IR 05000225/1988001
| ML20196L060 | |
| Person / Time | |
|---|---|
| Site: | Rensselaer Polytechnic Institute |
| Issue date: | 06/21/1988 |
| From: | Dudley N, Eselgroth P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20196L040 | List: |
| References | |
| 50-225-88-01OL, 50-225-88-1OL, NUDOCS 8807070212 | |
| Download: ML20196L060 (50) | |
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b U. S. NUCLEAR REGULATORY COMMISSION REGION I OPERATOR LICENSING EXAMINATION REPORT EXAMINATION REPORT N /88-01(0L)
FACILITY DOCKET N0. 50-225 FACILITY LICENSE NO. CX-22 LICENSEE: Rensselaer Polytechnical Institute Troy, New York 12181 FACILITY: RPI Critical Facility EXAMINATION DATES: May 24-25, 1988 CHIEF EXAMINER: / /
/hM N. Dudley, Mnior Oper4(tons 6//
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S ec list, OR APPROVED BY: /. 4 -G Peter W. Ese)proth, Chief PWR Section
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Date bb Opera (4ons Branch, DRS SUMMARY: One Senior Reactor Operator (SRO) applicant was administered a written and an operating examination. The applicant failed to pass both portions of the examination and a proposed license denial was issue PDR ADOCK 05000225 -
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REPORT DETAILS TYPE OF EXAMINATION: Replacement EXAMINATION RESULTS: One (1) SR0 applicant failed both the written and operating portions of the examinatio CHIEF EXAMINER AT SITE: N. Dudley, NRC Personnel Present at the Exit Meeting NRC Personnel Dudley, Senior Operations Specialist Facility Personnel F. Rodriquez, Operations Supervisor Exit Meeting The facility provided review comments on the written examination. The examiner discussed the training and experience requirements for issuance of an NRC operating license and provide the licensee copies of 10 CFR 55 Operators' Licensee and NUREG 1021, Operator Licensing Examiner Standards Chapters ES-110 E5!111, ES-204, ES-303, and ES-404 which pertain specifically to non power reactor Attachment: SR0 Written Examination and Answer Key
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ATTACHMENT 1
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V. 5. NUCLEAR REGULATORY C0KMISS10H
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SENIOR REACTOR OPERATOR LICENSE EXAMINATION FACILITY: RENSSELAER REACTOR TYPE: TEST DATE ADMINSTERED: 80/05/23 EXAMINER: JERRELL. _
CANDIDATE __
INSTRUCTIONS TO CANDIDATE:
Use separate paaer for the answers. Write answers on one side onl Staple question sleet on top of the answer sheets. Points for each question are indicated in parentheses after the question. The passing grade recuires at least 70% in each category. Examination papers will be pickec up six (6) hours after the examination start ,
% OF CATEGORY % OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY 20.00 20.00 REACTOR THEORY 20.00 20.00 RADI0 ACTIVE MATERIAL.S HANDLING DISPOSAL AND HAZARDS 20.00 20.00 SPECIFIC OPERATING CHARACTERISTICS 20.00 20.00 - FUEL HANDLING AND CORE PARAMETERS 20.00 ADMINISTRATIVE PROCEDURES, 20.00 CONDITIONS AND LIMITATIONS 10 % Totals Final Grade All work done on this examination is my ow I have neither given nor received ai Candidate's signature
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tiRC RULES AfID GUIDELIflES FOR LICEtiSE EXAMIttATI0tlS
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During the administration of this examination the following rules apply: Cheating on the examination means an automatic denial of your application and could result in more severe penaltie . 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 cheatin . Use black ink or dark pencil only to facilitate legible reproduction . Print your name in the blank provided on the cover sheet of the examinatio . Fill in the date on the cover sheet of the examination (if necessary). Use only the paper provided for answer . Print your name in the upper right-hand corner of the first page of each section of the answer shee . 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 shee tiumber each answer as to category and number, for example, 1.4, . Skip at least three lines between each answe . Separate answer sheets from pad and place finished answer sheets face down on your desk or tabl . Use abbreviations only if they are commonly used in facility literatur . 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 require . Show all calculations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or no . Partial credit may be given. Therefore, AtlSWER ALL PARTS OF THE QUESTI0ft Af40 D0 fl0T LEAVE AtlY At4SWER BLAf1 . If parts of the examination are not clear as to intent, ask questions of the examiner onl . 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.
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18. When you complete your examination, you shall:
a. Assemble your examination as follows:
(1) Exam questions on to (2) Exam aids - figures, tables, et (3) Answer pages including figures which are part of the answe b. Turn in your copy of the examination and all pages used to answer the examination question 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 examine If after leaving, you are found in this area while the examination is still in progress, your license may be denied or revoke ,
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. REACTOR THEORY Page 2
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QUESTION H.01- (2.00)
With the reactor critical, a small amount of. positive reactivity is rapidly inserted. EXPLAIN the "prompt jump" and subsequent linear power increase which would be observed on the nuclear instrumentatio (2.0)
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QUESTION H.02 (2.00)
The reactor is maintaining a constant power level indication on the nucicar indication at an intermediate power level with the source fully inserted. Assume that the source is then instantaneously withdrawn. DRAW on a graph of neutron population versus time the behavior which would result and EXPLAIN the shape of this resulting curv (2.o)
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QUESTION H.03 (2.00) WHY is the plutonium source surrounded by beryllium? (1.0)
4 Following an extended shutdown (6 months), WOULO you expect the effectise source strength to INCREASE, DECREASE, or REMAIN THE SAME7 JUSTIFY your answe (1.0) ,
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i QUESTION H.04 (1.50)
I With the reactor operating at 1004 power, an experimental .
, apparatus in the central area of a B core configuration l
suddenly fails, filling the previously voided volume with
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water. STATE WHAT automatic actions, if any, would occur if no operator actions are taken. JUSTIFY your answer and STATE any assumption (1.5)
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REACTOR THEORY Page 3 H. QUESTION H.05 (2.00)
DRAW a diagram of FUEL / MODERATOR. ratio versus REACTIVITY (units not required), SHOW the approximate full (water covered) operating point and INDICATE how this operating point is effected by draining water to the water storage tank, (2.0)
QUESTION H.06 (2.50) HOW (direction) and WHY (reason) does reactivity change with an increase in the temperature of the reactor fuel? (2.0) WHAT is this phenomena commonly called? _(0.5)
QUESTION H.07 (2.50)
The "in-hour" equation, as given below, relates rea:tivity to reactor perio *
rho = -- + - -----
T 1 + di T
. L=1 . DEFINE the symbols 1*, beta-i, and lamdba- (1.5)
. WHY does the sum go from 1 to 67 (1.0)
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H. -REACTOR THEORY' 'Page 4 m
QUESTION H.08 '(3.50)-
Assume the reactor is o)erating at 270 W-and a boron strip worth 60 cents falls out'of tie core. The reactor power takes a
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prompt jur.p to'675 W followed-by a subsequent power rise on a
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stable 6.5 second perio IF a scram were not initiated for 7 seconds'into the transient and 60 msec were required to turn the power rise after the initiation of scram, WHAT is the maximum power level the reactor would reach?- (1.75) Assuming an adiabatic fuel temperature increas (i.e., no heat transfer from the fuel) during the transient, with the specific heat of the fuel 0.10 Btu /lbm deg F, and the fuel mass of 10 lbm,
-PHAT would be the rise in fuel temperature? (1.76)
QUESTION H.09 (2.00)
SKETCH a control rod differential worth curve and EXPLAIN the reason for its shape. LABEL the axes on your grap (2.0)
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. RADI0 ACTIVE MATERIALS HANDLING DISPOSAL Page 5 AND HX2ARDS
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l-QUESTION I.01 (3.00) Briefly EXPLAIN H0W. reactor tank water is verified safeforoff-sitedischarge(3 steps). (2.25) WHAT administrative control would prevent a new R0 from inadvertently pumping reactor water to the river? (0.75)
QUESTION I.02 (3.50)
A three curie gamma source falls out of its shield cask midway between two students who are separated by 4 meters. One student ducks behind a shield wall consisting of 4".of lead located next to him, while the other student runs back to the far wall located 9 feet further away_from the sourc WHAT dose rate is each student receiving a) prior to and b) following their actions?
STATE ALL assumptions and SHOW ALL wor (3.5)
QUESTION I.03 (2.50)
A person is standing in a radiation field for 15 minutes consisting of rad of thermal neutrons rad of 1 Mev beta radiation rad of 1 Mev gamma radiation DEiERMINE WHAT the total dose is in RE SHOW all calculations and formula (2.5)
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,, - R DIDACTIVE MATERIALS HANDLING DISPOSAL
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QUESTION I.04 (3.00) Fill in the~ table below with federal exposure limit values for radiation' worker (2.0) .
REM per calendar quarter Quarterly ' Quarterly Averag Maximum Whole body Skin X
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Extremities X HOW much total whole boay exposure could an 18-year-old freshman student receive if an NRC Form 4 were on file? (1.0)
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QUESTION I.05 (3.00)
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A job must be performed in a 2 REM radiation field. Two alternative methods are to be considered: Two men working together can complete the job in 30 mi . Placing (20 min one-man job) and removing (20 min one-man job) shielding will reduce the radiation field in which the two men must work to 200 mrem /h WHICH procedure is better and WHY? SHOW all work (3.0)
QUESTION I.06 (2.00)
If a radioactive sample produces 22 rem /hr at 1 meter and has a half life of 17 seconds, HOW LONG must one wait to manipulate l it if a maximuu allowable radiation of 1 rem /hr at 1 meter is (2.0)
required?
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. RAD 10ACTIVi MATERIALS HANDLING DISPOSAL Page 7 AND HAZARDS
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QUESTION I 07 (3.00)
During full power operation the criticality detector system in the fuel storage area is found to be totally inoperative. Using the provided Technical Specifications pages, ANSWER the following: HAVE Technical Specifications been violated? SUPPORT your answe (1.5) IS it acceptable to temporarily place a portable area radiation monitor in the fuel storage area and continue operations? SUPPORT your answe (1.5)
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.. a Page 8 py L SPECIFIC OPERATING CHARACTERISTICS QUESTION. .J.01 (1.00)
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ANSWER'TRUE or FALS The instrument scrams at the RPI facility are based upon a v ail-safe philosoph (0.5) Multiple channel' scram triggers cause the probability for failure to scram to be acceptably smal (0.5)
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QUESTION J.02 (3.00)
INDICATE whether a safety trip would be expected for each of the following instrument failures. Consider each failure separately and include WHAT safety trip would be expected for those failures which would cause a tri a Log N meter. fails high (0,5)
a linear NI channel fails low (0,5) a linear NI channel fails high (0.5) a BF 3 detector fails high (0.5) a-UCI chamber loss of high voltage occurs (0.5) tank tempe"ature instrument fails high (0.5)
QUESTION J.03 (2.00)
Given the attached curves of integral bank control rod worth and period versus reactivity, WHAT is the minimum steady state pe*iod that would resulo from a bank rod withdrawal of one inch? (2.0)
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. SPECIFIC OPERATING C9ARACTERISTICS Page 9
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QUESTION J.04 (3.00)
Certain valves in the water piping system at the pensselaer Critical Facility are desinned to fail to-a preset position on loss of power. WHAT is the failed position, and give tne basis for this failed configuration for the following: pump discharge valve (1.5) pump suction valve (1.5)
QUESTION J.05 (1.50)
WHAT is the function of the 1000 ohm resistor in the AC supply line to the scram relays? (1.5)
. QUESTION J.06 (3.00)
The front panel of the scienoid interrupt circuit module has TWO voltmeters, WHAT voltages do they indicate? (TWO items) (1.0) WHAT are the normal indicated voltages? (TWOitems) (1.0) WHY are these indications important? (TWOitems) (1.0)
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QUESTION J.07 (2.50)
LIST the five (5) interlocks required to be met to allow rod withdrawa (2.5)
QUESTI0l1 J.08 (1.00)
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WHAT is the LEtiGTH and approximate WORTH of each control rod in the LEU core? (1.0)
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. SPECIFIC-0PERATING CHARACTERISTICS .Page 10'
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QUESTION 'J.09 (1.00)
Assume the facility is operating at 100% power when the-instrument air ~ compressor fails and the instrument ai system pressure drops to atmospheric.- HOW will the facility rtipond with no operator act ion? Include cause and effect relatic1 ship f t;^ each component effected. (1.0)
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QUESTION J.10 (P.00)
Assuma the f ac i l i t.y is operating at 100% :ower when the 400 cycle MG set fal1s. -HOW wi11 the faci 1ity. respond with no operator' action? Include cause and effect statements for each componer't effecte (2.0)
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. FUEL HANDLING AND CORE PARAMETERS Page 11
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QUESTION K.01 (2.00)
STATE if the following are TRUE or FALS Fuel pins may be stored in the vault or in a fully dispersed array inside the reactor tan (0.5) The fuel in the vault is stored in B10 lined steel tube (0.5) The k-infinity of fully loaded storage tubes shall remain subcritical by at least $142.00 when flooded with wate (0.5) A licensed senior operator and the critical facility supervisor shall be present for all fuel transfer (0.5)
QUESTION K.02 (1.50)
Fill-in-the-blank In the positive period method of control rod calibration, the position of the rods is related to a measured period caused by of a rod by a amoun (1.5)
QUESTION K.03 (1.50)
SPECIFY the following core parameters for a SPERT fue', pi . fuel pellet chemical form (name or formula) (0.5) fuel pellet U-235 enrichment (w/o) (0.5) cladding material (0.5)
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QUESTION K.04.- (3.00)~
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0 RAW a plot of 1/M versus fuel m ss and SKETCH i characteristic curves for the case of: neutron detector too close to startup source- (l'.0) neutron detector proper distance from startup source (1.0)
3.- neutron detector ton far from-startup source (1.0)
LABEL all axes and curve ,
QUESTION K.05 (4.00)
' STATE the four (4) reactor parameters that must be determined per Technical Specifications during the initial testing of an'
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. unknown or previously untested core configuratio BRIEFLY tell WHY this-is required prior to operation (one reason why
, all-four must be measured.) - (e .0)'
QUESTION K.06 (3.00)
With regard to safe core loading guidelines: WHAT position must control rods be in' prior to loading any fuel? (1.C) You load' ten fuel pins during the first step and observe
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no change in count rat WHAT i r. the maximum number of fuel pins which can be loaded during the second step prior to observing the count rate? WHY? (1.0) WHAT must be done if the source is relocated during fuel loading? (1.0)
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- FUEL HAN LING AND CORE PARAMETERS
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-QUESTIO K.07 (2.00)
For a known core configuration, it is desired to replace a single stationary fuel pin. 1Five requirements must be met Technical Specifications to perform this task. -LIST four 4). (per .(2.0)
. QUESTION K.08 (3.00)
In regard to the reactor' power calibration, ANSWER the following: WHY is it necessary to determine cbsolute thermal flux rather than aLyalue for simply total flux at a point in the core? (1.0) GIVE two (2) reasons WHY Au-197 is usually used to measure thermal flux? (1.0) WHY: 1s a cadaium. cover used on some of the gold foils? (1.0)
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? ADMINISTRATIVE PROCEDURES, CONDITIONS Page.14
'. AND LIMITATIONS-N QUESTIO L.01. .(3.00)
\ GIVE the. Technical Specifications bases for each of the following specifications: minimum flux. level of 2 cps (1.0) maximum-thermal power level of 135 watts (1.0). minimum period of 5 seconds (1.0)
._QUESTION L.02 (2.00)
WHEN (2 occasions) and under WHAT two (2) PROVISIONS'may the reactor door scram be bypassed? (2.0)
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QUESTION L . (2.00) WHAT is the minimum tank temperature allowed per Technical Specifications for reactor operation? (0.5)
, WHAT i the basis for this value? (1.0) HOW is. tank temperature measured? (0.5)
l-l-QUESTION L.04 (4.00)
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A feasibility study for producing a new detector liner is to be j conducted in the reactor.- A very small quantity of a coarse l
powder which is doubly encapsulated consisting of ferric chloride and urar.ium dioxide is to be inserted into the reactor l for activation. STATE two (2) Technical Specifications ttat ST/TE any would be applicable, AND the reason (basis) for eac assumption (4.0)
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- ADMINISTRATIVE PROCEDURES, CONDITIONS ~~~
-Page.15 AND LIMITATIONS
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QUESTION 'L.05 (1.50)
'While reading the Technical Specifications Section 4.1.2, water dump time-surveillance requirements, you find that it' references ~
Specification 3.1, Item 4 (rod drop time),-rather than the proper Section 3.~1, Item 5-(water dump reactivity time) WHAT, if anything, must be done? (1.5)
QUESTION L.06 (1.00)
DEFINE the term OPERABLE per Technical Specification (1.0)~
, QUESTION L.07 (1.50)
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From the following steps GIVE the order of their priorities when
'immediate actions must be taken if emergency conditions develop at the. reactor facility, i.e., which is first consideration, second, et . Steps to prevent the spread of hazards associated with accident condition (0.5) Steps to minimize the extent of damage to the critical facility and its equipmen (0.5)
3.- Steps for human safet (0.5)
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QUESTION L.08 (3.00)
You are in the office when an explosion with thick smoke and intense' heat occurs in the counting room where the facility and operations supervisors are conducting an experiment. As SRO, ANSWER the following: WHAT is your first action? (0.5) WHO is in charge? (0.5) WILL respirator protection be necessary prior to fighting the. fire? (0.5)- WILL the emergency alarm be automatically initiated? (0.5) Assuming that you could rescue one of the men from the counting room, WHERE should he be taken for treatment? (0,5) WHO should be called first? (0.5)
QUESTION L.09 (2.00)
STATE the two-(2) conditions that must be met to allow a restart following a scra (2.0)
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- the SA During the initial test period of the . e a .2 t o r .
measurements and calculations of core parameters will be fcr standard assemblies which are to be utill:od in the reactor's operational progra .3 Radiation Monitor'ino 8policability These specifications apply to the surveillance of the area and air radiation monitoring equipmen Obioctive The purpose of these specifications is to ascure the continued validity of radiation protection standards in the facilit Soecification .
The criticality detector system, area gamma monitors, and the mobile particulate air monitor shall be checked daily if the reactor is operated, tested monthly, and calibrated semiannuall i Base's Experience has demonstrated that calibration of the criticality detectors, air gamma monitors, and the mobile air monitoring instrument semiannually is adequate to assure that significant deterioration in accuracy does not occu Furthermore, the operability of these radiation monitors is included in the daily pre-startup check list.
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- - . - - - ..- _ - - - , ,, _
- 3.3 Radiation Monitorina
Acolicability
. These specifications apply to the minimum radiation monitoring requirements for reactor operation *
Obtective The purpose of these specifications is.to assure that adequate monitoring is available to preclude undetected radiation ha:ards or uncontrolled releases of radioactive materia Soecif'ications ,
' The minimum complement of radiation monitoring equipment required to be operating for reactor operation shall
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include:
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'% A criticality detector system which monitcrs the main fuel storage area and also functions as an area men: to This system shall have a visible and an accible alarm in the control roo An area gamma monitoring system which shall have detectors at least in the following locations: (l'
Control roomi (2) Reactor room near the fuel vault: (3)
Reactor room (high level monitor), andi (4) Outside the reactor room windo Instruments to continuously sample and measure tne particulate activity in the reactor room atmosphere shall be operating whenever the reactor is to be operate The radiation monitors required by 3. a, b, and c, may be temporarily removed from service if replaced by an equivalent portable uni . Portable detection and survey instruments shall be provide Bases
. The continuous monitoring'of radiation levels in the reactor room and other stations assures the warning of the existance of any abnormally high radiation levels. The availability of instruments to measure the amount of particulate activity in the reactor room air assures continued complLance with the requirements of 10 CFR Part 20. The availability of required portable monitors provide assurance that personnel will be abla to monitor potential radiation fields before an area is entere In all cases, the low power levels encountered in operation of the critical assembly minimizes the probable existence of high l radiation levels.
l l
3.4 Exoeriments Aeolicability -
These specifications apply to all experiments placed in the reactor tan Obi _eetive The objective of these specifications if to define a set of criteria for experiments to assure the Safety of the reactor and l
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personnel.
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EQUATION SHEET
............................................___.................___ ........
.. .
Where mi = m2 (density)1(velocity)1(area)1 = (density)2(velocity)2(area)2
..............__..........._______....... _____..______ ......._____ .._____
PE3 + KEi +P11V = PE +KE where V = specific KE="{2 PE = mgh 2 2+P22Y volume P = Pressure
... ____.......______.__........_... ___________. __......____.._______.....
Q = mcp(Tout -Tin) Q = UA (T ave .Tstm) i) = m(hl-h2)
............... ________.....____________ ...___..... __...________ ..__ ...
P = Po et /T SUR = 26.06 T = -(B-p) t P = Po 10(SUR)(t) T p
_______......._ ..______..... __ . _......_____. _________..............._ delta K = (Keff-1) CR1(1-Keff1) = CR2(1-Keff2) CR = S/(1-Keff)
(1-Keff1) (1-Eeff) x 100%
SOM =
X M = (1-Keff2) eff
............._______. .......___......... ......_______......... ______.....
-
decay constant = In (2) = 0.693 t t A I=Ae(decayconstant)x(t)
1/2 1/2
..........____________....___....______________________...________ ..____...
Water Parameters Miscellaneous Conversions .
1 gallon = 8.345 lbs 1 Curie = 3.7 x 10 dps 1 gallon = 3.78 liters 1 kg = 2.21 lbs 1 f t3 = 7.48 gallons 1 hp = 2.54 x 103 Btu /hr Density = 62.4 lbm/ft3 1 MW = 3.41 x 106 Btu /hr Density = 1 gm/cm3 1 Btu = 778 ft lbf 1 Btu = 1055 w.sec Heat of Vaporization = 970 Btu /lbm Heat of Fusion = 144 Btu /lbm Degrees F = (1.8 x Degrees C) + 32 1 Atm = 14.7 psia = 29.9 in Hg 1 inch = 2.54 centimeters g = 32.174 ft.lbm/lbf-sec2
......__ ..__.._____ .................___ ...._........____..........___....
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Page 17 REACTOR THEORY
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I-ANSWER- H.01 (2.00)
l I- 'The fission rate increases generating additional fast neutrons CO.53 Reaction. rate begins to diverge on~ prompt neutrons alone C+0.53
-
Since reactor is not prompt critical additional power raise is d'ependent
,
on delayed neutrons C1.03 L.
6- , ..
REFERENCE 1.
l' RPI: SER, p. 14-3.
N Generic: Lamarsh, J. "Introduction to Nuclear Reactor
'"
Theory," p. 42 ANSWER H.02 (2.00)
drop due to removal of source and resulting reaction rate decrease [+0.5]
Neutron Population approximately linear
<-- decrease controlled by delay]edneutrons
[+1.0 curve shape
_
~
new stable level time (CR = S/1-Keff) on suberitical mnitiplication
[+0.5]
REFERENCE RPI: SER, p. 7- (***** CATEGORY H CONTINUED ON NEXT PAGE *****)
- - - _ - _ - _ - _ _ _ _______________________________J REACTOR THE0RY_
Page 18
L-ANSWER H.03- (2.00). The plutonium causes at (n,2n) reaction in the beryllium thus acting as a-source strength multiplier. .[+1.0] Remains the same [+0.5] - the half life of plutonium (24K years) is 'very 1 cog compared to the shutdown period (so no appreciable decay would take place) [+0.5].
REFERENCE RPI: SER, p. 7- ANSWER- H.04 (1.50)
Assumption: small worth experiment [+0.5]
Pnsitive reactivity would be inserted [+0.5] causing power to increase to the high flux trip setpoint and a scram would result [+0.5] .
REFERENCE RPI: SAR modification, p. 1 . RPI: SER, p. 7- .
b i
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- . _ _ . - . . . -- - . . , - . - , . - . - , - . - - . - - - , - . - - . - . . - . - - - ..
_ _ _ _ _ _ _ . ._ _- _ __ . _ _ _ _ _ . . _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ - - _ - _ _
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- H .- REACTOR THEORY Page 19
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ANSWER- H.0 (2.00)
water drain b l normal
_
Reactivity operation Fuel / Moderator Grading: graphshap_e-[+1.0]-
operating point (under-moderated) [+0. 5]
water drain indication [+0. 5]
REFERENCE RPI: Answers to SAR Questions, Oct'ober 1986, Table ANSWER H.06 (2.50) An increase in fuel temp decreases resonarce escape probability (increases resonance capture) (value of P decreases). [+0.5]
This effect is seen because: the microscopic cross section peak is lowered, but its effect is felt over a broader energy band
[+0.5] the overall probability for resonance capture during neutron slowing down through resonance energies is increased [+0.5] since resonance escape (P) is 1 - neutrons captured decreases by[+
0.5]resonance absorption then reactivity this effect is called Doppler or temperature broadening
[+0. 5]
(***** CATEGORY H CONTINUED ON NEXT PAGE *****)
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. REACTOR THE0RY Page 20
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' REFERENCE' Generic: Lamarsh, J. "Introduction to Nuclear Reactor Theory."
. ANSWER H.07 (2.50) * = prompt neutron generation time beta-i = average fraction of neutrons per. fission due to the i-th group of delayed neutrons lambda-i = decay constant for the i-th group of delayed
. neutrons
[+0.5] each There are six predominant groups of delayed neutrons, i.e.,
the fission process can be adequately described by. assuming six radioactive decay chains ~that generate all of the delayed neutrons. [+1.0]
REFERENCE RPI: "A Manual of Experiments for the Rensselaer Reactor Facility," Richard M. Kacich, May, 1975, pp. 37 and 38.
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Page 21 REACTOR THEORY
ANSWER H.08 (3.50)
2400 2000 l
1600 l 1200 l 800 l 400 l Po----- l 270 _
l 1 2 3 4 5 6 7 GRAPH fiOT REQUIRED IN SOLUTION P = Poe**t/ tau [+0. 5] tau = 6.5 see t = 7 sec + 60 ms = 7.06 sec (50 - 100 ms for neg insertion)
P = (675) e (7.06/6.5) = 2000 w [+1.0] Q = mCp delta T [+0. 5]
from a) Q = (675 + 2000/2) 7.05 = (1337.5) 7.05 = 9429.4 wa+.ts x 1 Btu /1055 w x s = 8.94 Btu [+1.0)
8.94 Btu
= 9 deg F [40. 5]
delta T = Q/mCp = 10 ---lbm x 0.1 Btu /lbm deg F (accept 8 to 10 det ;
'
REFEREf1CE RPI: Harris and Wicks (RPI) letter to Thomas (fiRC),
September 21, 198 (***** CATEGORY H C0tiTIl1VED Olif1 EXT PAGE*****)
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ANSWER H.09 (2.00)
Reactivity (f)
Rod Position (in)
[+0.5] for shape and [40.5] for axis labels The incremental rod worth is due to the shape of the neutron flux (essentially a chopped sine wave) [+0.5] and the effectiveness (worth /in) of the rod being (linearly) dependent on flux density (by R = flux x macroscopic cross-section)
[+0.5].
REFERENCE RPI: Manual of Experiments, pp. 41 through 4 (***** END OF CATEGORY H *****)
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-I.-~RADI0 ACTIVE MATERIALS. HANDLING DISPOSAL '
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AND HAZARDS ANSWER' I.01 -(3.00) . mix the reactor tank and storage tan'd using' fill and-dump [+0.75] evaporate a (1 1)' sample to dryness- [+0.76] measure activity of residue [+0.~ 7 5)
(if below allowable limit, pump to the river) The shutoff valve to the river discharge line (valve 8) is locked-shut with the-key in control of the SR [+0.75]
. REFERENCE
- RPI: Operating Procedure, May 1987, pp. 5 and . RPI: Piping Flow Diagram, i
a
1 (***** CATEGORY I CONTINUED ON NEXT PAGE*****)
. RADI0 ACTIVE MATERIAL 3 HANDLING DISPOSAL Page 24 AND HAZARDS
ANSWER I.02 (3.50)
Assumption A 3 curie gamma source will produce approximately 3 R at a distance of one meter [+0.5]. Two inches of lead will provide one half value thickness, i.e., 2" Pb --> I/2 [+0.5].
a) Prior to moving each is receiving 2 2 Id =Id I=3R d =2M d =IM 11 22 1 2 1
Id 2 11 3(1) 3 I = ---- = ---- = - R/hr [+0. 5]
2 2 2 4 d 2
b) Following their actions they receive Shielding case 4" PB = 2 HVL I = Io x(1/2)**2 [+0.5] = (0.75)(1/4) = 0.19 R/hr [+0.5]
.
,
Distance case i 2
) Id
!
11 I =3R d =2m+3m=5m I = -----
[+0.5] 1 2 2 2 d d =1M 2 1
- = (3R)(1)*+2/(5)**2 = 3/25 = 0.12 R/hr [+0.5]
(***** CATEGORY I CONTINUED ON NEXT PAGE *****)
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. RADI0 ACTIVE fMTERI ALS HANDLING DISPOSAL Page 25 AND HAZARDS
.
REFERENCE RPI: Equation Shee . RPI: Manual of Experiments, Appendix A, p.14 AflSWER I.03 (2.50)
rem = rad x rbe [+0. 5]
' rem neutron) = 10 x 3 = 30 [+0.5] rem beta) = 20 x 1 = 20 [+0.5] rem gamma) = 30 x 1 = 30 [+0.5]
Total dose = 80 rem /hr x 15 min = 20 rem [+0.5]
REFEREf1CE RPI: Personel Safety and Radiation Monitoring, p. ANSWER I.04 (3.00) REM per calendar quarter Quarterly Quarterly Average Maximum Whole body 1.25 3 Skin X [+0.5] each Extremities 18.75 X no occupational exposure is allowed until a person's 19th year (5(N-18)=0) [+1.0]
l REFEREllCE l Generic: 10CFR50.
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. RADI0 ACTIVE MATERIALS HANDLING DISPOSAL Page 26
- AND HAZARDS
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ANSWER I.05 (3.00)
Case 1 2 men x 2 rem /hr x 1/2 hr = 2 rem (1 rem each man) [+0. 5]
,
Caso 2 sheild manipulation 1 man x 2 rem /hr x 2/3 hr = 1.33 rem [+0. 5]
perform the job 2 mer x 0.2 rem /hr x 1/2 hr = 0.2 rem [+0.5]
Total = 1.53 [40f]
Alternative 2 because of ALARA considerations [+1.0]
(lower total radiation exposure)
REFERENCE RPI: Personncl Safety and Radiation Monitoring; pp. 1 and ANSWER I.06 (2.00)
-lambda t 0.693 0.693 -1 A=Ae lambda = --- = ---- = 0.041 s o '2 17 s in (A/Ao) = - lambda t t = 1/ lambda in (Ao/A) = 1/0.041 in (22) = 75.83 s
= 1.26 min (***** CATEGORY I CONTINUED ON NEXT PAGE *****)
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J 1.- RPI: Equation Shee . Generic: Murry, R. "Introduction to Nuclear Engineering," p.-2 ANSWER I.07 f(3.00) Yes [+0.5], the Technical Specifications require the criticality detector to be operating for reactor operation
[+1.0].
. Yes [+0.5], Section 3.3.1.d allows an equivalent unit replacement [+1.0].
Grading Note: There appears to be a conflict between Tech Spec 3.3.1.a and 3.3.1.d centering on alarms in the control roo Also how long may this condition exist? Section 4.3 is not definativ REFERENCE RPI: Technical Specifications, Section 3.3 (attached).
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Page 28 SPECIFIC OPERATING CHARACTERISTICS
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ANSWER J.01 (1.00) False [+0.53 (Loss of power to instrument scrams will not cause a trip) True [+0.5]
REFERENCE RPI: Instrumentation and Interlock Diagrams, Figure . RPI: SAR, p. 2 ANSWER J.02 (3.00) yes high power no yes high power no no no
[+0.5] each REFERENCE RPI: Instrumentation c,d Interlock Diagrams; Control Instrumentation Block Diagra ANSWER J.03 (2.00)
A bank withdrawal of one inch would produce a maximum reactivity change of approximately 21.5/ (from Figure 5) [+1.0]. This would induce a sitive reactor period of about 32 seconds (from Figure 1) [+ (accept 30to34 seconds)
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REFERENCE RPI: Technical Plant Datai Figures 1 and . Equation Shee AMSWER J.04 (3.00)
. Pump discharge (reactor tank fill valve) f6ils CLOSE.-
. [+0.5] To prevent inadvertent filling of the rer.ctor tank
, during abnormal condition [+1.0] Pump suction (return valve) fails OPE [+0.5] To provide a drain line from the reactor tank to the storage tank during times of abncemal conditions.- [+1.0]
Any two (2), +3.0. maximu ' REFERENCE RPI: Section 11,! Instrumentation and Interlock Diagram ANSWER J.05 '(1.50)
- This resistor linits the current surge (prevents fuses 1A and IB fromblowing)resultingfromshortingofthescramrelayswhich is necessary during an instrument scram [+1.5].
'
l RiiFERENCE RPI: Instrumentation and Interlock Diagrams, p. 4, Figure '
t
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ANSWER J.06 (3.00) rectifier AC input voltage [+0.5:
rectifier DC output voltage [+0.5]
b- input 110 VAC [+0.5] (accept 120)
output 110 VDC [+0.5] positive indication of power intr.rruption to scram solenoids [+0. 5]
positive indication of power interruption to the scram relays [+0.5]
REFERENCE RPI: Instrumentation and Interlock Diagram, pp. 4 and 5, Figure ANSWER J.07 (2.50) Hz power on fill pump off chart rer. order on reactor period <15 se . startup channel on and counts > 5
[+0.5] each REFERENCE RPI: Startup Procedure.
l ANE4ER J.08 (1.00)
.ength = 36" [+0.5]
worth = approx. 0.007 delta K/K [+0.5]
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t REFERENCE' t RPI: . Responses to Questions (March 3, 1987), p. ANSWER J.09 (1.00)
dump valve fails open draining anderator tank -[+0.6]
reactor will shut down [+0.4]
- REFERENCE RPI: Startup Procedures, Section .
ANSWER J.10 (2.00)
red: drep due te less of perfer (plant shut dern) [21. 0 !' '" '"
4 control rods cannot be moved due to 400 Hz interlock g{}:'. 0] J *-in 88 c onwt at co M1 itw rs t.cs r ' [0,57J C + 5)
REFERENCE RPI: Startup Procedure, Sections 14 ano 1 t
,
r (***** END OF CATEGORY J *****) .
9 y --- ,.-.ym--- t -F = -v" ------*-m - - - -- --
e-7-+i---~'--te --e ev w---- '= -*-t -- N v ?- * v - --?r *
-
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- FUEL HANDLING AND CORE PARAMETERS Page~32
.
ANSWER K.01- (2.00)
a.= [+0.5] ~false false (vault
~(Cd only)[+0.5]
lined)
c. . true (subtritical by rho = 0.10; $1.00 = 0.007) [+0.5] false {'enf er eperater enly), [+0.5]
'lE'FERENCE hun)vmd md RPI: Proposed Mcis to Technical Specifications, Section ANSWER K.02 (1.50)
critical [+0. 5] -
withdrawal
[+ known (measured) 5] [+0. 5]
REFERENCE 1. - 'RPI: Manual of Experiments, p. 4 ANSWER- K.03 (1.50) U0-2 or uranium dioxide [^0.5] .8 w/o [+0.5] for 4.6 to 5.0 w/o stainless steel [+0.5]
REFERENCE RPI: SAR, June 198 (***** CATEGORY K CONTINUED ON NEXT PAGE *****)
. - ... _ . .
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, FUEL HANDLING AND CORE PARAMETERS Page 33
.
ANSWER' K.04 (3.00) ' (1) too close (concavedown)'
1/M [+1.0]
(2) oper distance tj inear) [+1.0]
far (concave upward)
[+1.0]
fuel mass (criticality)
' REFERENCE RPI: Manual of Experiments, pp. 24 through 2 .
ANSWER K.05 (4.00) control rod bank reactivity worth [+0. 75] temperature and void coefficient of reactivity [+0.75] reactor power measurements [+0.75] snutdown margin [+0.75]
' These parameters must be measured to assure that they are within the limiting values analyzed in the Safety Analysis Report (SAR). [+1.0)
REFERENCE
. RPI: Technical Specifications, Section 4.2.
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J-ANSWER -K.06 (3.00) fully inserted [+1.0]
b. pS b The number of elements added at an
, hver e[+xcee] .dthatofthepreviousstep(proceduref.stepcan (Alternate - explain linear extrapolation error in 1/H method) [+0. 5] .
, Two count rates must be taken'at the same fuel loading [+0.5]
to ensure (subsequent readings of neutron flux are) referenced to a common base [+0.5] .
REFERENCE RPI: Manual of Experiments, pp. 29 and 3 ANSWER K.07 (2.00) net change in' reactivity must be < $0.72 reactor suberitical by at least $1.00 initially only one vacant position within active fuel lattice NIs on scale and dump valve not bypassed critical rod bank position checked following completion Any four (4) [+0.5] each, maximum + REFERENCE RPI: Proposed Technical Specifications Modifications, p. 5- (***** CATEGORY K CONTINUED ON NEXT PAGE *****)
_
] FUEL HANDLING AND CORE PARAMETERS Page 35 ANSWER K.08 (3.00) Power (fission rate) is directly proportional to thermal flux only (and to use total flux would introduce large errors). [+1.0] . strong absorption cross-section [+0.5] half-life that produces a workable activity for counting [+0. 5] Cadmium total flux toabsorbes epithermal thermal neutrons preferentially flux subtractio [+ ] allowing a REFERENCE RPI: Manual of Experiments, pp. 8-8 through 8-12.
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. 3 ADMINISTRATIVE PROCEDURES, CONDITIONS Page 36
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ANSWER L.01 (3.00)
y W:rkcur TWERr1M. S04fcE f prevent : nch"izib#"start-up'(instrumentoperabilityand low level rate visibility) [+1.0] damage occur duetotofuel (anyclad (exceeding analyzed) designatransient safety limit))will (s [+1.0] not allows time for safety channels to insert negative reactivity prior to significant energy deposition in the core [+1.0]
REFERENCE ,
. RPI: Technical Specifications, Section ANSWER L.02 (2.00)
WHEN - during maintenance checks [+0.5] and radiation surveys
[40.5]
PROVISIONS - Operations Supervisor permission [+0.5]
no other scram bypassed [+0.5]
REFERENCE RPI: Technical Specifications, Section 3.0, Table 1.
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ANSWER L.03 '(2.00)
- Tmin = 50 degrees F [+0. 5]
Maintain operation within the temperature range for which
- the net positive reactivity limit is applicabl (limit potential positive reactivity) [+1.0] thera.ocouple (readout) [+0.5]
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' REFERENCE RPI: Technical Specifications, Section 3. ANSWER L.04 (4.00)
Assume: not flammable, explosive or chemically reactive [+1.0]
1.- written proced tre approved by NSRB [+0.5]
basis: ensure experiment is well planned and evaluated for safety .[+1.0] the maximum reactivity worth of the sample must not exceed
$0.60 [+0.5]
basis: ensure that reactor controls are capable of overcoming the positive reactivity of the sample [+1.0]
REFERENCE RPI: Technical Specifications, Section 3.4.
ANSWER L.05 (1.50)
Since this error appears to be typographical, (no substantive change) [+0.5] the SR0 should get the approval of the Operations *
Supervisor to make a temocrary change to the Technical Specifications [+0.5]. it should be documented and subsequently
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reviewed by the NSRB (for incorporation in future Technical Specifications change submittal) [+0.5].
i REFERENCE l
l RPI: Technical Specifications, Sections 3.1, 4.1.2, and l ,
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! ANSWER L.06 (1.00)
l A system or component is capable of performing its intended function in its required manner. [+1.0]
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REFEREtiCE RPI: Technical Specifications, p. 1- AtiSWER L.07 (1.50) second [+0. 5] third T+0. 5' first l+ REFEREtiCE RPI: Emergency Procedures, p. AfiSWER L.08 (3.00) onuure th.t a 6eactor scram was initiated [+0.S) the SRO [+0.5) Yes (r esp i r ator s are mandatory since radioactive materials would be involved) C+0.S] No (manual on1y) L+0.S) Ellin hospital C+0.S] Schenectady Fire Department C+0.S]
REFEREt4CE RPI: Emergency Procedures, Section 6.2 and At1SWER L.09 (2.00) the cause of the scram has Leer, determined [+1.0] all conditions for operation are normal [+1.0]
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REFEREllCE RPI: Operating Procedure, p. (***** END OF CATEGORY L*****)
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'." ADMINISTRATIVE PROCEDURES, CO?iDITI0f4S Page 39 o AllD LIMITAT10ftS REFEREliCE RPI: Operating Procedure, p. 3.
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