating, releasing the energy as light which is proportional to the radiation absorbed. (0.25) c) The film badge is a packet of two different types of film, one for gamma and xray and the other for beta, enclosed in a case.
(0.25 exposure to radiation causes the file to turn black upon development.(0.25) The degree of film darkening is proportional to the amount of radiation exposure. (0.25) REFERENCE Radiation Protection Manual and Training Guide pgs 57, 58 ANSWER I.06 (1.50)
@
a) 0.5 mR/hr b) O mR/hr c) 50 mR/hr
.
d) 1.0 mR/h e) 200 /hr f) mR/hr (Six required at 0.25 ea)
(***** CATEGORY I CONTINUED ON NEXT PAGE *****)
- _ _ _ _ - _ _ _ _ _ _ _ _ .
. _ _ , - _ _ - _ _ - _ . . ' .I . '
RAT)IOACTIVE MATERIALS HANDLING DISPOSAL Page 80 AND HAZARDS
.
REFERENCE.
Radiation Protection Manual and Training Guide pg 60 ANSWER I.07 (1.00) a) Minimize the amount of radioactive material being handled.
b) Contain the radioactive material.
c) Follow established laboratory procedures.
(Two required at 0.50 ea)
/$ Mr% 84 WI&n vt { f M/ ,- .fs 6C
'
d'& # REFERENCE g ,jg ] 7[g g/ ,_ ggy jgg,/,9 m , Radiation Protection Manual and Training Guide ANSWER I.08 (1.00) C REFERENCE Radiation Protection Manual and Training Guide pgs 66, 67
.
I
l (***** CATEGORY I CONTINUED ON NEXT PAGE *****) i l _ _ _ _ _ _ _ _ . - - J
- - _ _ _ . - _ _ , _--_ . _ _ . __ _ - . _ -- _. -- . * , .I . '
RADIOACTIVE MATERIALS HANDLING DISPOSAL Page 81 AND HAZARDS
. . ANSWER' I.09 (1.50)
a) Perform radiation surveys to determine radiation levels, b) Determineuif material can be safely handled without' creating a hazard.
c) Use appropriate handling. tools and shielding.
d) Perform radiation and contamination surveys when work is completed.
(Three required at 0.50 ea)
REFERENCE Radiation Protection Manual and. Training Guide pg 70 ANSWER I.10 (1.00) b
. REFERENCE Radiation Protection Manual and Training-Guide pg 12
.
(***** CATEGORY I CONTINUED ON NEXT PAGE *****)
!
_
.
' '. I a - RADIOACTIVE MATERIALS HANDLING DISPOSAL Page 82 AND HAZARDS
.
ANSWER I.11 (2.00) a) I = Io e -lambdat (0.25) 70 = 100 e -lambda 6 In 70/100 = -lambda 6 lambda = .0595 (0.25) T 1/2 = .693/.0595 = 11.65 hours (+/ .5 hours) (0.50) b) (II) (dl) 2 = (I2) (d2)2 100 X 100 = 10,000 (0.25) 10/10,000 = e -0.595 t-6.91 = .0595 t (0.25) t = 116.1 hours (+/- 1 hour) (0.50) REFERENCE Radiation Protection Manual and Training Guide pgs 4, 5
.
i i l l
(***** CATEGORY I CONTINUED ON NEXT PAGE *****)
k
. . - = . . . _ . . . <-
r '
.' I . RADIOACTIVE MATERIALS HANDLING' DIS'OSAL P Page 83 .
AND HAZARDS
..
ANSWER I.12 (1.00)
- a) Beta decay-b) ' Positron decay c) Electron capture d) Alpha decay e) Nuclear Transition (Gamma Ray mmission)
(Four required at 25 ea)
Radiation Protection Manualiand' Training Guide pg ANSWER I.13 (1.50)
.a) GM tube cannot distinguish between radiation types or energies.and produces a count, or pulse, rather than an average current produced over~many reactions. (0.75)
b) If the Gamma or Xray energies are known, the GM. instrument can be calibrated to' measure the exposure rates in MREM / hour.(0.75) REFERENCE Radiation Protection Manual and Training Guide
.
,
.
(***** END OF CATEGORY I *****)
- _ _ = - _ _ - . - . _ - _ _ - - . _ _. .-
-- . ,.. 'i' l .J.
, SPECIFIC' OPERATING CHARACTERISTICS Page 84
.- -ANSWER J.01 (1.50)
a)- Simultaneous tripping of the bridge radiation-alarm (0.25) and-the
' building air radiation alarm.(0.25)
b) 1.- Containment fans'are shut off. (O.25) 2. Basement Stack Fan is shut off. (0.25) 3. Air Conditioning unit #1 is shut off. (0.25) 4.' Fume Hood Supply Fan is shut off. (0.25) REFERENCE OperatingLProcedure'OP 28, Containment Ventilation System- Section VI ANSWER J.02- (0.70) Introduces slack in the tong tape and cable system which could'cause the cable to' jump from the pulleys. (0.70) REFERENCE Operating Procedure 45, Hot Cell and Manipulators. pg 4
.
ANSWER. J.03 (1.00) For'a high residual Xenon concentration, no change in detector position should'be required. (0.50) For a low residual Xenon concentration, the detectors should'be lowered to the previously established low residual Xenon position. (0.50)
(***** CATEGORY J CONTINUED ON NEXT PAGE *****) .
. __-_-_-_-
_ _-_ _ _ _ . _ _ _ _ _ _ _
=,: < , - J.. SPECIFIC OPERATING CHARACTERISTICS Page 85 REFERENCE-Operating Procedure OP 5, Routine Startup Procedure, Startup for Full Power Operation. Section II.2 i
ANSWER J.04 (2.00) a) A 5 KVA natural gas fired motor generator automatically starts and supplies essential loads. (0.50) The emergency generator in the power plant can be used to supply the exhaust blower (booster fan) at the base of the stack. (0.50) b) 1. Fire alarm system.
2. Building exit signs.
3. Building evacuation alarm horn.
4. Radiation monitors for effluent streams, hot cell and the bridge.
5. Reactor Building intercommunications system.
(4 required at 0.25 ea) b. h of } l REFERENCE
,* u# 4 s4x dame SUNY Safety Evaluation Report. Section 8.2
.
l
)
1 (***** CATEGORY J CONTINUED ON NEXT PAGE *****)
!
__- _ __ ______- _. . _ . - _ - _ _
L i'
,
J, SPhCIFICOPERATINGCHARACTERISTICS Page 86
.
ANSWER J.05- (1.50) a) When the pump stops, gravity opens the flapper valve (0.25) allowing.
heat transfer from the core to the pool by natural convection. (0.25) b) The' purpose of the holdup tank, is to increase the transient time of the discharge water, (0.25) to allow Nitrogen 16 radioactivity to decay to an acceptable level before coolant is returned to the pool.
(0.25) c). The reactor pool temperature is maintained by a pneumatically operated bypass valve on the secondary side of the heat exchanger. (0.25) The valve is controlled.by a temperature sensor.on the primary coolant outlet of the heat exchanger. (0.25)- V ,, fgcc> tWby bk h# "" W REFERENCE MWN [ . SUNY Safety Evaluation Report. Section 5.1 ANSWER J.06 (1.75) ]
,
a) During reactor operation the building is maintained at 1/2 inch water gage negative pressure, (0.25 by an automatically adjusted damper in the building air fan inlet. (0.25) b) During accident conditions, the inlet and exhaust duct dampers close, (0.25) the two (2) normal exhaust blowers are shut down, (0.25) the damper in the emergency exhaust duct opens, (0.25). air flow through.
the exhaust duct is controlled by dampers (0.25) to maintain the reactor building at a negative pressure. (0.25) REFERENCE . SUNY Operating Procedure OP 28. Sections IV, V and VI (***** CATEGORY J CONTINUED ON NEXT PAGE *****) _ _ - _ - __- _ _ _ _ _-. _ - _ _
_ - _ - - _ _ - - _ _ _ .- _. . . _ e e
.J , - ShECIFIC OPERATING CHARACTERISTICS Page 87- .
J.07'
'
I ' ANSWER (1.00) a) The dashpots absorb the shock of f a control blades falling into the core on a scram, (0.25) and must be immersed in water to be effective. (0.25) b) If the rods were scramed with the dashpots not under water, serious damage to the blade and drive could occur. (0.50) REFERENCE SUNY Operating Procedure OP 23. Section II.C ANSWER- J.08 (0.75) NO. (0.25)' On failure of'the hydraulic pumps, system pressure is maintained by air bladders in the accumulators (0.25) for ten to fifteen minutes, allowing operation of the dampers during this period. (0.25) REFERENCE SUNY. Safety Evaluation Report. Section'9.3 ANSWER J.09 (1.50) a) Beta / gamma monitors. (0.50) . b) On the coolant exit line downstream of the holdup tank. (0.50) c) Eliminates the effect of Nitrogen 16 effect on the monitors.(0.50) i a
(***** CATEGORY J CONTINUED ON NEXT PAGE *****) =_-_______-___-__-____. _ _
_ - _ . ___ _ ._ . _ _ . - - _ -- - - - - - - - - - - - - . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - l
.. '.J. SPECIFIC OPERATING CHARACTERISTICS Page 83 .
REFERENCE
SUNY Safety Evaluation Report. Section 7.3 ANSWER J.10 (1.00) no. (0.25) The air compressor supplying the air locks, truck door and fume hoods, (0.25) or the compressor supplying the reactor building controls (0.25) could be cross connected to supply the flow instrument. (0.25) REFERENCE SUNY Safety Evaluation Report. Section 9.2
. (***** CATEGORY J CONTINUED ON NEXT PAGE *****)
_ _ - - _ _ _ _ - - _ _ . _ - . _
-__. __ .-
, 1 '.J. $PECIFIC OPERATING CHARACTERISTICS Page 89 .
ANSWER J.11 (2.30) a) Reverse (0.10) Scram (0.10) b) 110% (0.10) 120% (0.10) c) Indication (0.10) Inhibit (0.10) d) < 2 cps (0.10) > 9800 cps (0.10) e) Scram (0.10) f) Not Fully Closed (0.10) g) Indication (0.10) Scram (0.10) h) 68 1 ps (0.10) i) Scram (0.10) j) Open > 250 KWt (0.10) k) Low alarm (0.10) High alarm (0.10) scram (0.10) 1) 6.43 m above fuel (0.10) 6.74 m above fuel (0.10) 6.13 m above fuel (0.10) m) Scram (0.10) g/ M n) 52 deg C (0.10) REFERENCE SUNY Safety Evaluation Report, pg 7-4
.
;
I I i l
(***** CATEGORY J CONTINUED ON NEXT PAGE *****)
l l l _ _ _ _ - _ _ _ _ _ .
o J, 'ShECIFICOPERATINGCHARACTERISTICS' Page'90 rf ..
(2.00)- '
L ANSWER J.12-a) All five (5) Control Safety Blades are withdrawn simultaneously, b) No Protective action is taken until the high power scram terminates
.the excursion.
c) The maximum ~ withdrawal-rato is > .6 cm'(3 inches) per minute.
d)' All five (5) Control Safety Blades are at their maximum differential worth.
(Four required at 0.50.ea)
' REFERENCE SUNY Safety Evaluation Report pg 14-5 ANSWER . J .13 : (1.50)
. a) 250 b) Closed c) 1080 REFERENCE SUNY' Operating Precedure OP 21 Sections IV A, B, and C
. (***** CATEGORY J CONTINUED ON NEXT PAGE *****) - - - _ - _ _ _ _ _ _ _ _ -
- - _ _ - - - . - .. ',J. =S2DECIFIC OPERATING CHARACTERISTICS ,
Page 91
.
ANSWER J.14 (1.50) a) 5.0-7.5 b) Less than 5 umohs c) Greater than 200K ohms (75K ohms for less than 15 days)-
(Three required at 0.5 ea)
REFERENCE SUNY Operating Procedure OP 24 Section III
.
l (***** END OF CATEGORY J *****) - - - - _ - _ /
-_ _ _ _ -_--_ __ _ _ _ . . _ _ _ _ __ . _ _ _ _ _ _ _ _ _ . _ _ _ .
i'l ,
* .]. F5EL' HANDLING AND CORE PARAMETERS Page 92 .
ANSWER K.01 (0.75) Sample are. contained in a special crimp sealed aluminum can. (0.25) The can l-is inserted into a hollow. lead cylinder called a " sinker". (0.25) The ainker is suspended in the IF tube in the core. (0.25) REFERENCE, SUNY Operating Procedure OP 49. Section II ANSWER K.02 (2.50) a) The shutdown margin relative to the cold, Xenon-free critical condition (0.25) shall not be less than the total worth of the most reactive safety control blade, + 0.5% delta K/K (0.25) b) 1. Xenon override (0.25) for peak Xenon condition. (0.25) 2. Temperature coefficient (0.25) hot operating. (0.25) 3. Power defect (0.25) for two (2) MWt. (0.25) c) 5.2 delta K/K REFERENCE SUNY Technical Specification. Section 3.1 SUNY Safety Evaluation Report. Sections 4.7.3 and 4.7.4
.
ANSWER K.03 (1. 0 0 ) - a) Viewing with binoculars the two (2) inch high identifying number on the side of the box.
b) " Summing the notch values on the top of the box.
(Two required at 0.50 ea)
>
(***** CATEGORY K CONTINUED ON NEXT PAGE *****)
l _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ . . . . _ _ _ . _ __ _ a
__ -- ._ _ _ -. . _ _ - _ _ _ _ _ - _ _ _ _-_
'* .K. _
FUEL HANDLING AND CORE PARAMETERS Page 93
.
REFERENCE SUNY Operating Procedure OP 9. Section C ANSWER K.04 (1.00) a) The fuel immediately adjacent to the blade has been removed.
b) The Technical Specification shutdown margin has been met, (0.25) with the blade fully withdrawn. (0.25)
(Two required at 0.50 ea)
REFERENCE SUNY Operating Procedure OP 9. Section D ANSWER K.05 (1.50) If releases of the material could cause any of the following: a) Excessive corrosive attack on the reactor or the experimental facility.
b) Excessive contamination, or production of air borne radioactivity.
c) A violent chemical reaction.
(Three required at 0.50 ea) REFERENCE . SUNY Operating Procedure OP 41. Section IV.2 (***** CATEGORY K CONTINUED ON NEXT PAGE *****)
- - _ _ _ _ _.
.. _ __ _ _ . _ _ ._
. . , ~ -.
( K.- FdEL HANDLING'AND CORE' PARAMETERS Page-94 p.- l ... } ,
ANSWER K.06 (2.00)-- a) 0.3%- b)- two (2) MWt c) 0.3% d) 3.0% l -(Four required at 0.50 ea)
'
l REFERENCE iSUNY Operating Procedure OP 41. Section V.B.2
' ANSWER- .K.07 (1.00) ' Waterlogging'could occur when a small hole in the cladding. allows water to leak slowly.into the fuel. (0.50). This water could be turned rapidly: into : steam during.a. reactivity transient. (0.50)
REFERENCE SUNY Safety. Evaluation Report. Section 14.5
,
(***** CATEGORY K CONTINUED ON NEXT PAGE *****)
- _ _ _ _ _ - _ _ _ _ _ _ . _ _ . _ _ _ _ _ - _ _ _ - -
_ _ - _ - _ - _ _ _ _ _ _
_ _ _ - _ - - _ . _ _ _ _ _ _ _ _ _ . t.
, c K.- [NEL HANDLING AND CORE: PARAMETERS 'Page 95~
.
YANSWERf K.08 (2.50) a) Cold-fuel-is defined as fuel that can be stored in the fuel vault
'(0.25)'without reading a radiation field at the outer vault boundary of greater than (5) mrem /hr. (0.25)
b) The-fuel is stored in the fuel vault (0.25) in rows of metal i cylinders (0.25) with 12.7 cm (5 inches) between. cylinders-(0.25) and 40.6'cm-(16_ inches) between rows. (0.25) c) The fission plate:can be stored in the fuel vault, (0.25) in a locked cask in the containment, (0.25) in the dry chamber (0.25) or in the thermal column. .(0.25) REFERENCE SUNY Technical Specification 5.7.1 ANSUER' K.09 (1.00) a) In.the hot-cell (0.25) or in a specially fabricated shielded facility within the containment building. (0.25) b) 1. 0.85' 2. ' Flooded REFERENCE j SUNY Technical Specification. 5.7.2 . l l
(***** CATEGORY K CONTINUED ON NEXT PAGE *****)
-
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ e,.*'
'"
K.a [UEL HANDLING AND' CORE PARAMETERS Page 96 s
.
ANSWER K.10 (1.75) a) Oxygen 16 is struck by a neutron, resulting in a neutron proton reaction (n,p) producing Nitrogen 16. (0.50) Argon 40 absorbs a neutron and becomes Argon 41. (0.50) b) The beam ports are flooded, (0.25) ventilation is vented to the stack (0.25) and there is a holdup tank on the primary coolant discharge from the reactor. (0.25) REFERENCE SUNY Nuclear Physics Made Very Very Easy. pg II 23 Radiation Protection Manual and Training Guide. Chart of the Nuclides.
ANSWER K.11 (1.50)
.The-Technical Specifications would not allow the insertion of the 1 experiment-(0.25). The absolute value of all the experiments in the core would exceed the Technical Specification limit of 3% delta K/K. (1.00)
REFERENCE SUNY Technical Specification 3.1.2 ANSWER K.12 (2.00) a) On the gamma deck outside labs 103 and 104. (0.50) b) Indicating lights (0.25) and pens on a recorder (0.25) in the control room (0.25) c) NO. (0.25) A vacuum breaker in the line prevents siphoning the pool.
(0.50)
(***** CATEGORY K CONTINUED ON NEXT PAGE *****)
- _ _ - _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
_, . _-
. *
l
K.
..
, 'FSEL HANDLING.AND CORE PARAMETERS- Page 97'
i REFERENCE zSUNY' Operating Procedure OP 42. Section II l l ANSWER K.13 (1.50) L .
'
a) The beam tubes are " stepped" to prevent streaming. (0.50) b) The-beam tubes have shielded plugs installed to prevent high radiation at the te'minating e point. (0.50) c) The aluminum casing.around the concrete plugs has a rupture disk installed to prevent pressure buildup. (0.50) REFERENCE SUNY Operating Procedure
!
.
(***** END OF CATEGORY K *****)
_ _ _ _ _ _ _ _ - _ _ - _ _ _ _ _ __-_ __
F Lo' -l V
~ ~
L. . E AUMINISTRATIVt'. PROCEDURES, CONDITIONS Page 98
>AND LIMITATIONS t-I j. 1 ANSWER L.01- (1.00).
a. The locks'will be modified, (0.25) and new keys will be-issued (0.25)
-b. It will beLremoved electronically from the system (0.50)'
l
' REFERENCE
' SUNYLOperating. Procedure-OP.57 Section III.1 .<- ANSWER L.02 ( 1. 00 ), Whenever the reactor is operating (1.0) REFERENCE SUNY Technical Specifications, Section 6.1.1.5
--ANSWER L'.03 (2.00)
1. Fuel manipulations in the core, when there are 15 or more fuel assemblies on the grid plate.
2. inani experiments are being manipulated in the core, that have an estimated reactivity worth of greater than 0.6% delta k/k.
3. Removal of one or more control blades if there are 10 or more fuel assemblies on the grid plate 1 4. Removal.of shielding pluge; from the beam tunes 5. Resumption of operation following an unscheduled shutdown, unless the shutdown was a result of an interruption of electrical power to the facility.
(Four required at 0.50 ea)
(***** CATEGORY L CONTINUED ON NEXT PAGE *****)
- _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - ._
- _ _ _ _ -- _ _ _ - _ - - . - - - - - - - - - - - - --
- - --
- = -
+-
g.
. 8 LT .ALhINISTRATIVE PROCEDURES, CONDITIONS _Page:99 AND LIMITATIONS
~ '
r-L REFERENCE.
y :SUNYHTechnical' Specification 6.1.1.7 a l
. ANSWER L.04 (1.25)-
a..One year (0.50)
'b. All.new and revised Operating'. Procedures.must be reviewed'(0.25)iand approved (0.25) by the. operating committee '(0.25)
l- REFERENCE-
'SUNY Technical Specification 6.5 ANSWER :L. 05 - (1.50)
.b, c and f (0.50.ea)
'
REFERENCE SUNY; Technical Specifications Section 6.4
' ANSWER- L.06 (2.25)
I a. The. building fire alarm. . (0.25) A constant Kla.>on (horn) (0 25) for three minutes'(0.25) shuts off automatically (0.25) b. The building evacuation alarm (0.25) An intermittent Klaxon (born) .(0.25) which is turned off manually. (0.25).
c. PA. announcement (0.25) Manually secured after the announcement is made
'several times (0.25)
B (***** CATEGORY L CONTINUED ON NEXT PAGE *****)
- _ _ _ _ _ _ - _ - __-
_ __ . - - -- - _
- _ _ . . _ . - _ __
. . .
-- i , .c ;
L. ADMINISTRATIVE' PROCEDURES, CONDITIONS .Page100. ) XND LIMITATIONS
=.
i REFERENCE, j
. .
I I" .SUNY Emergency-Procedure EP #1, Staff General Emergency Procedure I Section IV.A ANSWER L.07 '( 2. 00) a. All personnel in the effected area shall stop work and restrict their
: movements to limit the spread of contamination, b. Advise personnel'outside of, but in close proximity to, the spill area, of the spill c. Confine the spilled material if possible -
d. If. airborne contamination-is suspected, evacuate the area e. One person from th area proceed to the closest location and call Health Physics s f. Person ~ notifying Health Physics, remain'at that location until consulted / monitored by Health. Physics.
(Four required at'O.50 each) REFERENCE SUNY Emergency Procedure EP 3,.High Level of-Radioactive' Surface Contamination . Section II
* j' t h ? m g j fy(( '
.
gyy,( ,/ Q:e j f[ ~ f f' ;/lr ac2 Y h o c l
@* ^ .l GL<* f/ ,
(***** CATEGORY L CONTINUED ON NEXT PAGE *****)
l l
.. < # .,9 L. ADMINISTRATIVE PROCEDURES,' CONDITIONS Page101 'nND LIMITATIONS .
l I ANSWER L.08- (1.75)
'
a. Back-up the flow scram. (Take the key) b. Turn'off the primary pump
'c. Turn off the secondary pump d.. Turn off;the demineralized pump.
c. Verify the plenum flapper valve is open f. Verify the' rods are seated g. Inspect the reactor core-
.h. Notify the Shift Supervisor or the SRO on call (Sevan required at 0.25 each)
REFERENCE SUNY Emergency Procedure EP #4, Reactor' Loss of Coolant Accident, Section IV.A ANSWER L.09 .(2.50) i n. 1. Recirculation of the tank through the filter and flow meter.
2. Recirculation of the tank bypassing the filter and flow meter 3. Discharge to the sanitary sewer through the filter and flow meter. , b. NO, not necessarily, (0.25) Increasing flow rapidly by starting the pump ' with the pump discharge valve open, can cause the flow meter to indicate zero (0.50) c. The pump suction for discharge is located one (1) foot above the bottom of the tank, which prevents pumping sludge. (0.50) Both bottom suction valve, and discharge suction valve are keylocked (0.25) with the operator allowed to have only one key at a time. (0.25)
l (***** CATEGORY L CONTINUED ON NEXT PAGE *****)
,.. . 1
_ _ _ - - .
;e L.1 ,A4MINISTRATIVE PROCEDURES, CONDITIONS :Page102 ...AND LIMITATIONS O
REFERENCE
- .
;SUNY Operating Procedure OP'31A, Section IV and VI ANSWER L.10 (1.50)
1. c
--3, -b47[bt%~
3. a 4. . a 5, b 6. a (Six required at 0.25 each) REFERENCE
:SUNY NSTF Emergency Plan Section 5.1 a
ANSWER L.11 (1.50) a. Facility Operations Committee yb. Nuclear Safety Committee
c. New York State Health Department
. (Three required at 0.50 each)
REFERENCE SUNY NSTF Emergency Plan Section 2 (***** CATEGORY L CONTINUED ON NEXT PAGE *****) _ -_ . - _ __ ___
- - - . --- - - _ - - _ - - _ - - - - _ - - - _ - - - - - - - - - - - - - - - - - . -. - - - - . --
t L. ' AlhINISTRATIVE PROCEDURES, CONDITIONS
-
Page103 AND LIMITATIONS l l l JANSWER._ L.12 (1.75) a. Selected from the-candidate list, in order of succession (0.25) The. Emergency Director will be the foremost person on the' list who is on site (0.25) , b. 1. Granting permission to exceed normal whole body radiation L exposure limits. (0.50) 2. Classification of the Emergency. (0.50) c. The Emergency Director .(0.25) REFERENCE SUNY NSTF Emergency Plan Section 3.1
.
(***** END OF CATEGORY L *****)
(********** END OF EXAMINATION **********)
f _ _ _ _ _ _ _ _ - - - - - - - _ _ _ _ _ - _ - . -_-
- _ -_ __ _ _ _ _ _ _ . . _ _ _ _ _ - _ _ - _ - - _ - - _ - . - _ ___,_ =.__-__ - _- .
_ . - - _ - - _ - _ ___ __- _ _
- . * ,' '
? .c ATTACHMENT 2 U. S '. NUCLEAR' REGULATORY COMMISSION " REACTOR OPERATOR LICENSE EXAMINATION
' REGION 1 FACILITY: State Univ. of N.Y.
REACTOR TYPE: PULSTAR DATE ADMINISTERED: 89/01/30 INSTRUCTIONS TO CANDIDATE:
'Use separate paper for the answers. Write answers on one side only.
' Staple question sheet on top of the answer sheets. Points for each' question are indicated in parentheses after the question. The passing grade requires at least 70% in each category. Examination papers will be picked up six (6) hours after the examination starts.
% OF CATEGORY % OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY 14.50 14.50 A. PRINCIPLES OF REACTOR OPERATION 14.50 14.50 B. FEATURES OF FACILITY DESIGN 15.00 15.00 C. GENERAL OPERATING CHARACTERISTICS 13.50 13.50 D. INSTRUMENTS-AND CONTROLS 13.50 _13.50 E. SAFETY AND EMERGENCY SYSTEMS 14.00 14.00 F. STANDARD AND EML'RGENCY OPERATING PROCEDURES 15.00 15.00 G. RADIATION CONTROL AND SAFETY 100.0 % TOTALS FINAL GRADE All work done on this examination is my own. I have neither given nor received aid.
Candidate's Signature '
- _ _ _ _ _ _ _ - _ _ - _ _ _ _ _ _ _ . . _ - - _ .
*
-A
_ _ _ _ _ -
. . . 1 '
NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS j
)
During the administration of this examination the following rules apply: ; 1. Cheating on the examination means an automatic denial of your application and could result in more severe penalties.
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 room to avoid even the appearance or possibility of cheating.
3. Use black ink or dark pencil only to facilitate legible reproductions.
4. Print your name in the blank provided on the cover sheet of the examination.
I 5. Fill in the date on the cover sheet of the examination (if necessary). ' 6. Use only the paper provided for answers.
7. Print your name in the upper right-hand corner of the first page of each section of the answer sheet.
8. Consecutively number each answer sheet, write "End of Category __" as appropriate, start each category on a new page, write only on one side of the paper, and write "Last Page" on the last answer sheet.
9. Number each answer as to category and number, for example, 1.4, 6.3.
10. Skip at least three lines between each answer.
11. Separate answer sheets from pad and place finished answer sheets face down on your desk or table. j 12. Use abbreviations only if they are commonly used in facility literature.
13. The point value for each question is indicated in parentheses after the question and can be used as a guide fcr the depth of answer requirea, 14. Show all calculations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or not.
15. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE 4' QUESTION AND DO NOT LEAVE ANY ANSWER BLANK.
16. If parts of the examination are not clear as to intent, ask questions of the examiner only.
17. You must sign the statement on the cover sheet that indicates that the work is your own and you have not received or been given assistance in l completing the examination. This must be done after the examination has j been completed.
l l t ! __
--- - - - ~ _ ._
- . , 'I- -18. When you' complete your examination, you shall:
a.- Assemble your examination as follows:
. (1) Exam questions on top.
(2)- Exam aids - figures, tables, etc.
-(3) Answer pages including figures which are part of the answer.
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.
.
.l .
. - - - - _ _ _ _ _ ____ __ _ ______.
.
'A. PRINCIPLES OF REACTOR OPERATION Page 4 . QUESTION- A.01 (3.00)
The graphs below indicate the concentration of xenon-135 for the given. power history.
a. Why.does the xenon concentration initially decrease after (1.0) the power' increase from 1 MW to 2 MW? b. Why does the xenon concentration increase so rapidly after the (1.0) reactor scram? c. If'there were enough excess reactivity in the core to startup the (1.0) reactor 12 hours after the scram, how would the. xenon concentration. change from that shown in_the graph, and how would-the xenon concentration effect the operation of the reactor during the startup? 2 MW + scram 1 MW : __._____+__________________ _______________________ t=0 hrs t=50 hrs-l
.
x? ' e. /) n o n c o n C.
________+-________________+_______________________ t=0 hrs t=50 hrs (***** CATEGORY A CONTINUED ON NEXT PAGE *****)
*
- _ - _ _ _ _ - _ _ - _ _ _ _ _ _
__-
. .
t A. PRINCIPLES OF REACTOR OPERATION Page 5 i QUESTION A.02 (3.00) j D3 fine Prompt neutrons and Delayed neutrons and state why delayed (3.00) nnutrons are so important to reactor operations.
)
(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
_ _ - _ _ _ _
-
._-____ - __-__ . .
A. ' PRINCIPLES OF REACTOR OPERATION page 6 QUESTION A.03 (1.00) In the space provided, draw what a trace from the linear recorder (1.0) would look like after a reactor scram from 100% power.
I l
(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
I l
~
_ _ _ _ _ _ _ _ _ _ __ _ _ - - - _ _
- - ., _
, ' i A.- PRINCIPLES:OF REACTOR OPERATION Page 7-
, l'
-Q ESTION- .A.04 (2. 00) . 'The' reactor is supercritical and on as 100 sec period.'If a (2.0)
5 degree F. increase in moderator temperature brings the reactor
.to a critical state, what is the moderator temperature coefficient of' reactivity in (delta k/k)/deg F?
Assume' beta =L0.0064-and lambda = 0.1/sec .
..
:i l
s I
(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
>
* l
F . i. . ! * A' . ' PRINCIPLES'OF REACi'OR OPERATION Page 8
/
l . i QUESTION A<.05 . (1.50) t.
l .The-fuel in a reactor is enriched with 352 grams of U- 5. Assuming no L
. fissions from.any other fuel and complete fissioning f all the U- 5, how much power (MWt)~would be produced by the fissio i of t -235? (given Avagadros # 6.023E23 atoms /gmole and 3.23E-1 Watt c / fission)
i i
:
\i i
!
l l l (***** CATEGORY A CONTINUED ON NEXT PAGE *****) ! l
*
I
- .. . - _ - _ _ -- .-- _ ._ - _ . .. .o ..'
A.<-PRINCIPLES OF REACTOR. OPERATION Page '9 k.
< i :- -QUESTION. A.06 ._(2. 00) The reactor is operating at one - (1) MWt steady state, when the Primary Coolant Pump'is shutdown.
Assuming:n'o: automatic or operator actions, what is the effect on
.the following:
a) Reactivity, relative to'the present'value. (Positive, Negative or,
,
lNo Effect) b) Metial-to-water- ratio. - (Increases, Decreases or Remain the Same).
I c). Average Thermal' Neutron Energy. (Increases, Decreases or-Remains the Same) d)' Resonance Escape Probability (Increases, Decreases, or Remains the Same)
)
.
?
'(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
-
- _ _ _ _ - _ - _ _ _ _ - - . - - . -
-_. ._
- - _ _ _ _ _ _ _ _ _ _ __ . _ _ _ .___
i
' +
t A. PRINCIPLES OF REACTOR OPERATION Page 10 QUESTION A.07 (2.00) To equalize fuel burnup, fuel assemblies are shuffled to move some of the peripheral assemblies to the center of the core and the central assemblies to the periphery. Assuming that only original fuel elements remain in the core, and no net fuel addition or subtraction took place, WOULD it be safe to assume that no change in core excess reactivity took place? EXPLAIN.
I l l l l (***** END OF CATEGORY A *****) I l I -
.
.- _.
. _ - -
. .,.
- B. FEATURES OF FACILITY DESIGN Page 11
.
1
1 (***** CATEGORY B CONTINUED ON NEXT PAGE *****)
.
____
. '
l B. FEATURES OF FACILITY DESIGN Page 12 QUESTION B.01 (2.50) Emergency Power is supplied by a 5 KW natural gas generator (2.5) for the reactor facility. List five (5) of the six (6) loads which are powered by this generator during a loss of power.
I (***** CATEGORY B CONTINUED ON NEXT PAGE *****)
~
- _ _ _ _ _ _ _ _ - _ _ _ _ _ - _ _ _ _ -_ _
_ - _ . - - - _ - _ _ _ - _ _ _ -
,
i a f . B. FEATURES OF FACILITY DESIGN Page 13 1 i QUESTION B.02 (2.00) I a What are the four (4) Safety Limits in the Forced Convection Mode? (2.0) f (***** CATEGORY B CONTINUED ON NEXT PAGE *****)
.
-. - . *
B. FEATURES OF FACILITY DESIGN Page 14 QUESTION B.03 (1.00) Explain how a Plutonium Berillium source produces neutrons. (1.0) s (***** CATEGORY B CONTINUED ON NEXT PAGE *****)
-
- _ _ _ _ - _ . - _
_______________,
"
l
*
l
*
B. FEATURES OF FACILITY DESIGN Page 15 I l QUESTION B.04 (1.00) l l With the reactor shutdown, an experiment is to be run in the hot cell (1.0) which requires placing the experiment in the hot cell's gamma facility.
a. What is the source for the gammas for the gamma facility? b. Where is the gamma source located?
.
(***** CATEGORY B CONTINUED ON NEXT PAGE *****)
-
_ _ _ _ _ _
. _ _ - _ _ _ - - . . 'B.
FEATURES OF FACILITY DESIGli Page 16 QUESTION B.05 (1.00) Nitrogen-16 is produced during normal operations. Will the primary (1.0) coolant radiation monitor respond to the radiation from N-16? Why, or Why not? l
i
!
l (***** CATEGORY B CONTINUED ON NEXT PAGE *****)
*
_ _ _ _ _ - _ _ _ _ _ _ _ _
_ _ _ _ _ _ _ - _
, '
B. FEATURES OF FACILITY DESIGN Page 17 QUESTION B.06 (1.50) STATE the three (3) conditions given in Technical Specifications (1.5) Definitions that constitute " Reactor Operations" l l
i l l l i
^
,
(***** CATEGORY B CONTINUED ON NEXT PAGE *****)
-
_ _ _ -
__ _ ; _ _
. ' 'B . FEATURES OF FACILITY DESIGN Page 18 QUESTION B.07 (1.00)
When incorporating an experiment of large negative orth into the (1.0) core, should adjustments in K excess be made with he experiment LOADED or UNLOADED? EXPLAIN.
. f
\
[
f f
\
e (***** CATEGORY B CONTINUED ON NEXT PAGE *****)
-
- - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -
_ _ - _ _ _
.
,
*'B. FEATURES OF FACILITY DESIGN Page 19 QUESTION B.08 (1.50)
What is the Limiting Condition for Operation (LCO) for the reactor (1.5) Shutdown Margin? I i
:
i I l l
! (***** CATEGORY B CONTINUED ON NEXT PAGE *****)
l __
-
l
._ __ _ _ . _ - _ _ _ _ _ _ _ _ _ _ _ _ _ , .
' B. ' FEATURES'OF FACILITY DESIGN Page 20
.
QUESTION. B.09 (1.50) The physical' design of the-beam tubes minimizes the effects of gamma and neutron radiation.
a) What physical design prevents / minimizes streaming? (0.5) b) What prevents high radiation levels in the area where the tubes terminate? (0.5) c) What feature prevents plugs from failure due.to pressure build-up? (0.5)
(***** CATEGORY B CONTINUED ON NEXT PAGE *****)
-
_ _ --._____ __-_.
- __
. '
N. FEATURES OF FACILITY DESIGN Page 21 j
!
QUESTION B.10 (1.50) Answer the following questions concerning the Primary Cooling Subsystem. I l a) How is heat removal from the core maintained if the primary coolant pump stops? (0.5) b) What is the purpose of the holdup tank on the discharge of the outlet plenum? (0.5) c) How is the reactor pool temperature maintained during reactor operation? (0.5)
. (***** END OF CATEGORY B *****)
_ . _ . . . . _ _ _ _ _ _ _______i______-.________-.__ _ _______ .__ _ ___
- - - - .
. '
U ~ GENERAL OPERATING C9ARACTERISTICS Page 22
.
(***** CATEGORY C CONTINUED ON NEXT PAGE *****)
.
_;--
.
U. GENERAL OPERATING CHARACTERISTICS Page 23 QUESTION C.01 (2.00) a. State two ways that it would be known that the resins in the (1.0) domineralizer in the purification system become depleted? b. What would be the effects of operating for a long period of time (1.0) with depleted resins? l s l (***** CATEGORY C CONTINUED ON NEXT PAGE *****) . - _ _ - - _ _ - _ _ _ _ _ _ _ _ - _ _ _ _ _ _ . __ _ _ _ __ _ _ .- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ __n
.. . , , .
- - _ _ ._ _ _ _ - - _ _ _ - _ _ _ _ - _ - - _ - _ _ - - _ _ _ _ - - _ _ _ _ _ - -
. . .
C. * GENERAL OPERATING. CHARACTERISTICS- Page 24 l
. QUESTION .C.02 (3.00)
Technical' Specifications lists five (5) operation that must be (3.0)
.cupervised.by.a senior reactor. operator. List three (3) of these five'(5) operations.
,
.,_
(***** CATEGORY C CONTINUED ON NEXT PAGE *****)
*
- _ _ - _ - _ _ _ _ _ _ _ _ - _ _ _ _ _
___,__________.__
. . e .p. GENERAL OPERATING CHARACTERISTICS Page 25 i ' QUESTION 'C.03 (1.00)
I l Two'(2) secured experiments are now in the core. The first secured (1.0) l experiment has a reactivity ofL-1.3 delta'k/k. The second secured experiment has a reactivity.of +1.2 delta k/k. There is also an ] i unsecured! experiment in the reactor with a reactivity worth of {
-0.4 delta k/k. Would Technical Specifications allow the insertion J of an experiment using the rabbit system if.the experiment had 1 a reactivity of.-0.2 delta k/k?
'Why, or why not?.
!
l
)
I J l l
(***** CATEGORY C CONTINUED ON NEXT PAGE *****)
,
- _ _ - _ _ _ _ _ _ - _ _ - _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ._. ._ l
_. . _ _ _ - _ _ _ - - _ _ -
.
d. GENERAL OPERATING CHARACTERISTICS Page 26 I
i
I QUESTION C.04 (2.00) , Draw a. typical differential control rod worth curve and EXPLAIN (2.0) THE SHAPE OF THE CURVE. (Make sure you label your axes.)
(***** CATEGORY C CONTINUED ON NEXT PAGE *****) l L _ _ _ ---
. _ . ,_ . '
C. GENERAL OPERATING' CHARACTERISTICS Page 27 QUESTION C.05 (1.50) How is Nitrogen-16 produced in your reactor? What does Nitrogen-16 (1.5) decay into? What is the half-life of Nitrogen-16?
(***** CATEGORY C CONTINUED ON NEXT PAGE *****) I
_ - _ _ _ _ . _
___, , _
) -
1 d.
' GENERAL OPERATING CHARACTERISTICS Page 28 l QUESTION C.06 (1.50) j l How much highly enriched Uranium-235 may the fission plate contain? (1.5)
'
Why is the fission plate limited to use only on the outside face of the thermal column? _
(***** CATEGORY C CONTINUED ON NEXT PAGE *****)
~
- _ _ - _ - _ _ _ __ __ -
.,__________________________.
_
.. *
d. GENERAL OPERATING CHARACTERISTICS Page 29
)
QUESTION C.07 (2.50) a. Briefly DESCRIBE control rod worth calibration by the Inhour (2.0) method.
b. WHY must the calibration be performed at low power? (0.5)
( * * * * * C:ATEGORY C CONTINUED ON NEXT PAGE *****)
- _ - _ - _ _
_ , - - - - _ . _ __ ._
, - ,
p *"d. GENERAL OPERATING CHARACTERISTICS page 30 l.
!
" '. QUESTION C.08 -(1.50)
- .-
'~
: LIST the chemistry limits.for the following:
a).. Pool' Ph
:b) Pool conductivity c) Demineralized Effluent Resistivity
,
.
l
-
(***** END OF CATEGORY C *****) 1
' i
_ - - _ _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _
___7.._..
- _ _ _ _ _ _ _ _ _ _ _ _
_,
.
'
. D. INSTRUMENTS AND CONTROLS Page 31
!
,
i
!
t
'
(***** CATEGORY D CONTINUED ON NEXT PAGE *****)
I
.
y____.__ _ _ i
' l
*
6. INSTRUMENTS.AND CONTROLS Page 32 l l l l l QUESTION D.01 (2.00) 1 According to Technical Specifications, WHAT is the difference (2.0) b tween a FAST scram and a SLOW scram?
(***** CATEGORY D CONTINUED ON NEXT PAGE *****)
u_______ _ _ _ _ _ _ ___
-
- _ _ - . . ' d. INSTRUMENTS AND CONTROLS Page 33 i
I 1 QUESTION D.02 (1.50) What is inhibited when the startup channel countrate drops below (1.5) 2. counts per second? WHY? l l
(***** CATEGORY D CONTINUED ON NEXT PAGE *****)
-
- _.
u _ _ _ _ _ _ _ _ _ _ _ _ _ l b. INSTRUMENTS AND CONTROLS Page 34 QUESTION D.03 (3.00) What are the three (3) neutron absorbing metals used in the (3.0) control rods, and what type of neutron (energy level) will cach material absorb best? I (***** CATEGORY D CONTINUED ON NEXT PAGE *****) - _ - _ _ _ _ _ _ _ _ ._ ___ - _
.
, _ - _ _ _ _ _ _ _ _ _ , '
b. INSTRUMENTS AND CONTROLS Page 35 l l QUESTION D.04 (1.50) Explain how gamma radiation is " compensated" out of the entire (1.5) incident radiation field in a compensated ion chamber.
!
(***** CATEGORY D CONTINUED ON NEXT PAGE *****)
*
- _ _ _ _ - _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ . _ _ _
_ - _ _ _ _ - _ - _ - - _ _ _ _ _ _
,* . < ' '!6. ' INSTRUMENTS ' AND CONTROLS- Page 36 l ,
QUESTION. D.05 (3. 00) . STATE the five (5) - types. of instrumentation ! used to monitor, (3.0) control, and automatically shutdown the reactor.-Also STATE the' function (s) that each type of instrumentation provides.
,
.
(***** CATEGORY D CONTINUED ON NEXT PAGE *****)
- _ _ - - - - - _ - , _ =_____ _ -_-_ . - _ _ _ _ _ - _
__ -.
. J
6. INSTRUMENTS AND CONTROLS Page 37 I
' QUESTION D.06 (2.50) j
'
a. How many compressed air subsystems are there at SUNYAB NSTF? (0.5) b. List all of the loads supplied by each subsystem. (2.0) l l
.
(***** END OF CATEGORY D *****)
.
- - - _ _ _ . _ _ . . _ _ _ _ _ _
.__._.y.
!
. *
5. SAFETY AND EMERGENCY SYSTEMS Page 38 l
!
s l I l l (***** CATEGORY E CONTINUED ON NEXT PAGE *****) I
!
l
~
- - _ _ _ _ _ _ - - _ _ _ _ . __
\
_ _ _ _ _ .
. . .. $. SAFETY AND EMERGENCY SYSTEMS Page 39 QUESTION E.01 (2.00)
Technical Specifications list three (3) criteria for determining (2.0) whether or not experiments should be doubley encapsulated. STATE two (2) of these three (3) criteria.
l (***** CATEGORY E CONTINUED ON NEXT PAGE *****) _ _ - _ _ _ _ _ _ _
. - - -__ _______ _ _ . $. SAFETY AND EMERGENCY SYSTEMS Page 40 QUESTION E.02 (2.50)
According to EP #5 (Reactor Fuel Failure Accident), what are (2.5) five (5) of the six (6) indications used to verify failed fuel?
,
l (***** CATEGORY E CONTINUED ON NEXT PAGE *****) ! l l t i
- ,_ _ - . - _ _ _ _ . _ _ _ _ - _ _ _ _ _ _ . _ - _ _ _ - _ _ _ _ _ _ - _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _
. $. SAFETY AND EMERGENCY SYSTEMS Page 41 QUESTION E.03 (3.00)
List six (6) of the seven (7) scrams which must be operable in (3.0) order to increase power above 250 KW.
(Include Setpoints where applicable) l l
'i i
i ) l d l
l l l l l
.
i l
(***** *****)
'
CATEGORY E CONTINUED ON NEXT PAGE ! l
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ ._.
. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -
"
S. SAFETY AND EMERGENCY SYSTEMS Page 42 QUESTION E.04 (2.00) The ion chamber channels for neutron monitoring are calibrated (2.0) as required to maintain true power indication. What two(2) methods may be used to determine true power for these calibrations? Why are these true power indications used? l
i (***** CATEGORY E CONTINUED ON NEXT PAGE *****) _ _ _ _ _ _ - _ - _ - _ - . _.
_ _ _ _ _ _ _ _
'
'
$. SAFETY'AND EMERGENCY SYSTEMS Page 43 QUESTION E.05 (1.00)
i What signals will cause the Reactor Building Ventilation Dampers (1.0) to automatically close? i
! (***** CATEGORY E CONTINUED ON NEXT PAGE *****)
_ _ _ _ _ _ - . _
, _ , _ , ' E. SAFETY AND EMERGENCY SYSTEMS Page 44 E.06 (3.00) '
QUESTION Label the six (6) components of the secondary cooling system (3.0) in the attached drawing.
i ! I '
(***** END OF CATEGORY E *****)
.
L__------___---.____ _
-
..y-. - _ . - - - - - - - - - - . _ _ . - - - _ _ _ .
e 0.. g
~g 's
. .
. - - -
.
i __ a I 1 3
- .
b I42
. @ -I . =
_ w
: A [ . A = *
2 = g ( 31.'2 k _ 3 e _
-
I :
.. a ~
l... . A e A :
-
.
.
% 'T JL
- - -
e m
1.[_ s To J it _-
-
.
ap - -
&
- ,
u c u a - *
-
3 f" * :o c > n f o s * u a b L e i w #5 d D
;, c
! "
e, . m.
L \/ v y
.
--
21/\ a 1 --; e ~
n a i e u
'M#r=== - Q
,O e
f~- 2 w n 7
-
<
c 4. , _ $_z a , Ipc 3 f
,,7 O) Eg *
~
. 1
~ n
~
\
.
C9 SUNYAB SER 5-4 i
.
x-- q 1 -!
, - P. STANDARD AND' EMERGENCY OPERATING PROCEDURES page 45 I
1 l l l
; (***** CATEGORY F CONTINUED ON NEXT PAGE *****) , - - - - - _ - - - - _ - _ _
-. . _ . . _ _ _ _ _ _ _ _ _ _ _ _ * .
' . F. STANDARD AND EMERGENCY OPERATING PROCEDURES Page 46 I l QUESTION F.01 (1.50) List three (3) of the four (4) chemical elements that would (1.5) comprise the majority of fission products released from the fuel as a result of a fuel leak.
.
(***** CATEGORY F CONTINUED ON NEXT PAGE *****)
_ _ _ _ _ - _ _ _ _ _ _ _
. . . . - _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ - _ _ _ - _ _ _ _ - -
ei F.
' STANDARD'AND EMERGENCY OPERATING PROCEDURES- Page.47: l QUESTION F. 02' (O.50)- During an emergency, if the facility.must be evacuated, whose (0.5) permission is required in order for an individual to exceed the normal whole body radiation exposure limits.
! <
(***** CATEGORY F CONTINUED ON NEXT PAGE *****)
'
- - - _ _ _ _ _ - _ _ - _
- - ____ . _ _ _ _ _ ,
. '
h. STANDARD AND EMERGENCY OPERATING PROCEDURES Page 48 l I i QUESTION F.03 (2.00) 1 According to the Emergency Plan, during an emergency which requires (2.0)
'the evacuation of the facility, what are the four (4) responsibilities of the Reactor Operator?
i
\
l (***** CATEGORY F CONTINUED ON NEXT PAGE *****) _ _ _ _ _ _ _ _ _ _ _ _ _
_ _ _ - _
-
,
l * I I -N. STANDARD AND EMERGENCY OPERATING PROCEDURES Page 49 i l l QUESTION F.04 (1.50) The Reactor facility has been evacuated, and the Emergency (1.5) Director has directed you to set up two (2) zones for radiological control in accordance with the Emergency Plan.
c. What are the names of these two zones? l b. Where are the detectors, used to perform surveys of these l two zones, located?
.
_
l (***** CATEGORY F CONTINUED ON NEXT PAGE *****) j
l
- _ _ _ _ _ - - _ _ _ _ l
. _ _ _ _ _ _ _ _ _ _ _ _ - _ _ .
_
;.
. 'l c; . =
'7 ' F . - STANDARD AND EMERGENCY OPERATING P.iOCEDURES Page '50-
-g (){
TQUESTION- F.05' (1.50) l According'to OP #6, if a. Scram signal is' received, what' actions- ~(1.0)-
'chould the. operator take? (2 required) .When should the Scram signal'be-reset? '(0.5)
f-( * * * * * CA'I'EGORY F CONTINUED ON NEXT PAGE *****)
-
_ _ _ _ _ _ _ _ _ .
.. _ _ _ - __ - _ _ _ _ .
*
,
l h. STANDARD AND EMERGENCY OPERATING PROCEDURES Page 51 QUESTION F.06 (3.00) List three (3) of the six (6) conditions which must be met for the (2.5) R actor Containment Building before reactor operation is allowed.
l l
; (***** CATEGORY F CONTINUED ON NEXT PAGE *****) ]
l l w __- _ _-_ _ b
_ _ _ _ _ _ _ _ _
.
h. STANDARD AND EMERGENCY OPERATING PROCEDURES Page 52 i QUESTION F.07 (2.00) What are the minimum staffing requirements for both the control (2.0) room and the facility when the reactor is operating? What restriction is placed on the person (s) in the facility who are fulfilling these personnel requirements?
(***** CATEGORY F CONTINUED ON NEXT PAGE *****)
i , _ _ _ _ _ _ _ _ _
.. . _ _ _ _ _ _ _ <
J- [. STANDARD'AND' EMERGENCY OPERATING PROCEDURES Page 53- ,. .
-QUESTION F.08 '(2.00)
'
t;.: lD3 fine.in accordance with Technical Specifications ct.' Reactor Secured . ( l'. 0 ) ,
. b. Reactor Shutdown' (1.0)
..
.
..
I (***** END OF CATEGORY F *****) ' '
. _ _ _ _ . _ - _ -. . _ .1
, - _ - - - _
.
:
i' G- RADIATION CONTROL AND SAFETY Page 54 ! l j i l
!
i
,
i I
!
!
-
I (***** CATEGORY G CONTINUED ON NEXT PAGE *****) __ _ - _ _ _
_ _ - _ _ _ - - - _ - - _ _ _ _ _ - . - _ . _ _ _ .
...
4'
.,
'G.--RADIATION CONTROL AND SAFETY Page 55 QUESTION- ~ G.01.
.
(2.00)'
!
You have a. survey meter with a 5% efficiency for 500 kev gammas. (2.0) Your background reading is 800 counts in a 15 minute. period.
.What is the minimum source of 500 kev gammas you could detect
.with this instrument in the given background?
(***** CATEGORY G CONTINUED ON NEXT PAGE *****)
~
_ - _ _ _ _ - _ _ _ _ _ _ - _ - _ _ - - _ - _
_ _ , _ .
. < . *
G. RADIATION CONTROL AND SAFETY Page 56 QUESTION G.02 (2.50) The Half Value Layer (HVL) of lead for gammas produced by Iodine-131 (2.5) is 0.178 cm. How much lead shielding would be required to reduce the intensity of radiation from a collimated Iodine-131 source from 10 mr/hr to 2 mr/hr?
; (***** CATEGORY G CONTINUED ON NEXT PAGE *****)
_ _ _ _ _ _ _ _ _ _ _ _ - -
. _ - .
a e
, *
i l G. RADIATION CONTROL AND SAFETY Page 57
.
i QUESTION G.03 (1.50) What are the three primary methods of reducing the hazard of (1.5) cxternal radiation?
!
I i i i l (***** CATEGORY G CONTINUED ON NEXT PAGE *****)
'
_ _ _ - _ _ _ _ _ _
- - - - - . . . - - _ < . - . -- _- . _ . . - _ - _ ._ -- .- . . - - _ - _ _ _-- - ,_ -mm. - ..*: . . . .o.'o .. .. -G; RADIATION CONTROL AND' SAFETY.- Page-58
- "? QUESTION .G.04'. '(2.00) .Wh'at..is your-combined dose (in mrem) if-you were exposed to the -(2.0)
following amounts of radiation? 20 mrad of' gamma radiation ,
.{'
5 mrad of slow neutron radiation 2 mrad of' alpha' radiation 1' l 1, l
.
f i
(***** CATEGORY G CONTINUED ON NEXT PAGE *****) ]
l i
,
*
c--___-_____ - _ _ _ _ _ _
-- _ _ _ _ - - - , _ - - - - _ -
:, ,.. . , . ' ' ,$ . -:G'. ' RADIATION CONTROL AND SAFETY Page 59' . QUESTION' G.05- (2.50)-
During full power-operation, a fuel pin fails and releases. (2.5)
-soveral curies of radioactivity into the pool water. Assuming .
that this contamination was restricted to liquid form, WHAT systems (subsystems) are in place to warn or protect the '; reactor staff and general public from radiation-dangers? Itve required for full credit.
(***** CATEGORY G CONTINUED ON NEXT PAGE *****)
' - _ _ _ _ - _ _ _ - _ - _ - _ _ _ - _ - - _ -
- - - _ - _ _ - - _ _ _ _ _ _ _ _ _ _ - _ _ _ __ ._ -_ - _ . . -
- _ - . - - - - - . - - - . .
, . . 'O
' ~
=.. G . - RADIATION CONTROL AND SAFETY Page 60-l
.
L-QUESTION G.06 (2.00) 1.-What are the Federal limits for radiation workers-for quarterly average exposure to-a. whol'e body b. skin c. extremities
'2.~What is the quarterly maximum whole body dose?
!
!
l
't-i l
!
!
!
j i
~
,
i j l i i l l (***** CATEGORY G CONTINUED ON NEXT PAGE *****)
-
_--__1__ _----____ _
- _ _ , _ _ _ . - - _ _ _ _ _ - _ - _ _ - _ - _ _ _ _ - _ _ _ _ - _ _ - - _ _ _ _ _ - _ _ _ _ _ _ - _ _ _ - _ _ _ _ _ _ . _ . _ _ _ _ _ - _ - _ - _ _ _ - - . : ,- . ,f. Q ;:
G. RADIATION CONTROL AND SAFETY Page 61 QUESTION G.07 (2.50) a. According to OP #26C (Continuous Air Monitors), if one CAM alarms (1.0) with no increase in effluent monitor response and no increase in the other CAMS, how should you verify the CAM system operation? b. If your first action.results in a decreased monitor. response, (1.5) what actions should be performed? .g i J l
(***** END OF CATEGORY G *****)
(********** END OF EXAMINATION **********)
!
.
F :. [
., ,3 EQUATION SHEET f = ma , y= s/t v = mg s = v,t + hat 2 Cycle efficiency = Net g Work (out)
E = mC a = (vf - yo )/t KE = my 2 -At v f=v o+ at A = AN A = A,e PE'= mgh w - e/t W = v4P A = in 2/tg = 0.693/tg AE = 931Am- . e(,ff) h
, Di;Mtd Q=[nC6T (tg+t)b 'Q = UA6T p
I . I e-IX I Ie UX P w r = W ' In f I.I O lo-X/ M y.p to SUR(t) TVL = 1.3/p p.p t e /T o HVL = 0.693/u SUR = 26.06/T T = 1.44 DT
. /A e o)
SCR = S/(1 - K,ff) ' SUR = 26 g CR x = S/(1 - K,ggg) T = '(1*/o ) + [(6 'o)/A,ffo ] 1
~
eff 1 " 2 0O T eff 2 7 . g*f (, _ g H = 1/(1 - K,gg) = cR /CR g 0 I"I ~ P)! eff D
0 " (Eeff M = (1 - K,ff)0 (l ~ eff)1-1) eff " A eff effl SDM = (1 'K,ff)/Keff % # ~ #bff p= ~
[1*/TKyff.] + [E/(1 + 1,ggT )] t* = 1 x 10 seconds
% P = I4V/(3 x 10 0)
'
~
A,ff ? 0.1 seconds I = Na Idl f =_ I d22
'
WATER PARAMETERS Id g =Id22 1 gal. = 8.345 lbm 2 1 gal. - 3.78 liters R/hr = (0.5 CE)/d (meters) ' R/hr = 6 CE/d (feet) 1ft = 7.48 gal.
MISCELLANEOUS CONVERSIONS Density = 62.4 lbm/ft 1 Curic = 3.7 x 10 Odps Density - 1 gm/cm 3 1 kg = 2.21 lbm Heat of valori:ution = 970 Itu/lbm
'
I hp - 2.54 x 103 BTU /hr Heat of fusica = 144 Btu /lbm 1 Hw - 3.41 x 100 Btu /hr 1 Atm = 14.7 Psi = 29.9 in. I'g.
1 BLu = 778 f t-lbf 1 ft. HO=0.4335lbf/in 2 1' inch = 2.54 cm T = 9/5 C + 32
"C = 5/9 ( T - 32) -
_ _ - -
. . . . . . _ ,n U. S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION REGION 1 FACILITY: State Univ. of N.Y.
' REACTOR TYPE: PULSTAR DATE ADMINISTERED: 89/01/30 INSTRUCTIONS TO CANDIDATE: Use separate paper for the answers. Write answers on one side only.
Staple question sheet on top of the answer sheets. Points for each question are indicated in parentheses after the question. The passing grade requires at least 70% in each category. Examination papers will be picked up six (6) hours after the examination starts.
% OF CATEGORY % OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY 14.50 14.50 A. PRINCIPLES OF REACTOR OPERATION 14.50 14.50 B. FEATURES OF FACILITY DESIGN 15.00 15.00 C. GENERAL OPERATING CHARACTERISTICS 13.50 13.50 D. INSTRUMENTS AND CONTROLS 13.50 13.50 E. SAFETY AND EMERGENCY SYSTEMS 14.00 14.00 F. STANDARD AND EMERGENCY OPERATING PROCEDURES 15.00 15.00 G. RADIATION CONTROL AND SAFETY e 100.0 % TOTALS FINAL GRADE All work done on this examination is my own. I have neither given nor received aid.
Candidate's Signature
_ _ - _ _ - _ . - - _ _ _ _ _ _ --- . _ _ _ _ _ _ _ _
, ,l ? ' , , . . :u 6 4,- *
U. S. NUCLEAR REGULATORY COMMISSION REACTOR' OPERATOR LICENSE EXAMINATION REGION 1 1
!
FACILITY: State Univ. of N.Y.. REACTOR TYPE:- PULSTAR DATE ADMINISTERED: 89/01/30 INSTRUCTIONS TO CANDIDATE: Use separate. paper for the answers. Write answers on one side'only.
Staple question sheet on top of the answer sheets. Points for each
. question are indicated in parentheses after the question. The passing . grade requires at least 70% in each category. Examination papers will be picked up six (6) hours- after the examination starts.
% OF CATEGORY _ % OF ' CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY 14.50 14.50 A. PRINCIPLES OF REACTOR OPERATION 14.50 14.50 B. FEATURES OF FACILITY DESIGN 15.00 15.00 C. GENERAL OPERATING CHARACTERISTICS 13.50 13.50 D. INSTRUMENTS AND CONTROLS 13.50 13.50 E. SAFETY AND EMERGENCY SYSTEMS 14.00. , 14.00 F. STANDARD AND EMERGENCY OPERATING PROCEDURES 15.00 15.00 G. RADIATION CONTROL AND SAFETY e-100.0 % TOTALS FINAL GRADE
-
!
All work done on this examination is my own. I have neither given nor received aid.
i Candidate's Signature l
~ - _ __- _ _ _- - _ - - .
. . _ _ . - - - _ . - _. - _ . _ . - _.
_ _ _ _ _ _ _ - _ _ - _ _ _ _ _ _ _ _ _ _ _ _
* , js i ' 9 A. PRINCIPLES OF REACTOR _ OPERATION Page 61 -
i l
;
ANSWER A.01 (3.00) c. The xenon concentration initially decreases after the power increase due to the increased thermal neutron flux burning out the xenon at a higher rate,(0.5) but xenon is still being .
produced at:the equilibrium rate for 1 MW, due to the half-life of the iodine isotope which decays to xenon-135 (0.5) i b. The xenon concentration increases rapidly after a reactor scram because the thermal flux has decreased to a very small value.
Therefore, there is not much removal of xenon due to neutron
.absorbtion. (0.5) But the xenon is still being produced at the full power equilibrium rate due to the half-life of the iodine isotope which decays to xenon-135 (0.5)
c. The xenon concentration would decrease more rapidly than shown on the graph if~a startup were done 12 hours after the scram. (0.5) Because the xenon is decaying very rapidly, it will be adding positive reactivity rapidly, so it will make the reactor less stable during the startup. (0.5) REFERENCE Lamarsh," Introduction to Nuclear Engineering" pp. 287-289 ANSWER A.02 (3.00).
Prompt neutrons - neutrons produced directly from the fission process (1.0) Delayed neutrons - neutrons produced from the radiological decay of (1.0) the fission products Delayed neutrons increase the amount of time the reactor takes to respond to changes in reactivity. (0.5) Without delayed neutrons, the reactor would respond so rapidly that it would not be possible to control. (0.5) REFERENCE , Nuclear Physics Made Very Very Easy pp. III-15,16 (***** CATEGORY A CONTINUED ON NEXT PAGE *****) - _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _
u ? q.
' :c).
' A ; - PRINCIPLES OF-REACTOR OPERATION Page 62
.
ANSWER ~ A.03 (1.00)
-0.5-for. showing a prompt drop O.5 for showing a -80 second period (exponential' decay)
' j REFERENCE Training Manual Startup #8 ANSWER A.04 (2.00) T = 100 sec rho = beta /(1+T*1ambda) .
(0.5)
=
0. 0064/ (1+ (100 sec) * (0.1/sec) )
=
0.0064/11
=
0.00058 delta k/k (0.5) mod. temperature coefficient = reactivity change / temperature change (0.5)
= (0.00058 delta k/k)/(5 deg F)
= 0.000116 (delta k/k)/deg F (0.5)
: REFERENCE'
.
Nuclear Physics Made Very Very Easy p. III-28
. ANSWER A.05 (1.50)<Q:2[[g 352 grams of U-235 = 352/235 = 1.5 moles of U-235 = 1.5 * 6.023E23 = 9.0E23 atoms of U-235 (0.5)
3.23E-11 Watts /second/ fission (0.5)
.9.0E23 * 3.23E-11 = 2.9E13 Watts-sec. / (3600 sec/hr) = 8.1E9 Watts-brs /(10E06 W/MW)
!'
= 8.1E3 MW-hrs (0. 5)-
(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
'
. _ _ - - _ - _ _ _ _ _ _ _ - _ _ - _ _ - _ - - - - _ _ - - _ _ - - - - _ _ _ _ _ - _ - _ _ - _ _ _ _ - _ _ -
. - _ _ _ _ - _ - - ___ _ - _
l
~ - A . PRINCIPLES OF REACTOR OPERATION Page 63
.
-.r.' . REFERENCE'
- 0 Nuclear Physics Made Very Very Easy p. 11 LANSWER A.06 (2.00)
a) Negative (0.5) b) Decreases (0.5) /MC/C#' c) Increases (0.5) d) Decreases (0.5) REFERENCE Nuclear Physics Made Very Very' Easy p. III-28 ANSWER A.07 (2.00) No (0.'5) Moving the' fuel elements could significantly affect
..
core excess reactivity, due to a possible net change in the microscopic cross.section(0.5) for the uranium. Net fuel may have been chifted toward .or~ away (0.5) from regions of higher potential neutron flux.(0.5) REFERENCE SUNY OP #4 p. 5 _
..
(***** END OF CATEGORY A *****)
i
*
_ _ _ . _ _ _ . _ _ . _ _ . _ . _ _ _ _ . _ . _
_ _ _ - _ - _ __ J
**B. FEATURES OF FACILITY DESIGN Page 64 .
I ANSWER B.01 (2.50)
- ' 1. Radiation Monitoring systems - 2. Exit lights / 3. Public Address system - 4. Evacuation Alarm 5. Fire Alarm System
'
< ' 6. Ventilation system damper solenoids 2[ #1p (5 required 0 0.5 each)
$ 6nyg '
* "
REFERENCE
[M7 Emergency Plan ANSWER B.02 (2.00)
1. The true value of reactor thermal power (0.25) shall not exceed 3.3 MW (0.25) 2. The true value of pool water level fron the surface to the top of the core (0.25) shall not be less than 5.2 meters (17 feet) (0.25) 3. The true value of primary coolant flow rate (0.25) shall not be less than 63 1/s (1000 gpm) (0.25) 4. The true value of the bulk pool temperature (0.25) shall not exceed 60 C (140 deg. F)- (0.25) REFERENCE Technical Specifications p. 5 ANSWER B.03 (1.00) Plutonium-239 decays to Uranium-235 plus an alpha (0.5) B:rillium-9 plus an alpha creates Carbon-12 plus a neutron (0.5)
. (***** CATEGORY B CONTINUED ON NEXT PAGE *****)
_ - _ _ _ _ _ _ _ _ _ _ _ _ _
- - . - - ,-- . - , .
v
.N ' "B . " FEATURES OF FACILITY DESIGN. Page 65- > .
l REFERENCE Training Manual (Reactions Section) i-ANSWER 'B.04- .(1.00) c.-irradiated' fuel provides a source of gammas (0.5) b.,the. fuel is placed in special holders along the wall of' the reactor tank. (0.5)
' REFERENCE SER pp. 10-2,10-3 ,
ANSWER 2
'B 05 (1.00)
NO. (0. 5) -
'
Thn monitor is locatedLdownstream of the hold-up tank (0.5) REFERENCE' SER p.;7-3 ANSWER B.06 (1.50) Li 1. Control blades installed in the core are not fully inserted (0.5)
/t i-7[2. The console key is in the keyswitch. (0.5)
3. Manipulations are being conducted in the pool that could affect
. core reactivity. (0.5)
)
,. j l l (***** CATEGORY B CONTINUED ON NEXT PAGE *****)
' = _ - - _ - _ _ _ _ - - _ .-_ -
._ _ - - _ . .. _ . _ . . _ . -. - - -_ - *
, , ;.:3 * - * ? B . -- FEATURES OF FACILITY DESIGN Page 66 , . , '
REFERENCE Technical. Specifications.p. 3 j .,
, ANSWER. B.07 ~(1.00)L g g g [
Thel experiment'should be unloaded (0.5).
I: This-is to ensure that' proper shutdown margin is achieved without r the negative effect of the experiment. (0.5)
..
REFERENCE
; OP #4 p. 4 t > ANSWER. .B.08 (l'. 50 ) ' .The shutdown margin relative to the cold, xenon-free critical condition-(0.5) .shall be not-luss'than the total worth of the most reactive safety-control blade (0.5) + 0.5% delta ~ k/k (0. 5)
REFERENCE Technical' Specifications r. 8 ANSWE.i .B.09 (1.50) a.'The beam tubes are " stepped" to prevent streaming (0.5) b. The beam tubes.have sbielded plugs installed to prevent high radiation at-the terminating point. (0.5)
:c. The aluminum casing'around the concrete plugs has.a rupture disk installed-to prevent pressure buildup. (0.5)
-REFERENCE SUNY; Operating procedure
!
L g
(***** CATEGC"Y B CONTINUED ON NEXT PAGE *****)
L_ ..
-
_ - - _ _ _ _ _ _ _ _ - _ -__
...
, j 9.
- , B.- FEATURES OF FACILITY DESIGN Page 67 ANSWER; B.10 (1.50)
a):When the pump stops, gravity opens the flapper valve allowing heat transfer from the core to the pool by-natural convection (0.5) b) The purpose of the holdup tank is to increase the transient time of the discharge water (0.25) to allow Nitrogen 16 radioactivity to decay to an acceptable level before coolant is returned to.the pool.
(0.25) c) The reactor pool temperature is maintained by a pneumatically operated bypass valve on the secondary side of the heat exchanger (0.25)
.The valve is. controlled by a temperature sensor on the primary coolant outlet of the heat exchanger (0.25).
REFERENCE DI' 8 '
'SUNY Safety Evaluation Report Section 5.1
[c/Ltd
!
l I
:
(***** END OF CATEGORY B *****)
_ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _
_ _ - _ _ _ - _ _ _ _ _ - - - - - _ - _
.f: . :J ~ ' 'C . GENERAL OPERATING CHARACTERISTICS Page 68 t .
ANSWER C.01 (2.00) a. Conductivity would increase-(0.5)
. reactor water radioactive activity would increase (0.5)
L l b.. Fuel damage would occur (0.5)
'Also building radiation levels'would increase (0.5) -REFERENCE OP #24 ANSWER C.02 (3.00) =1. Fuel manipulations in the core (0.5)-when there are >= 15 fuel assemblies on the grid plate.(0.5)
2. When experiments are.being manipulated in the core (0.5) that have an estimated reactivity worth >0.6% delta k/k.(0.5) 3. Removal of one'or more control blades (0.5) if there are >= 10 fuel assemblies'on the grid plate. (0.5) 4. Removal of-shielding plugs (0.5) from the beam. tube. (0.5) 5. Resumption of operation-following an unscheduled shutdown, (0.5) unless the shutdown was a result of an interruption of electrical power to the center. (0.5)
(3 required 0 1.0 each)-
REFERENCE Technical Specifications, pp. 31-32 ANSWER C.03 (1.00) No (0.5) the absolute value of all experiments in the core would exceed 3.0. (0.5)
(***** CATEGORY C CONTINUED ON NEXT PAGE *****)
.
-. .__ . , 3 l- -
Ci ' GENERAL' OPERATING CHARACTERISTICS Page 69 L.. 1
REFERENCE Technic'al Specifications _p. 8' l'
- ANSWER C.04 (2.00)
R r Drawing correctly shaped e curve (0.5) c g.
/ t i
\
e i v i I t Y' I'"'___________________.._______h_________
,
Rod Position (0.5) L ~ Tho' rod has a highest differential worth in the area of the highest
. thermal neutron flux (0,5).
' REFERENCE,
: Nuclear Physics Made-Vecy Very Easy p.III-23 ' ANSWER. C.05 (1.50) , Oxygen-16 plus a neutron becomes Nitrogen-16 plus a proton (0.5)
The Nitrogen-16 decays into Oxygen-16 (by beta and gamma emission) (0.5) The half-life of Nitrogen-16 is approximately 7 seconds (0.5) REFERENCE - Nuclear Physics Made Very Very Easy p. II-23
(***** CATEGORY C CONTINUED ON NEXT PAGE *****)
*
- _ _ _ _ _ - _ _ _ - _ _ _ _ - _ _ _ _
_ - _ - _ _ _ . _ _ _ t
'
)
.,C. GENERAL OPERATING CHARACTERISTICS Page 70 l
'
ANSWER C.06 (1.50) 1 kg (0.5) 4 l to insure use only in a low neutron flux (0.5), therefore the power i produced in the plate will not cause damage to the plate (0.5) ] REFERENCE Technical Specifications ANSWER C.07 (2.50) a. Attain a low power, stable critical position, then withdraw the rod to be measured to achieve a slow (long: approximately 30 second) period (0.5). Measure the time it takes power to change a specific amount (0.5). By recording the new position of the rod being-calibrated (and relating that to the period produced (period = power change /2.3), then reactivity can be read from the decade time versus % delta k/k plot (or calculated from the Inhour equation) (0.5) The % delta k/k per inch of rod travel for the entire rod can be determined from a sequence of measurements (0.5) b. To avoid temperature effects (0.5) REFERENCE OP #61 ANSWER C.08 (1.50) a) 5.0 - 7.5 b) Less than 5 micromhos c) Greater than 200K ohms (75K ohms for less than 15 days)
(3 required 0 0.5 each) (***** CATEGORY C CONTINUED ON NEXT nGE *****)
L - - _ _ _ _ _ _ -
_ _ _ _ _ _ _ _ _ __ _ . _ _ _ _ .-. - _ _ . . . _ _ _ _ _ i:
. > "'C, GENERAL OPERATING CHARACTERISTICS Page 71 l .
. REFERENCE l SUNY Operating Procedure OP 24 Section III
' i
,
(***** END OF CATEGORY C *****) ,
*
- - _ _ _ _ _ _ _ . .
__ - _ -___ _-
. . .t 3 0 D. INSTRUMENTS AND CONTROLS Page 72 ANSWER- D.01 (2.00) .A. FAST scram is a rapid reduction of the DC magnet holding current of the control blades, (1.0) and a SLOW scram is the- shutoff of AC electrical power.to the units providing the magnet holding current with subsequent decay (slow) of the magnet holding current. (1.0)
l
. REFERENCE Technical Specifications pp. 2-3 ANSWER D.02 (1.50)
Control Blade withdrawal is inhibited (0.5) This prevents the operator from adding positive reactivity (0.5) when there is not a visible countrate on the startup channel (0.5) REFERENCE Technical Specifications ANSWER D.03 (3.00) Silver (0.5) intermediate energy. neutrons (0.5) Indium (0.5) high thermal energy neutrons (0.5) Cadmium (0.5) thermal neutrons ( 0. 5) REFERENCE NUCLEAR PHYSICS MADE VERY VERY EASY p. III-22 ANSWER D.04 (1.50) The CIC contains two chambers, one chamber is sensitive to gammas (0.5) and the other chamber is sensitive to gammas and neutrons (0.5).
The first chamber's signal is electronically subtracted from the second chamber's signal (0.5)
(***** CATEGORY D CONTINUED ON NEXT PAGE *****)
*
_ _ - _ - - - _ - _ _ _ - - - -
. _ _ _ _ _ _ _ _ _ _ - _ _ -
t
. 'e
-*,- .
..
{
D.' INSTRUMENTS AND CONTROLS . page 73
.
REFERENCE t ANSWER D.05 (3.00) 1. log countrate or startup channel (0.25) for monitoring reactor
,f ~ power during a startup (0.25)
2. linear-N power or linear power channel (0.25) - for monitoring power (0.25) -(frn= -1 u- to-e-MW)--and .provi-de= siyuat fcr the--
/d, automatio-serve centrol (0.25)
3. Log-N power channel (0.25) - for monitoring power (0.25)
<'/rf (from a few W to > 2 MW) and provides the signal input for displaying reactor period (0.25)
Safety channels (0.25) - provides input to two independent channels
- 'pI 4. whichigive the redundancy to SCRAM the reactor-in response to
--
'high power (0.25) 1
{
, 5. N-16 power channel (0.25) - for monitoring power (0.25)
.,f/t (from about 50 KW to 2 MW)
REFERENCE 6, @,)&///N 4 M d T NMNMMM' SER p. 7.2 d# ANSWER D.06 (2.50) a. 3 subsystems (0.5) b. largecompressor-airlocksko.2), truck door seals (0.2), demineralizers(0.2), fume hoods (0.2),
lab benches (0.2)< second subsystem - Reactor Building Ventilation Controls (0.5) third subsystem - primary. coolant flow transmitters (0.5) REFERENCE Y .[d4 Wp /# // SER p. 9-1 l I I i i l (***** END OF CATEGORY D *****) l J _ - _ _ - _ . _ _ - - - 1
_- _ _ _ _.
- 4't
.
I E; SAFETY AND' EMERGENCY SYSTEMS Page 741 j '} ' .,
}u l.
' ANSWER- E.01 ( 2 . '00 ) 1. Potential.for excessive corrosive attack (0.5) of the reactor or experimental facility. (0.5) 2. Potential for excessive contamination (0.5) or production of airborne radioactivity (0.5)
.3. Potential.for a violent chemical reaction. (1.0) (2 required 0 1.0 each)
REFERENCE Technical Specifications p. 17
.
' ANSWER. E.02- (2.50)
'1.. Pool water analysis 3. 4., Primary water monitor increase i. gi 3. Building air monitor increase r / 4. . Particulate monitor increase 5. N-16 mon! tor increase y,j 6. Bridge mon.' tor increase (5 required 0 0.5 each)
: REFERENCE EP #5-(***** CATEGORY E CONTINUED ON NEXT PAGE *****)
*
m___u_______ _
- , _ . -. _ _ - . _ _ _ _ _ _ _ _ _ - _ - _ _ _ - _ _ ___ _ _ _ ______ _- _ - - _ ___.
-- t . e
"E. SAFETY-AND EMERGENCY SYSTEMS Page 75 ANSWER E.03- .(3.00)
SCRAM .SETPOINT _________________ ____________________ Manual Scram. (0.5) v Dry Chamber Door (0.25) .open- (0.25)
< Flow (0.25) < 68 1/s (0.25)
vFlapper position (0.25) 'open (0.25) Water Level' Low (0.25) 6.13 m above the fuel (0.25) High Power (0.25): 120% (0.25)
'High. Pool' Temp. (0.25) 52 C (0.25) (six. required 0.25 for each scram 0.25 for-each'setpoint)-
REFERENCE Technical Specifications-Table 3.1 ANSWER E.04 (2.00) 1. a Heat Balance Measurement O /" de /
(0.5)
2. the N-16 Monitor (0.5) neither parameter is affected by control blade position. (1.0) REFERENCE ANSWER E.05 (1.00) _
: Bridge' Fixed Area Monitor high (0.5)
and building exhaust effluent monitor high simultaneously (0.5) REFERENCE Technical. Specifications (***** CATEGORY E CONTINUED ON NEXT PAGE *****) _ - - _ _ _ _ _ _ . _ _ _ - _ _ _ _ _ _ _ __ _ _ _. . _ _ _
_ . _ _ ___ _ _ . - _ _ _ . . _ _ _ _ _ _ _ _ _ _ . _ - - _ _ . _ _ _ _ - - - _ _ _ . _
.-_.;- _- __ _ __._ _ _ _ _ _ _ _ __ _
c
. ' t '.
e
-..._
. ,
..
*$:t SAFETY'AND EMERGENCY SYSTEMS 'Page.76 E.. ,
>
l (3.00)
'
ANSWER. E.06; ,
:a. city' water (0.5) '
p" f b. heat. exchanger (secondary)- (O.5)- l '. :c. secondary pump. (0.5) f- ,d.' auto bypass valve ,(0.5) c. a..c,. water pump (0.5) f.'_' air-conditioner condenser. -- ( 0. 5 )
> REFERENCE T
SER-p.,5-4
': _r .
!
(***** END OF CATEGORY E *****)
. -__ -_ ____--- _ ____-_
___ . - _ _ .
' 't- . 'e < '#
F. STANDARD AND EMERGENCY OPERATING PROCEDURES Page 77
.
ANSWER HF.01 (1.30)
-
1". krypton. g ~ L 8/eu' m Of3 2. xenon j , /,
[v/9eCt//"
,
3. bromine 4. iodine f*
, (3 required 0 0.5 each)
REFERENCE EP 5 p. 4-ANSWER F.02 ( 0.' 5 0 )
' Emergency Director (0.5)
REFERENCE t Emnrgency Plan I
' ANSWER F.03 (2.00) 1. Shut down the plant (0.5)
, '
2. carry out the initial steps as specified by the EPs .(0.5) 3. Evacuate the reactor building (0.5) 4. Remain available to the Emergency Director. (0.5) REFERENCE-
. Emergency Plan (***** CATEGORY F CONTINUED ON NEXT PAGE *****)
i i
.]
__z=__---__ _ _ - 4
. _ _ _ _ _ _ _ _ _ _ _ . - _ _ _ _ -
;
4:
. .
n., o- 'F.- STANDARD.AND' EMERGENCY' OPERATING PROCEDURES Page!78-
.'
i
' ANSWER F.04- (1.50) ,
!
1.' Uncontrolled Zone. (0. 5) . - 2.. Controlled Zone (0.5) j j ffWK
.The detectors are located in the emergency kit at Mc'; Rascacch Se44 cling ( 0 . 5 ) --
REFERENCE Emsrgency Plan-ANSWER F.05'- (1.50)
' Manual;- Scram -(0.5) ' verify the. rods are. inserted (0.5) .
The scram'should be' reset after the cause of the scram is determined (0.5) REFERENCE OP #.6
,
(***** CATEGORY F CONTINUED ON NEXT PAGE *****)
-
-__ _ - _ _ - _ _
_ _ _ _ _ _ _ _ _ _ t
. *
F. ST,4NDARD AND EMERGENCY OPERATING PROCEDURES Page 79
.
ANSWER F.06 (3.00) 1. The truck door shall be closed and sealed, (0.34) one door in each of two airlocks shall be closed and sealed, (0.33) and all other penetrations other than ventilation ducts shall be sealed. (0.33) 2. The' stack fan in the university steam plant shall be operating and (0.5) the fan in the building air duct shall be operating (0.5) 3. The pressure in the containment vessel shall be negative (0.5) with respect to the outside atmosphere (0.5) 4. The dampers in the containment ventilation ducts must be operable and be capable of closing in 5 sec. or less. (0.4) They must close automatically in response to coincident alarms from the building air monitor and the bridge monitor (0.4) or in response to a manual signal (0.2) 5. A charcoal filter shall be maintained in the emergency exhaust duct (0.5) and the modulating damper in the exhaust duct and its controller shall be operable (0.5) 6. The leak rate of the containment vessel shall not exceed 3.3 1ps (7 cfm) standard air (0.5) at a negative differential of 1.27 cm of water (1/2 inch of water) (0.5) l (3 of 6 required at 1.0 each) REFERENCE Technical Specifications pp. 13-14 ANSWER F.07 (2.00) 1 A licensed Reactor Operator (RO) (0.33) or a licensed Senior Reactor Operator (0.33) must be present in the control room whenever the reactor is operating. (0.34) A second person must be present at the facility (0.5) who can be reached from the control room by telephone or intercom. (0.5)
(***** CATEGORY F CONTINUED ON NEXT PAGE *****)
l l - )
_.
s . C F. STANDARD AND EMERGENCY OPERATING PROCEDURES Page 80 REFERENCE
' Technical Specifications p. 29 ANSWER F.08 (2.00)
c. The reactor is secured when a shutdown checklist has been completed (1.0) { b. The reactor is considered shutdown if all control safety blades are fully inserted (0.34), the console key is removed (0.33), and.no manipulations are being conducted in the pool that could { affect core reactivity.(0.33) l REFERENCE Tcchnical Specifications p 3
< (***** END OF CATEGORY F *****)
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .
e-.
..
,
,
! IG. -RADIATION CONTROL AND SAFETY _ Page 81
[ .' :
ANSWER G.01 (2.00) p standard deviation of counts = sqr root (800) - .28 cts Minimum Detectable Activity = 3 * std tn/(count time) j
=3 * 8.28 cts)/(15 min) = . 6 cts / min convert cpm to dpm (5.66 cts / min)/(0.05 cts / dis) = 113.14 dis / min
( = 51 E -06 micro Ci ) i '
REFERENCE Radiation Protection, Training Manual p. 20 ANSWER G.02 (2.50) x(1/2) = In(2)/mu (0.5) mu = In(2)/x(1/2) ,
= - (0. 6931)/0.178 cm = 3.894 cm(-1) (0.5)
I=I(0) e**(-mu*x) (0.5) I/I(0) = e**(-mu*x) In(I/I(0)) = -mu*x x = In(I/I(0))/-mu (0.5) x = In(2/10)/ (-3. 894) - x = 0.413 cm (0.5)
(= 0.163 in)
REFERENCE Radiation Protection Training Manual pp. 56-57 (***** CATEGORY G CONTINUED ON NEXT PAGE *****)
.
-- . ..
L. - # G. RADIATION CONTROL'AND SAFETY Page 82
.a (
ANSWER G.03 (1.50) _l'. Time- (O.5)
,
2.. Distance - (0. 5)-
. 3.; Shielding (0.5)
REFERENCE
' Radiation-Protection Training Manual p. 52 ' ANSWER G.04 (2.00)
dose (in mrem).= dose (in mrad).* Quality Factor .
(0.25)
20 mrad * 1 = 20 mrem (0.5) 5. mrad ~* 3 = 15 mrem (0.5) 2 mrad * 20 - 40 mrem'
._________
(0.5)
Total dose = 75 mrem (0.25)
-REFERENCE-Radiation Protection Training Manual p.12 ANSWER G.05 ( 2 .' 5 0 )
' l. area radiation monitors
' 2.Lprimary coolant monitors 3. effluent' monitors 4.-primary loop components (leak tight integrity)
5. installed shielding
6. containment 7. primary purification (demineralized)
(5 required-@ 0.5 each) (***** CATEGORY G CONTINUED ON NEXT PAGE *****)
i_______________________ _ _ _ _ _ .
*
i
__- - _ __- -_ __ ._.
.A
'^
f;,., g}G.- RADIATION' - CONTROL AND' SAFETY Page 83 o.
REFERENCE-
-SER'pp. 4-2,4-3,5-1,5-3,6-2,12-3 ANSWER' G.06 (2.00)
1. a. 1.25 R/qtr (0.5) b. 7.5 R/qtr- (0.5) c. 18.75 R/qtr (0.5)
~2. 3 R/qtr (0.5) ' REFERENCE-Radiation. Protection Manual p. 40 . ANSWER G.07 ( 2 '. 5 0 ) .
a. remove the filter ~from the alarming CAM (0.5) to verify system operation-(0.5) b. if Filter removal results in decreased monitor response, SHUT DOWN the Reactor-(0.75) and evacuate the containment building (0.75) REFERENCE OP #26C p. 3 (***** END OF CATEGORY G *****)
(********** END OF EXAMINATION **********)
)
.
_ - - - _ _ _ _ _ _ . _ _
_ - _ - _ _ _ _ _ _ - _ _ - _ - - _ _
-
ATTACHMENT 3 SUMMARY OF FACILITY COMMENTS'AND NRC REVIEW f STATE UNIVERSITY OF NEW YORK, BUFFALO MATERIALS RESEARCH CENTER I I REACTOR OPERATOR EXAMINATION: I Question A.05 The facility _ pointed out that this question was incorrect in that the power asked for could not be calculated with the information given.
After review, the NRC has determined that the conversion given l was incorrect and that the question would be deleted because / it cannot be adequately answered as stated.
Question A.06 a) The facility commented that an oscillatory temperature would be experienced when the primary coolant pump is shut I down, and.that a positive reactivity effect could also be expected.
The NRC has determined that an osci31atory effect is a long term phenomenon that is not applicable to the question as stated. The effect requested is the one following the i shutdown of the pamp, not many hours later. No change to l the answer key will be made, b) The facility stated that the Metal to Water ratio would increase and not decrease under the conditions stated in the question.
The NRC has determined that the Metal to Water ratio would increase. The answer key has been modified to reflect this correction.
Question B.01 l The facility stated that the Emergency Phone and Emergency Light above the generator were also powered by the emergency { power source at the facility.
l The NRC has determined that these additions will be accepted ' as valid answers. l I Question B.07 ' The facility stated that this question was difficult to understand, and was not worded in such a way as to elicit the , response sought. ) I The NRC has concluded that the question at stated is not ! l sufficiently clear to elicit the answer regs '. red. The l question is therefore being deleted from tne examination.
! _m-_____um___.-_
_ _ - - - -
'
i
i i
;
I Question B.10 c) The facility stated that in actuality, primary temperature is controlled by adjusting the cooling tower louvers instead of controlling the bypass valve for the heat exchanger.
The NRC has determined that this method of control will be accepted in addition to the anrwer described in the answer key.
Question D.05 The facility stated that an alternate answer could be a description of the delta T instrumentation which is also used in control, shutdown and monitoring functions. The facility also stated that the servo rod no longer exists at the i facility and should be removed from the answer key.
The NRC answer key will be modified to accept such a discussion as an alternate answer. The reference to the servo rod will be removed from the answer key. The facility should ensure that future reference materials sent to the NRC reflect actual plant configuration.
Question D.06 The facility stated that the third subsystem also provides air to the secondary bypass valve.
The NRC answer key will be modified to accept the facility comment as an acceptable answer.
Question E.04 The facility stated that a common way to refer to a heat balance at the site is to speak of a " delta T", therefore this should be acceptable for one of the answers.
The NRC will accept a reference to " delta T" as being a heat balance.
Question F.01 The facility stated that cesium 138 and rubidium could also be released during a fuel leak and are considered to be additions to the four elements listed in the answer key.
The NRC answer key has been modified to accept the additional two elements.
Question F.04 The facility stated that the equipment referred to is kept in Clark Gym and not Howe Hall.
The NRC will accept Clark Gym instead of Howe Hall.
Question G.01 The facility stated that material covered in this question is
_ - _ _ - _ _ _ _ - _ _ _ _
-
;
*
i beyond the scope of licensed operator duties at the facility and therefore should not be included in the examination.
This question has been deleted from the examination due to certain. sections of the Radiation Manual not being applicable to the reactor operators.
SENIOR REACTOR OPERATOR EXAMINATION Question H.02 The facility stated that the question could not be solved for megawatt hours (stated that units were incorrect).
An NRC review resulted in the determination that the question was correct, and solvable. However, Avogadro's Number as given was incorrect but this will not count against the candidate.
Question H.04 See NRC response to facility comment for Reactor Operator Examination question A.06.
Question H.07 The facility stated that the answer key should state that leakage is increased, not resonance escape probability.
An NRC review has determined that the facility is correct.
The answer key has been modified to reflect the correction.
Question I 01 The facility stated that the simplification made on the answer key is not commonly used, and that the candidate would probably make suitable assumptions.
The NRC has determined that alternate and justifiable solutions apart from the solution documented in the answer key are acceptable. A commonly used expression for gamma related activity has been introduced into the answer key.
Question I.04 The NRC has determined that since mu was not specified as the mass attenuation factor la the question, using mu as the
-
linear attenuation factor is acceptable for full credit.
l Question I.06 The facility stated that this question requires knowledge outside that requirsd of an operator at the facility. This section of the Radiation Manual is designed for other ; personnel at the University. I ( The NRC agrees with the facility's contention and has deleted this question from the examination.
I I I l _ ._. l
. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ _ _
. ,
.
!
Question I.07 The facility stated that additional answers are documented in the Radiation Protection Manual.
The NRC has determined that additional answers are available in the Radiation Manual under the laboratory procedures section. These will be accepted for credit.
Question J.04 See facility comment and NRC resolution for Reactor Operator Examination question B.01.
Question J.05 See facility comment and NRC resolution for Reactor Operator Examination question A.06 (a) ana B.10 (c).
Question J.11 The NRC noted that SER page 7-5 indicates that pool temperature is also used for indication during operations, therefore, credit will be given for stating this in part m of the question.
Question L.07 The NRC has determined that additional answers for this question are contained in the Radiation Manual pages 65 and 66. These additions will be accepted for credit.
Question L.10 The facility stated that part 2. of this question was not an emergency and therefore did not apply to the question.
The NRC agrees with the facility in that the discharge would need to be an average value over time to be a genuine emergency, this part of the question has been deleted.
_ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ - . _ _ _ _ .
. - _ _ _ _ - - -. _ - . _ _ . . _ _ . . . . . , _ m.
[- ,
. _ , , . .. . ..
[: ATTACHMENT 4 l .*
-
3ME- o o BUFFALO MATERIALS RESEARCH CENTER
'
_D J l M
'
*
February 9, 1989 l Mr. David Wallace-U.S. Nucicar Regulatory Commission Region'I L 475 Allendale Road King of Prussia, Pennsylvania 19406
Dear Mr. Wallace:
Enclosed for your files are copies of two memoranda which I have distributed here at BMRC.
The first memo, which is addressed to all licensed Operators and
. Senior Operators, indicates how re-qual examinations are currently administered. It also indicates what action will be taken in the event of known or suspected cheating.
The second memo is addressed to members of the management staff who are responsible for writing section(s) of the test. It describes what minimum precautions are necessary to safeguard the integrity of the exam.
' I hope you will find these satisfactory and consistent with our previous conversations. If you would like any further action or j have questions, please let me know. ,
,
Yours very truly, aA Louis G. Henry Director amf enclosures (2) . cc: ;P. Orlosky
,M. Pierro (
SUNY-BUFFALO, ROTARY ROAD BUFFALO. NEW YORK 14214-TELEPHONE (716) 831-2826 * Encyllnk 02910144
!
"" _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ _
___ o o p1989 16:26 D1RC/SUNY BUFFfLO
?i6 832 7693 P.01 l
m
*
" 3M3 2.D j l
-
o o u M " # BUFFALO MATERIALS RESEARCH CENTER l MEMORANDUM TO: All Operators and Trainees \ FROM: Louis Henry ! 94 r
,
DATE: February 6, 1989 C SUBJECT: Operator Requalification Exams i
!
k
-
The purpose of this memo is to reiterate BMRC and y
.
All Requal examinations will be conducted closed book . Exams will not be administered on shift or on a take A home b When operators complete an exam, they will be required to leav . the building operators areand not discuss finished taking the exam with anyone until all e the exam.
proctored. Requal exams will be Operators will be afforded a reasonablee period after
. of timThe before the exam. conclusion of the lectures to study the materials presented' !
be covered in the retraining lectures,Alli.e., questions on the exam will not nec relieve an operator from bein the lectures do not -
,
reactor operation and theory.g knowledgeable in all areas of all pertinent materials before the Operators exam. are expected to review lectures.
operators begin this review in advance of the retrainingIt is suggested that . All exams will be carefully reviewed by the the operat operating c mmittee.
e exam, can be proving Committee will investigate vigorously.
involved. en, we will seek dismissal of the individual (s)If cheating If we determine that an operator han knowledge of cheating on the exam and does not come forward, we will similarly investigate both operators. and if proof is availabic, we will seek dismissal of Any examoperator should not that becannot operating legitimately pass the roqualificati on the reactor.
will simply not be tolerated. Cheating in any form _.
I
!
(
I
!
SUNY BUFFALO, HOTARY ROAD, BUFFALO, NEW YORK 14214-TELEPHONE -
* EasyLink 62010144 (716) 8(I
_ _ _ _ _ _ _ _ _ - - - - - - - - f
- - - - - - _ _ _ - _ _ _ _
. . , - - to h6 * Q y n ** C y wt ( 6 f, O 7 - ,c. . - , - , 4. . , ., . es w w n =.. -
. _ _ ,_3_,_ _ _ _ _
'
___
*
G2/09/1989 1G:25 D1RC/SUt# DUFFf-iLO 71G 832 7693 P.03
.
-
* 3ME o o BUFFALO MATERIALS RESEARCH CENTER M
'
'
.cP J L -
!
MEMORANDUM To: PMO, MAP, JPG, MSA, DWS FROM: Louis G. Henry M DATE: February 6, 1989 SUBJECT: Requal Exam Security
.O
.:
- The purpose of this-memo is to outline a policy for the jh preparation of Operator Requalification Exams. ;jj
,. :
As in the past, we will be dividing the test into sections with si individual sections or questions to be allocated between us on a .i case by case basis. We must minimize the opportunities for any g unauthorized individual to view the test materials in advance. I i am therefore establishing the following policies: ( y
~
Test questions and answer keys will not be stored overnight - except for approved locations. The approved locations will bo !
- In Mark Pierro's office in parker .
,
-
At our homes .{
- In a safe which will be located within the facility c.
If you compose the questions or answers using a computer, do not I store the files on a hard drive within BMRC overnight. Store the y files on a flexible disk as outlined above. M Y3 If you wish to store copies / disks in the safe, make' arrangements of directly with me. :l, During the day do not leave exams or answer keys out when your j l desk is unattended. Lock them in a locker, file cabinet or : drawer. -
Compliance. with the above policies may be unpleasant, but it is .! necessary to provide reasonable assurance to the NRC and to the 4 { public that we have minimized to the extent practible the M opportunity for individuals to cheat, fj
Nm -r L iu
'
.g l l
q
' k
_5 r .A j.
ki ) l }}