ML20137J950

Exam Rept 50-027/OL-85-01 on 851213.Exam Results:One Reactor Operator Passed Written & Oral Exam.Exam & Answer Key Encl.Exam Results Withheld (Ref 10CFR2.790)

ML20137J950
Person / Time
Site:	Washington State University
Issue date:	01/07/1986
From:	Huenefeld J, Pate R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:
Shared Package
ML20137J924	List: ML20137J920 ML20137J950
References
50-027-OL-85-01, 50-27-OL-85-1, NUDOCS 8601230300
Download: ML20137J950 (40)

Text

. . _

Enclosure (1)

EXAMINATION REPORT 50-27/0L-85-01

FACILITY LICENSEE

Washington State University Nuclear Radiation Center Pullman, WA 99164-1300 FACILITY DOCKET NO.: 50-27 FACILITY LICENSE N0.: R-76 Examinations administered at the Washington State University Test Reactor, Pullman, WA.

Chief Examiner: / 12/3.7/g[

q/C'H~uene d IDat( Signed

/

Approved By: -

M J7N

/Dats Signed

[obertPate,BranchChief

SUMMARY

Examinations administered on December 13, 1985 Written and oral examinations were administered to one R0 candidate. The candidate passes these examinations.

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_. - ~ -- .

REPORT DETAILS

1. Examiner James C. Huenefeld

2. Examination Review Meeting The examination review meeting was conducted in conjunction with the exit meeting.

3. Exit Meeting At the conclusion of the examinations, an exit meeting was held with the licensee. Persons in attendance were:

J. C. Huenefeld -- Examiner W. E. Wilson -- Facility The facility was informed that the candidate was a clear pass on the operating portion of the examination. Facility concerns regarding the written examination were discussed during the exit meeting.

Subsequently the facility documented these concerns in a letter

" Wilson to Morrill" dated December 18, 1985. In conjunction with the Contract Examiner the NRC Region V reviewer resolved the facility comments as described in Attachment A.

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ATTACHMENT A TO REPORT 50-27/0L-85-01 ,

Resolution of Facility Comment:

1. The training manual for the GA reactor really does'not apply to our reactor. The WSU TRIGA reactor is a modified.TRIGA~ reactor, which means that it is an MTR plate type reactor with a square grid box that uses a special version of TRIGA type fuel arranged in 4-rod clusters. Consequently, taking questions from the GA training manual is not necessarily valid. We do not use this manual for training purposes.

Resolution: Comment accepted.

2. Question A7 is not an RO type question but rather an SRO type question.

Operators of a TRIGA reactor are not taught anything about DNB since it is not a significant parameter in a TRIGA type reactor as is the case with a power reactor.

Resolution: Comment not accepted. A general knowledge of this topic appears appropriate due to the power level of the WSU reactor.

3. Question A8 is ambiguous. The correct annwer listed for this question is even more confusing than the question. The actual " pulse tail" for the WSU cesctor with FLIP fuel is shown on attached Figure 19.

Resolution: Comment not accepted. The desired response was only intended to demonstrate general knowledge of the reactor response.

4. Question A9 does not state enough conditions for an operator to be able to answer the question. It depends upon the rate with which reactivity is added. An operator cannot be expected to understand all the fine points about reactor kinetics. An operator will think in terms of the way the reactor and associated instrumentation behaves rather than in terms of the predicted response based on the solution of the reactor kinetics equation. I see what the question is trying to ask, but it does not ask it in a manner that can be understood by a reactor operator. We tried this out and the result is a very suberitical reactor due to the lag in response of the period meter.

Resolution: Comment not accepted. As in Question A8, a general knowledge of this topic is appropriate. Knoaledge that a reactor's period depends upon both the reactivity and reactivity insertion rate does not appear unreasonable.

5. Question B.I.C--the current total worth of all the blades is $12.96.

Resolution: Comment accepted.

1

6. Question C.5--the value of the WSU TRIGA reactor's max henon is $3.15 eleven hours ?ter shutdown and the equilibrium valve is $2.70.

Resolution: Comment accepted.

7. Question C.8--this is not an R0 question but rather an SAO question.

We do not go into thermal hydraulics with operators; the overriding importance of the effects of the large prompt negative temperature coefficients of a TRIGA reactor is the prime consideration that allows pulsing and safe operation.

Resolution: Comment not accepted. Some knowledge of the reactor fuel dynamics appears appropriato.

8. Question E.1 -- at least 15 seconds; it really sounds for 30 seconds.

Resolution: Comment accepted.

9. Question G.5--poorly worded. Film badges for staff are charged monthly by pocket dosimeters; for visitors, etc. they are charged daily.

Resolution: Comment accepted. Either answer.is satisfactory.

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1 U.S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION .

Facility: Washington State University Reactor Type: TRIGA (Modified)

Date Administered: December 13, 1985

. Examiner: J. C. Huenefeld Candidate:

INSTRUCTIONS TO CANDIDATE:

4 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 i

indicated in parentheses af ter the question. The passing grade requires at least 70% in each category. Examination papers will be picked up six (6) hours af ter the examination starts.

' Category 1 of Candidate's  % of Value Total Score Cat. Value Category 16.5 A. Principles of Reactor Operation '

15.5 B. Features of Facility Design 16.0

C. General Operating Characteristics 13.0 D. Instruments and

! Controls

, 12.0

E. Safety and Emergency i Systems

. 14.0 F. Standard and Emergency Operating Procedures -

' 13.0 G. Radiation Control and -

Safety l

4 100 TOTALS

' Final Grade  %

4 All work done on this exam is my own. I have neither given nor received aid.

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A.0 PRINCIPLES OF REACTOR OPERATION (16.5 POINTS)

A.1 What is the maximum permissible reactivity worth of all experiments and irradiations installed at any one time? (1.0)

A.2 What is the minimum shutdown margin including all experiments and irradiations with the transient and regulating control elements fully withdrawn? (1.0)

A.3 Define shutdown margin. (1.0) l A.4 Fuel in the storage rack may have an effective multiplication constant of 0.8. --What value of reactivity does this correspond to? (1.5)

A.5 Control element calibrations require the measurement of doubling time. Given that power increases from 20% to 40% on the Linear Power Channel in 10 seconds, calculate the period. (show your work) (2.0)

A.6 Calculate the amount of uranium-235 that is fissioned in one (1)

MWD of operation given that: (2.0) 1.6 x 10-13 joule = 1 Mev Avagadro's i = 6.023 x 10 23 A.7 The maximum allowable power density is based upon the maximum steady-state power density at Torrey Pines TRIGA Mark III. The WSU TRIGA pool is deeper than that of the Torrey Pines TRIGA, so the maximum allowable steady-state limit at the Torrey Pines TRIGA is assumed to be conservative for WSU. Explain why pool depth makes the Torrey Pines value a conservative safety limit for the WSU reactor. (2.0)

A.8 Is the "after pulse tail" (i.e., the comparatively low power Tevel to which the reactor returns after a pulse) at a steady-state value prior to the transient rod SCRAM (about 8 secondsafterthepulse)? Explain. (2.0)

- Section A Continued on Next Page -

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2 A.9 The reactor is critical at a power level several orders of magnitude below the point of adding heat. A stable 10 second period is established. If rods are inserted continuously until period becomes infinite, and then the rod insertion is immediately stopped, will the reactor be critical, supercritical, or subcritiTaT7 Explain. (2.0)

A.10 Curve "A" on the trace below is a logarithmic plot of total neutron power versus time after a reactor trip. Curve "B" is a plot of the neutron power due to delayed neutrons alone versus time for the same trip. Explain why total neutron power (i.e.,

curve A) does not drop all the way down to the delayed neutron level (i.e., to curve B). (2.0)

A - TOTAL NEUTRCM PONER 8 - DELAYED ._,

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- End of Section A -

3 B.O FEATURES OF FACILITY DESIGN (15.5 POINTS)

B.1 a. The regulating rod (servo rod) is made of a different material than the other control elements. Of what material is it composed, and is its. total worth more or less than that of the other individual rods? (1.0)

b. What design feature helps to reduce the effects of viscous danping on the control blade fall time? (1.0)

c. To the nearest dollar, what is the total reactivity of all of the control elements including the transient rod and the regulating, and safety blades? (0.5)

d. What slows the control blades during the last phase of their travel? (0.5)

B.2 Draw a basic schematic of the Transient Rod Drive showing the bottom limit, the air supply hose with the three-way valve, the ball nut, the worm gear, the piston, and the externally threaded c.vlinder with vent holes. (2.5) 8.3 a. The pool water is cooled by circulation through a tube and shell heat exchanger. Does the heated pool water circulate through the . tube side or the shell

~

side of the heat exchanger? (0.5)

b. What is the ultimate heat sink for the heat generated by the reactor? (0.5)

c. What prevents an inadvertant draining of the reactor pool in the event of a piping rupture? (1.0) i B.4 a. Where in the purification flowpath does makeup water tap in? (1.0)

b. How does the makeup system compensate for pool evaporation? (1.5) l

c. Where in the pool is suction for the makeup and purification l system normally taken, and where does it normally discharge '

to? '

(1.5)

B.5 What type of elements surround three of the four sides of the reactor? (1.0)

- Section B Continued on Next Page -

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4 B.6 a. In what general vicinity of the core is the transient rod

, located? (1.0) i

b. In what general vicinity of the core is the rabbit tube located? . (1.0)

c. In what general vicinity of the core are the nuclear flux detectors located? (1.0) i i

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5 C.0 GENERAL OPERATING CHARACTERISTICS (16.0 POINTS)

C.1 a. The SAR specifies a peak adiabatic temperature limit as a safety limit for FLIP fuel. What is this safety limit? (1.0)

b. Is this limit higher or iower than that for standard fuel?

Eiplatn. (1.5) ,

C.2 There are three (3) separate effects that contribute to the prompt negative temperature effect. State these three (3) effects and indicate their relative importance. (1.5)

C.3 a. Give a brief definition of " Bath" temperature coefficient. (1.0)

b. Is the Bath temperature coefficient positive or negative at r60m temperatures? (0.5)

c. TRUE or FALSE. The prompt transient (i.e., pulsing) behavior of the TRIGA reactor is primarily determined by the Bath temperature coefficient. (0,5)

C.4 Sketch power versus time for a typical two dollar ($2) pulse of your TRIGA reactor and explain what causes power to return to a comparatively low level following the pulse rather than simply leveling off at a high power. (3.0)

, C.5 State the value of the reactivity associated with maximum peak xenon (i.e., the maximum reactivity of the xenon resulting from steady-state full power equilibrium xenon conditions). (1.0)

C.6 Peak power resulting from a pulse varies: (Selectone) (1.0)

, a. linearly with the amount of reactivity inserted for the

pulse.

! b. as the square of the amount of reactivity inserted for the pulse.

c. as the square root of the amount of reactivity inserted for the pulse.

d. as the cube of the amount of reactivity inserted for the pulse.

- Section C Continued on the Next Page -

6 C.7 TRUE or FALSE. The prompt negative temperature coefficient gets mc,re negative with increasing temperature when fuel temperature is greater than 300 degrees C. (0.5)

C.8 What radial position inside of the fuel element corresponds with the highest temperature following a maximum allowable power pulse? (1.0)

C.9 Experimental results show that the fuel can pressure varies linearly with pulse reactivity. Is this indicative of large scale release of hydrogen from the zTrconium hydride? Explain. (1.5)

C.10 Does the xenon peak occur sooner or later following a SCRAM from a low power level as opposed to a SCRAM from a higher power level? Explain.

(2.0) i 1

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- End of Section C -

7 D.0 PRINCIPLES OF REACTOR OPERATION (13.0 POINTS)

O.1 What is the function of the " Delay" switch in the rabbit control system? -

(1.5)

D.2 Should it become desirable to return the rabbit before the timer has reached zero, what must be done? (1.0)

D.3 What should be done if the " Granted" light does not light when the " Request Granted" switch is depressed? (1.5)

D.4 After reactor thermal power has been determined by performing a calibration run, how are the nuclear instruments adjusted to i read the correct power level? (1.5)

D.5 List eight (8) of the ten (10) console alarms that do not cause an automatic SCRAM. (2.0)

D.6 a. State the SCRAM trip setpoints for fuel temperature (in degrees C) , and power level (in % of full licensed power level). (1.0)

b. Besides the fuel temperature SCRAM and the high power SCRAM, there are six (6) other possible SCRAM input signals. State five (5) of these input signals. (1.5)

D.7 State the two (2) inhibits associated with the Wide Range Safety Channel. (1.0) 0.8 Where in the purification loop are the conductivity cells located? (1.0)

- Section D Continued on Next Page -

l .

8 i D.9 At least one of the fuel rods is instrumented. The instrumented l fuel rod (s): (Selectone) (1.0)

a. is (are) located in the peripheral fuel elements.

b.isa(are)standardtypeeiement(s).

c. is a (are) three rod element (s).

! d. is a (are) FLIP type element (s).

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- End of Section D -

4

• 9 E.0 S_AFETY AND EMERGENCY SYSTEMS (12.0 POINTS)

E.1 Describe the sound of the building evacuation alarm and state its duration. (1,0)

E.2 Describe the audible and visual indications for high radiation level'in the cave. (1.0)

E.3 The ventilation system is designated as an Engineered Safety Feature in the Technical Specifications. What is the operability requirement of that system, and how should it be operated in the event of a substantial release of airborne radioactivity? (3.0)

E.4 What is the function of each of the following reactor safety channels? (3.0)

a. Pulse-mode switch

b. Preset timer

c. Transient rod control E.5 TRUE or FALSE. The fuel element temperature channel will limit the peak power generated during a pulse. (0,5)

E.6 How often should a channel check of each of the reactor safety system channels be conducted? (1.0)

E.7 What is the difference between Experiment Safety Systems and Reactor Safety Systems? (2.0)

E.8 TRUE or FALSE. A non-operable fast recorder precludes critical operation. (0.5) i .

l - End of Section E -

i

10 F.0 STANDARD AND EMERGENCY OPERATING PROCEDURES (14.0 POINTS)

F.1 TRUE or FALSE. Samples to be lowered down a dry irradiation tube should be supported in the core region by a nylon or polyethylene line. . (0.5)

F.2 According to the startup procedure, SP 4, power should not be raised faster than what positive period? (1.0)

F.3 By procedure, criticality is achieved on what rod blade? (1.0)

F.4 The reactor is critical at a stable power level. How many people must be present at the Radiation Center and what qualifications must they have? (2.0)

F.5 Prior to a reactor startup, the expected fuel temperature is determined. How close should actual temperature be to the expected temperature? What must be done if that tolerance is exceeded? (1.0)

F.6 List three (3) types of Emergency Plan emergencies and gM one (1) example of each. (3.0)

F.7 TRUE or FALSE. Fuel moving operation must be under the direct supervision of a licensed reactor operator or senior reactor operator. (0.5)

F.8 During transfer of irradiated fuel elements, the elements shall be under at least feet of water at all times. (Select 4

one.) (1.0)

a. 1

! b. 5

c. 10

d. 20.

F.9 When a diver is in the reactor pool, the reactor must be in a l shutdown condition. What reactivity value corresponds to a '

shutdown condition? (1.0) l 1

- Section F Continued on the Next Page -  !

l 1

11 i

F.10 The Building Evacuation signal has sounded, what must be picked up by reactor personnel as they exit the building? (1.0)

F.11 A High Radiation Level in .the Radiochem Room is received.

According to the Standard Procedure for Actior, in Event of Alarm, SP-19, your action should be to: (Selectone.) (1.0)

a. initiate a building evacuation,

b. leave the area immediately and contact the campus police.

c. survey the area and take steps to reduce the radiation level.

5

d. proceed directly to the control room and inform the licensed operator on duty.

F.12 Of the console alarms not on the SCRAM chain, which ones require an immediate manual SCRAM (in accordance with SP-19)? (1.0)

- End of Section F -

12 G.0 RADIATION CONTROL AND SAFETY (13.0 POINTS)

G.1 Standard procedure No.1 gives conditions that must be met for irradiations. One of these conditions is that the maximum dose equivalent rate upon removal from reactor shielding not exceed:

(Select one.) (1.0) a 1 Rem /hr at 10 ft

b. 10 Rcm/hr at 1 ft

c. 1 Rem at 10 ft

d. 10 Rem at 1 ft.

G.2 What two (2) constraints are specifically placed upon the irradiation of explosive material? (2.0)

G.3 What precaution should be taken with a sample reading in excess of 100 mrem /hr at one foot over and above those required for a sample reading less than 100 mrem /hr at one foot? (1.0)

G.4 During routine surveys, the Health Physics Monitor is alerted to make note of any excessive dose equivalent rates. State the two (2) guidelines for excessive dose equivalent rates. (2.0)

G.5 How often is personnel dosimetry changed? (1.0)

G.6 According to the Standard Procedure for Calibration of the Area Radiation Monitors, SP-17, what are the area radiation monitor alarm trip points for the foTT6 sing: (1.5)

Reactor Bridge Sample Monitor '

, Cave Monitor.

G.7 Where does the pneumatic transfer system (rabbit) discharge its exhaust air to? (1.0)

G.8 What design feature ensures that activation gases do not escape from the thermal column and cause high airborne in that vicinity? (1.0)

- Section G Continued on the Next Page -

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G.9 Describe the design feature that minimizes the N 16 level at-the bridge. (1.5)

G.10 Approximately how many curies of Ar 41 are released from the WSU NRC annually'l (Selectone) -

(1.0)

a. .01 Ci

b. .1 C1

c. 1 Ci l d. 10 Ci I

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Where mi = m2

( densi ty)1( vel oci ty)1 ( a rea )1 = ( den si ty) 2 ( vel oci ty)2 ( area )2 KE = mv2 PE = mgh PEi +KEi +P1Vi = PE +XE 2 +E2 V22 wherE V = specific li , volume P = Pressure s

Q=se(Tout-Tin) p Q = UA (Tay,-Tstm) Q = m(ht -h2 )

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P = Po10(SUR)(t) p , poe t/T SUR = 26.06 T = (B-p)t f T P

delta K = (K,ff-1) CR 1 (1-Keffi) = CR 2 Il-Keff2) CR = S/il-KeffI

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i decay constant = In (2) = 0.693 A1 = Age-(decay constant)x(t) 1 t l 1/2 1/2 Water Parameters Miscellaneous Conversions 1 gallon = 8.345 lbs. 1 Curie = 3.7 x 1010 dps 1 gallon = 3.78 liters 1 kg = 2.2,1 lbs

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l 1 ft3 = 7.48 gallons 1 hp = 2.54 x 103 Btu /hr.

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i Density =62.4lbg/ft 1 MW = 3.41 x 106 Btu /hr

Density = 1 gm/cm 1 Btu = 778 ft-lbf '

Heat of Vaporization = 970 Btu /lbm Degrees F = (1.8 x Degrees Ci + 32 s Heat of Fusion = 144 Btu /lbm I inch = 2.54 centimeters 1 Atm = 14.7 psia = 29.9 in Hg g = 32.174 f t-lbm/lbf-sec2 \,

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U.S. NUCLEAR REGULATORY C0lHISS10H

, R OPERATOR LICENSE EXAMINATION E U DEC 20 M D 3n Fa::ility: Washington State University Reactor Type: TRIGA (Modified)

U O ' P'" E Date Administered: December 13, 1985 l '.*'

Examiner: J. C. Huenefeld 3 Candidate: Answer Key INSTRUCTIONS TO CA:lDIDATE:

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 af ter the question. The passing grade requires at g least 70% in each category. Examination papers will be picked up six (6) hours a*ter the examination starts.

Category  % of Candidate's  % of Valu? Total Score Cat. Value Category

'16.5 _ A. Principles of Reactor Operation 15.5 B. Features of Facility Design 16.0 C. General Operating Characteristics 13.0 __

D. Instruments and Controls 12.0 ,

E. Safety and Emergency

/ Systems i

14.0 F. Standard and Emergency Operating Procedures -

13.0 i

G. Radiation Control and

, i Safety 100 TOTALS

' Final Grade  %

All work done on this exam is my own. I have neither given nor received aid.

Candidate's Signature

. 4 0

e 4 A.0 PRINCIPLES OF REACTOR OPERATION A.1 ANSWER

$5.00

Reference:

SP 1, p. 5.

A.2 ANSWER

$0.25

Reference:

SP No. 1, p. 5.

A.3 ANSWER l Shutdown Margin: Shutdown margin shall mean the minimum shutdown reactivity necessary to provide confidence that (1) the reactor can be made subcritical by means of the control and safety systems, starting <

from any permissible operating conditions, and (2) the reactor will remain subcritical without further operator action.

Reference:

Technical Specifications p. 3.

A.4 ANSWER N = o. T (e *f'[-

- 0.2. f l

May also answer in $ f f value for B is indicated.

Reference:

SP 7, p. 2. g,q A.5 ANSWER P,2P,e.*

f */t b d 75 b '., 1 ; it. t gwa).3 fe le l sta W

2. : ta -

kAt<4. Y 3.$4a.bli t; %

Reference:

SP 16, p. 2. ,

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. 2 A.6 ANSWER About 1 gram 0 86400 Fission _" I MW

• 10 joules

• fission

• Mev x

MW - sec 202 Mev -l3 d*Y MWD 1.6 x 10 joule 21

= 2.67 x 10 This converts to grams of U-235 fissioned per MWD as follows:

21 Grams U-235 Fissioned , 2.67 x 10 Fissions x ##**

MWD 24 MWD .6023 x 10 atoms

Reference:

SP 20, p. 2. = 1.044 A.7 ANSWER The crucial concern regarding power density limits is whether or not critical heat flux is attained. Critical heat flux is the heat flux at which a departure from nucleate boiling would occur. An increase in pool depth implies an increase in the thermodynamic saturation pressure for the water surrounding the fuel elements. This increases the value of the critical heat flux.

Reference:

SAR Appendix, p. 2 A.8 ANSWER No. The fuel temperature overshoot is roughly a factor of two higher than the value corresponding to the power peak, and the fuel cool off time is on the order of a minute, so power will be increasing (supercritical on delayed neutrons only).

Reference:

Training Manual, p. 6-37 A.9 ANSWER The reactor will be supercritical. Because the reactor is " prompt subcritical," the insertion of negative reactivity will cause prompt

- power to turn before causing delayed power to turn. The "subcritical effect" of the prompt neutrons is prevalent because prompt neutrons comprise about 99% of all neutrons in the reactor.

Reference:

Training Manual, Section 6.2 ,

3 1

A.10 ANSWER The magnitude of the prompt drop is dependent upon the amount of negative reactivity that is inserted. The countrate above and beyond that due to delayed neutrons alor.e is caused by subcritical multiplication of the delayed neutrons. If an infinite amount of negative reactivity was inserted, then Curve A would fall immediately to 8 Curve B upon Rx trip.

Reference:

Training Nanual, Section 6.2 ,L l

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, B.O FEATURES OF FACILITY DESIGN B.1 ANSWER

a. Stainless steel, less reactive.

b. Small flow holes are drilled in the bottom of the shroud.

c. $14.00.

d. A dash pot on the control shaft.

Reference:

SAR pp. 4-14, 4-19, 5-1.

B.2 ANSWER See Figure 4.7-4 attached.

Reference:

SAR p. 4-21.

B.3 ANSWER

a. Tube side.

b. The atmosphere via the cooling tower.

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c. Appropriately placed siphon breaks.

i

Reference:

SAR pp. 4-24, 4-30.

B.4 ANSWER

a. At the suction to the recirculation pump.

b. A float switch in the pool actuates a solenoid valve in the makeup line.

c. Suction is taken from the pool surface via a surface skimmer and returned to a sump on the pool bottom.

Reference:

SAR pp. 4-30, 4-34.

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-b ONNECTION TO BOTTOM LIMIT =

CONTROL R00 G

4 Schematic Drawing of Transient Rod Drive FIGURE 4.7-4

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5 B.5 ANSWER Graphite Reflecter Elements.

Reference:

SAR p. 5-3.

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! B.6 ANSWER

a. In the center.

b. On the edge.

c. At all four corners.

Reference:

SAR p. 5-3.

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6 C.0 GENERAL OPERATING CHARACTERISTICS C.1 ANSWER

a. 1150 degrees C.

b. Higher. Standard TRIGA fuel nominally contains more hydrogen than does FLIP fuel.

Reference:

SAR Appendix, p. 2.

C.2 ANSWER Cell (mostsignificant)

Leakage Doppler (leastsignificant).

Reference:

Kinetics Section of GA Training Manual, p. 6-27.

C.3 ANSWER

a. The change in reactivity associated with a change in pool temperature.

b. Positive

c. False.

Reference GA Training Manual, p. 6-28.

C.4 ANSWER (and Reference)

, See SAR Figure 5.3-1, p. 5-16, (attached) and Figure 6.12, p. 6-36, in l the Training Manual. As fuel temperature increases, prompt insertion of l negative reactivity occurs. The return to low power is caused by a temperature overshoot by a factor of 2 of that coinciding with the peak.

C.5 ANSWER About 2.2% delta K/K. 3)S) y

Reference:

Training Manual, p. 6-34.

0

, , -,. _r..._._ .% , _ _ , . .

3-.. m-..

5-16 q Peak Power and Energy Release vs. Reactivity Insertion 2000 1

1750 1500 E'

1250 - -

25 a i

a y . W

n. X o

.o ~

to 3 3 1000 - -

20 -

o.

g

\

%  ?

E a 750 - ' -

15 500 .

o 10 250 - -

5 s

V -

t t t I e 1.25 1.50 1.75 2.00 2.25 2.50 Reactivity Insertion ($)

FIGURE 5.3-1 ,

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. 7 C.6 ANSWER b.

Reference:

Training Manual, p. 6-37.

C.7 False.

Reference:

Training Manual, p. 6-41.

C.8 ANSWER In the fuel immediately adjacent to the clad.

Reference:

Training Manual, p. 6-50.

C.9 ANSWER No. If the pressure increase were caused by a release of hydrogen from zirconium hydride, then the pressure increase would be exponential with reactivity. Temperature varies linearly with reactivity ... therefore, a linear increase in pressure implies a pressurization of the gas used to pressurize the fuel can. .

Reference:

Training Manual, p. 6-47.

C.10 ANSWER i It peaks sooner. This is because of the non-linearity in the behavior of equilibrium xenon. At lower power there is a disproportionate amount of direct xenon concentration in the core. This concentration causes a shift of the peak xenon value, causing it to peak sooner.

Reference:

Training Manual, p. 6-32.

O I

. . . ~-- - ,. --, - . . , -

8 D.0 INSTRUMENTS AND CONTROL I

D.1 ANSWER Depressing the " Delay" switch will result in a 10-second delay between the time the sample leaves the reactor core and the time the counting sequence starts.

Reference:

SP 2, p. 4.

D.2 ANSWER Depress the " Capsule Return" switch.

Reference:

SP 2, p. 5.

D.3 ANSWER If the " Granted" light does not come on after depressing the switch, check to insure that all receiver valves are shut.

Reference:

SP 2, p. 6.

D.4 ANSWER The detectors for the instruments are either lowered or raised until the indication matches the desired power level.

Reference:

SP 13, p. 5.

D.5 ANSWER Beam Port Plugs [+0.25 each for any eight (8)]

Blade Disengaged Conductivity Continuous Air Monitor Exhaust Gas Monitor Low Pool Water Level Low Pulse Air Alarm Neutron Flux Short Period Stack Gas Monitor.

Reference:

SP 19, p. 3-6. .

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9 D.6 ANSWER

a. Fuel temperature - 500 degrees C. Power level - 125% of full power.

b. Seismic Detection [+0.3 each for any five (5)]

! CIC HV failure Log-N HV failure Short Period 4

Bldg. Evacuation Manual.

Reference:

SAR, pp. 4-25, 4-28.

D.7 ANSWER t

Prevent initiation of a pulse above 2 KW Prevent control element withdrawal when ( 2 cps.

Reference:

SAR, p. 4-29.

D.8 ANSWER At the inlet to and the outlet from the mixed bed ion exchanger.

Reference:

SAR, p. 4-34.

D.9 ANSWER d.

Reference:

SAR, p. 5-3.

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10 E.0 SAFETY AND EMERGENCY SYSTEMS E.1 ANSWER A continuous stren sounding for 15 seconds.

Reference:

SP 19, p. 1.

E.2 ANSWER Visual - Red Light Audible - Pulsating high pitched tone.

E.3 ANSWER Specification: The reactor shall not be operated unless the facility ventilation system is operable, except for periods of time not to exceed 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> to permit repair or testing of the ventilation system. In the event of a substantial release of airborne radioactivity within the facility, the ventilation system will be secured or operated in the dilution mode to prevent the release of a significant quantity of airborne radioactivity from the facility.

Reference:

Tech Specs, p. 13.

E.4 ANSWER Pulse-mod switch - Prevents withdrawal of standard control and regulaion elements in the pulse mode.

Preset timer - Transient rod scram 15 seconds or less after pulse.

Transient rod control - Prevents application of air unless fully inserted.

Reference:

Tech Specs, p. 11.

E.5 ANSWER False. - Temperature response time is too long.

Reference:

Tech Specs, p. 7.

e 1

11 E.6 ANSWER A channel check of each of the reactor safety system channels for the intended mode of operation shall be performed before each day's operation or before each operation extending more than 1 day. (Note:

The pool level channe; is checked monthly.)

Reference:

Tech Specs, p. 20.

E.7 ANSWER Reactor Safety Systems: Reactor safety systems are those systems, including their associated input circuits, designed to initiate a scram for the primary purpose of protecting the reactor or to provide information that requires protective action to be initiated.

Experiment Safety Systems: Experiment safety systems are those systems, including their associated input circuits, that are designed to initiate a scram for the primary purpose of protecting an experiment or to provide information that requires manual protective action to be initiated.

Reference:

Tech Specs, pp. 4 and 5.

E.8 ANSWER False.

Reference:

SP 4, p. 2.

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. 12 F.0 STANDARD AND EMERGENCY OPERATING PROCEDURES 1

i F.1 ANSWER False.

Reference:

SP No. 1, p. 9.

F.2 ANSWER I

10-second period.

Reference:

SP 4, p. 4.

F.3 ANSWER No. 2.

i

Reference:

SP 4, Appendix A.

F.4 ANSWER

Two (2). One individual licensed reactor (or senior) operator and one

! individual capable of following written procedures.

Reference:

SP 4, p.il.

I F.5 ANSWER Within i 10 degrees Notify the Senior Operator immediately.

Reference:

SP 4, p. 4.

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_ , _ . , _ , , , _ ____ , _ , _ _ , . _ _ , . _ . . ~ , . , _ . . . . . _ _ _, ,

~

13 F.6 ANSWER

1. Safety Event--(Non-Reactor Related)

a. Personal injury with or without radiological complications.

b. Minor facility or individual contamination.

c. Minor fire or explosion unrelated to the reactor or the reactor control system. -

2. Unusual Event--(Reactor Related)

a. Reactor Effluent Alarm >10 MPC at site boundary or concentration in exhaust causing 15 mrem W.B. Dose in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b. Fire or explosion related to reactor.

c. Civil disturbance or bomb threat.

, d. Earthquake.

! e. Failure of in-core experiment or irradiation.

f. Sounding of Building evacuation.

3. Alert

a. Reactor Effluent Alarm >50 MPC at site boundary or concentration in exhaust causing 75 mrem W.B. Dose in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b. Radiation level at site boundary of 20 mrem /hr for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or 100 mrem Thyroid Dose in I hour.

c. Significant fire or explosion in Reactor related area. .

d. Failure of in-core experiment or irradiation with a significant release.

e. Exceeding a safety limit.

f. Fuel element failure.

g. Low pool level alarm with abnormal loss of water.

Reference:

SP 6, p. 1.

F.7 ANSWER False.

Reference:

SP 7, p. 1.

F.8 ANSWER c.

Reference:

SP 7, p. 1.

e

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i 1

i 14 F.9 ANSWER

$1.00.

l

Reference:

SP 9, Tech Spec p. 2.

i i F.10 ANSWER i

! The Emergency Kit.

1 i

Reference:

SP 19, p. 1.

i F.11 ANSWER C.

1.

1

Reference:

SP 19, p. 2.

l J.

, F.12 ANSWER Beam Port Plug Alarm

Low Pool Water Level.

{

Reference:

SP 19, p. 2.

I -

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, _ . _ , _ _ . _ . - - _ _ - , . _ . , _ . , . ~ ~ . . _ . . - , _ , _ _ _ . _ _ . . _ . . . _ , . _ _ _ _ _ _ _ , _ _ , - - __-_,.t-______m_._._, s . .- .. , - -._ . ...

i i .

15 G.0 RADIATION CONTROL AND SAFETY i

G.1 ANSWER j b.

l

Reference:

SP 1, p. 1.

i i G.2 ANSWER T

l 1. The maximum quantity of explosive material irradiated at any one time shall not exceed 25 milligrams.

2. Explosive material must be encapsulated in a container that will not burst if the material were to detonate.

Reference:

SP 1, p. 5.

G.3 ANSWER t

The higher reading sample must be suspended in the reactor pool or placed in a suitable shield and locked in the cave room barring other special arrangements. ,

Reference:

SP No. 1, p. 10.

I G.4 ANSWER J l

a. Rates in excess of 50 mrem /hr in a Radiation Area.

b. Rates in excess of 1 mrem /hr in an unrestricted area.

Reference:

SP 10, p. 3.

G.5 ANSWER

! Monthly.

Reference:

SP 10, p. 4.

i .

i 1

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. - . . . - , . - _ . _-. -._. , - ,_ - . , _ _ . ~ _ , _ - _ , , . , , . - . . - , , - , , _ . . . , _ , , , , , . , _ , , , ,_. ,,_ ,--__,- -.._, __ ..,,

_. .- _ _ = . _ _,_ - . _ . - .. . - - _ _ __.

. 16 l G.6 ANSWER

Reactor Bridge 200 mR/hr Sample Monitor 100 mR/hr Cave Monitor 50 mR/hr.

G.7 ANSWER Into the monitored facility ventilation system.

Reference:

SAR, p. 35.

G.8 ANSWER The monitored ventilation system keeps a negative pressure on the thermal column.

Reference:

SAR, p. 35.

4 G.9 ANSWER i

i A diffuser system consisting of a centrifugal pump and a discharge l nozzle was installed. This system pumps water from the surface of the pool and discharges it downward and across the top of the core, increasing the transport time of N-16 to the surface. ,

l

Reference:

SAR, p. 35.

G.10 ANSWER d.

4 l

Reference:

SAR, p. 6-13.

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EQUATION SHEET

___ ._______...___._____________________..______........__.___...__ .___._ m Where mi = m2 (density)1(velocity)1(area)1 = (density)2(velocity)2(area)2

___________..........____ ......._______....__________ __.___.___._____... hs

! 2 where V = specific KE = mv PE = mgh PEi +KEi+P iV1 = PE +KE 2 2 V22

+P volume li P = Pressure ,

Q = UA (T aye -Tstm) Q = m(ht -h2 )

Q = mcp (Tout-Tin) p , p e t/T SUR = 26.06 T = (B-p)t P = Po10(SUR)(t) o T p i

CR1 (1-Keff1) = CR2 Il~Keff2) CR = S/(1-Keff) l delta K = (Keff-1) i i

SOM = (1-Keff) x 100%

M = (1-Keffi) ll-Keff2) Keff decay constant = In (2) = 0.693 Ag = An e-(decay constant)x(t) t 1/2 t1/2 i

Water Parameters Miscellaneous Conversions 1 gallon = 8.345 lbs 1 Curie = 3.7 x 10 10 dps  !

1 gallon = 3.78 liters 1 kg = 2.21 lbs I ft3 = 7.48 gallons 1 hp = 2.54 x 103 Btu /hr 3 1 MW = 3.41 x 106 Btu /hr Density = 62.4 lbg/f t 1 Btu = 778 f t-lbf l Density = 1 gm/cm Heat of Vaporization = 970 Btu /lbm Degrees F = (1.8 x Degrees C) + 32 Heat of Fusion = 144 Btu /lbm 1 inch = 2.54 centimeters 2 i

1 Atm = 14.7 psia = 29.9 in Hg g = 32.174 f t-lbm/lbf.sec O

f I

9 a

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