ML20151E667
| ML20151E667 | |
| Person / Time | |
|---|---|
| Site: | 05000083 |
| Issue date: | 07/05/1988 |
| From: | Arildsen J, Brockman K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20151E656 | List: |
| References | |
| 50-083-OL-88-01, 50-83-OL-88-1, NUDOCS 8807260165 | |
| Download: ML20151E667 (200) | |
Text
{{#Wiki_filter:- . , x. ENCLOSURE 1 , EXAMINATION REPORT 83'0L-88-01 l Facility Licensee: University of Florida ' 202 Nuclear Sciences-Center Gainesville, FL 32611 Facility Name: . University of Florida Training Reactor Facility Docket No.: 50-83
! Written examinations and operating tests were administered at the University of Florida in Gainesville, Florida. ,
Chief Examiner: 2o ; ruse 1988
'e A. Arildsen Date Signed Approved by: [sdAshd Kenneth E~. Brockman, Section Chief r 7vtY i9eb Date Signed Operator Licensing Section 2 Summary:
e Examinations on June 8-9, 1988. Operating tests were administered to two candidates, two of whom passed; two candidates were administered written examinations, one candidate passed. Based on the results described above, zero of one R0's passed and one-of one SR0's passed.
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k s-REPORT DETAILS
- 1. Facility Employees Contacted: H
- W. G. Vernetson, Director of Nuclear Faci.ities, UFTR
. P. M. Whaley, Reactor Manager, UFTR
- Attended Exit Meeting
- 2. Examiners:
*'J. A. Arildsen K. E. Brockman
- Chief Examiner
- 3. Examination Review Meeting At the conclusion of the written examinations, the examiners provided Dr. Vernetson with a copy of the written examination-and answer key for review. There were no facility comments.
- 4. Exit Meeting 7
At the conclusion of the site visit the examiners met with representatives i of the plant staff to discuss the results.of the examination and forthcoming changes to procedures and other UFTR material. The cooperation given to the examiners and the effort to ensure an atmosphere in the control room conducive to oral examinations was noted and appreciated. The licensee did not identify as proprietary any of the material provided to or reviewed by the examiners. 1 v a = 1 e
[JRC 0,1 f ic ia l Uce Only MAST 6R Ro Nuclear Regulatory Commission Operator Licensing
** Examination This document is removed from Official Use Only category on date of examination.
1 l l' NRC Official tise Only (
s % U.-S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION FACILITY: UNIVERGITY OF FLORIDA REACTOR TYPE: TEST DATE ADMINISTERED: 88/06/08 EXAMINER: ARILDSEN. J. CANDIDATE: __
. 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 paperu'will be picked up six (6) hours after the' examination starts.
% OF CATEGORY % OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY 15.00 15.04 A. PRINCIPLES OF REACTOR OPERATION 15.00 15.04 B. FEATURES OF FACILITY DESIGN 13.75 13.78 C. GENERAL OPERATING CHARACTERISTICS 13.00 13.03 D. INSTRUMENTS AND CONTROLS 14.75 14.79 E. SAFETY AND EMERGENCY SYSTEMS '~.00 iT.?' F. STANDARD AND EMERGENCY OPERATING PROCEDURES 13.25 15.29 G. RADIATION CONTROL AND SAFETY ^?.75 % Totals Final Grade All work done on this examination is my own. I have neither given nor received aid.
Candidate's Signature l l l l 1 3 . . _ . . ,. . . _ . _
n. I ) NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the cdministration 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 mur,t avoid all contacts with anyone outside the examination room to avoid even the appearance or oossibility 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. ,
S. 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 uection of the answer sheet.
B. 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 sheetr from pad and place finished answer sheets face down on your desk or cable.
- 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. ,
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- 14. Show all calculations, methods, or apsumptions 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 )
DUESTION 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.
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- 17. You must sign the statement on the cover sheet that indicates that the l work is your own and you have not received or been given assistance in I completing the examination. This must be done after the examination has ;
been completed.
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- 10. 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.
i Ao PRINCIPLES OF REACTOR OPERATION PAGE 2 1 i OUESTION A.01 (1.00) A reactor has been operating for an extended period of time at 50% reactor power. WHICH ONE of the following statements most accurately describes the concencration of samarium-149 11 power were increased to and maintained at 7S% reactor power?
- a. The concentration of Sm-149 initially increases and then levels off to a new equilibrium level higher than the equilibrium level et 50% reactor power.
- b. The concentration of Sm-149 initially increases but then decreases to an equilibrium level eqaal to the equilibrium level at 50% reactor power.
- c. The concentration of Sm-149 initially decreases and then levels of. to a new equilibrium level lower than the equilibrium level at 50% reactor power.
- d. The concentration cf Sm-149 initially decreases but then incre anes to an equilibrium level equal to the equilibrium levet at 30% reactor power.
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A, PRItICIPLES OF REACTOR OPERATION PAGE 3 QUESTION A.02 (1.50)
- a. DEFINE "thermal nonleakage factor". (0.5)
- b. EXPLAIN HOW the thermal nonleakage f ac. tor can be (1.0) greater than one.
4 (***** CATEGORY A CONTINUED ON NEXT PAGE *****)
~4 A. PRINCIPLES-OF REACTOR OPERATION- PAGE 4 s
GUESTION A.03 (1.00) Reactor power is 100 watts and increasing with a constant reactor period. FOUR (4) minutes later, reactor power is 2 KW. CALCULATE the reactor period during the last four minutes. SHOW ALL WORK! l (***** CATEGORY A CONTINUED ON NEXT PAGE *****) i
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s A, PRINCIPLES OF RFACTOR OPERATION < PAGE 5 9 QUESTION A.G4 (2.00) Reactor power is 2KW with rods in the following pocitions: Safety Diade #1 - Fosition 1000 Gafety Diade #2 - Position 1000 i Safety Blade #3 - Position 1000 Regulating Dlade - Position 400 CALCULATE the period one (1) minnte after a scram. SHOW ALL WORK! (ASSUME a' Lambda of 0.0124 ,and a Pete Effective of 0.0065.) NOTE: APPLICADLE GRAPHS ARE ATTACHED GUR = Startup Rate = Decades / Minute t' W , (***** CATEGORY A CONTINUED ON NEXT PAGE *****)
,A. PRINCIPLES OF REACTOR OPERATION PAGE 6 l l l i l QUESTION A.66 (2.00) l For each of the following definitions, STATE the term tha' is derfined , l
- a. The factor by which neutron population changes between generations (from f issi on ) . '
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- b. The decay of an excited nucleus into a stable nucleus with the ,
i simultaneous ejection of einctr omagnetic energy. ;
- c. The amount of time required for the neutron populatinn to increase by a factor of "e" (2.718).
- d. A gamma ray causes the ejection of an electron from a target stomt the gamma roy's energy is totally transmitted to the electron for ejection.
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A. PRINCIPLES OF REACTOR OPERATION PAGE 7 I' I: QUESTION- A.06 (1.00) i Which one of the following describes the beta decay of a nuclide?
- a. Atomic Mass # decreases by 1, number of protons remains constant
- b. Atomic Mass # remains the same, number of protons increases by 1
- c. Atomic Mass # remains the dame, number of protons remains constant
- d. Atomic Mass # decreases by.1, number o' protons decreases by 1 i
- i ;
(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
; A. PRINCIPLES OF REACTOR OPERATf0N PAGE O QUESTION A.07 (1.00)
Which one of the'following terms of the six factor formula is most affected by "Poisons".
- a. Fast Fission Factor
- b. Thermal Utilization Factor c.. Thermal Non-Leakage Probability
- d. Reproduction Factor P
l l l i 1 l J (***** CATEGORY A CONTINUED ON NEXT PAGE *****) i I l l 1
l-A. PRINCIPLES OF REACTOR OPERATION- PAGE 9 s v 6 QUESTION A.00 (1.00) Which one of the following statements concerning the reactivity values o , 9 equilibrium (at power) xenon and peak (after shutdown) xenon is correct? Assume shutdown occurs from equilibrium conditions,
- a. Equilibr ium_ xenon in INDEPENDENT of power level;-peak xenon is INDEPENDENT of power level. 4
- b. Equilibrium xenon is INDEPENDENT of power level; peak xenon is DEPENDENT on power ilevel. !
- c. Equilibrium xenon is DEPENDENT on po we ,- level; peak xenon is INDEPENDENT of power level.
- d. Equilibrium xenon is DEPENDENT on power level; peak xenon is DEPENDENT on power level.
I h a l l l i l l (***** CATEGOF,Y A CONTINUED ON NEXT PAGE *****) 4
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.A. PRINCIPLES OF REACTOR OPERATION .i PAGE 10 t
GUESTION A.09 (1.003 ! I
-The ratio'of;Pu-239 and Pu-240 atoms to_U-235 atoms changes over core life.
Which one of the following pairs'of parameters is most'affacted by this c han g e? '- _i a). -Moderator Temperature coefficient and Doppler Coefficient !
.$ i b). Doppler Coef ficient and Betag e- '
4 c). Deta and Moderator Temperature Coefficient ' d). Moderator Temperature Coefficient and Neutron Generation Time , h s I i 5 4 ) i 't ll b
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i 4 s s (***** CATEGORY A CONTINUED ON NEXT PAGE *****) .t 1 ? 1
y D PRfNCIPLES OF REACTOR OPERATION 11
,A. , t- PAGE l
r , GUESTION (: .10 (1.00) t WHICbONEof the following factors han the LEAST effect on the'value of rod war th7
- a. Nun.ber and location of adjacent control rods. ,
- b. Temperature of the moderator,
- c. Temperature of the fuel.
- d. Core ' age.
f p 1 i I (***** CATEGORY A CONTINUED ON NEXT PAGE *****) l l l
p. A. PRINCIPLES OF REACTOR OPERATION ] PAGE 12 i QUESTION l%.11 (2.50) DEFINE EACH of the following terms:
- a. Suberitical multiplication
- b. Reflector
- c. Xenon burnout
, d. Decay heat r
- e. Differential rod worth l
t l ,) (***** END OF CATEGORY A *****) l l
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B4 FEATURES OF FACILITY! DESIGN PAGE 13 T >
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- QUESTION D.01 (2.00)
ANSWER EACH of the following questions TRUE or FALSE.
- a. The Primary Reactor Cooling Sys?.em does not contain any valves which could be left in the wrong position and restrict or shut off the primary flow without activation of the Reactor Protection System,
- b. The Primary Coolant System ir protected by a Graphite Rupture Disc set to burst at 7 PSI above the normal operating pressure.
- c. The Primary Water Makeup System connects to the Coolant Storage Ta.k via the Purification System. 1
- d. The Secondary Cooling System Sample Tank is normally kept isolated during Reactor operation.
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B. FEATURES OF FACIL ITY DESIGN PAGE 14 i GUESTION B.02 (2.50) ANSWER EACH of the following questions concerning UFTR design features. (FILL IN THE DLANKS)
- a. The Multiple Blade Withdrawal Interlock prevents exceeding
- c. reactivity addition rate of per second as specified in Technical Specifications,
- b. The UFTR is designed to operate at a rated power of .
- c. The core excess reactivity at cold critical, without xenon '
poisoning, shall not exceed .
- d. The UFTR is heterogenous in design, using percent ,
enriched fuel elements. 4 4 4 i
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D. FEATURES OF FACILITY DESIGN . PAGE iS GUESTION B.03 (1.00) GTATE what is used to separato and secure fuel assemblies to 4 < prevent lateral and vertical movement, assure proper flow, and a constant fuel to moderator ratio. l I i I i 1 d l (***** CATEGORY D CONTINUED ON NEXT PAGE *****)
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.B. FEATURES OF FACILITY DESIGN PAGE 16 3-QUESTION D.04 (1.00)
GTATE the purpose of the sixteen (16) vertical foil slots in - the Reactor. f f 4 4 i I (***** CATEGORY B CONTINUED ON NEXT PAGE *****) j I I i l e w -- - -m-, w y ,, ,m o +w- m ,- - 4.-y,- , -n-4m
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B. FEATURES OF FACILITY DESIGN , PAGE 17 t GUESTION B.05 (2.00) , i ANSWER EACH of-the following questions concerning I the Core Vent System.
- a. STATE the purpose of the Vacuum Breaker Vent Lines. (1.0)
, b. Where 17 the Ef fluent Gamma Detector located ? (0.S) ; l , c. The Vent Damper is. electrically interlocked so that 1 it cannot be opened unless the dilution fan is energi od. STATE the purpose of this interlock. (0.5) L I i 3 i 1 l i
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D. FEATUREG OF FACILITY DEGIGN '., PAGE 18 , I f QUESTION B.06 (1.00) STATE two (2) purposes crf the graphite blocks in the core. i r Y 1 i i i . (***** CATEGORY D CONTINUED ON NEXT PAGE *****) j l l 1
D. FEATURES OF FACILfTY DESIGN PAGE 19 l
, 'I OUESTION D.07 (2.00) ao STATE the purpose of the Reactor Vent System,
- b. LIST two (2) radioactive gases produced within the UFTR 1
that'are removed from the Reactor Cell by the Vent System. 1 x 1 N I a l .i I ) 1 1 l I i (***** CATEGORY B CONTINUED ON NEXT PAGE *****) . f r
'i. .Do FEATURES OF FACILITY DESIGN PAGE 20 I
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;, QUESTION B.08 (1.50)
'i' y tap water is used for makeup to the Primary System.
E...' LAIN HOW this water is purified to comply with Tech Spec
- requirements. Include in your answer a discussion of the physical processen by which the water is purified.
4 e (***** CATEGORY D CONTINUED ON NEXT PAGE *****) ; 1 J
Bn FEATUREG OF FACILITY DESIldi PAGE 21 QUESTION B.09 (2.00) STATE the PURPOSE of the following components of the Coolant f,5orage Tank AND HOW (by design) each one accomplishes this purpose.
- a. Diffuser
- b. Ducket Badfie
.I i 1 (***** END OF CATEGORY D *****) I 1
,C. GENERAL OPERATING CHARACTERISTICS 4 PAGE- 22 GUESTION C.01 (2.00)
_ Reactiv,ity in the core has been determined to be.-0.1230 delta k/k. CALCULATE how much the Safety Blades must be~ withdrawn to increase the present coun't. rate by 50%. SHOW ALL WORK! NOTE: APPLICADLE CURVES ARE ATTACHED FOR REFERENCE ASSUME ALL RODS WERE INITIALLY FULLY INSERTED
,. ASSUME ALL ROD WITHDRAWALS ARE PERFORMED IN SEQUENCE AND THAT THE FIRST ROD IS FULLY WITHDRAWN BEFORE THE NEXT ROD BEGINS ANY WITHDRAWAL i
(***** CATEGORY C CONTINUED ON NEXT PAGE *****) j
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,C. GENERAL' OPERATING CHARACTERISTICS PAGE 23
-QUESTION C.02 (1.00)
WHICH ONE of the following is the reason for the -80 second period following a reactor scram?
- a. The doppler'effect adding positive reactivity due to the temperature decrease following a scram.
- b. The ability of U-235 to fission with source neutrons.
- c. The amount of negative reactivity added on a scram being. greater than the Shutdown Margin.
- d. The decay constant of the longest-lived group of delayed neutrons.
l 4 (***** CATEGORY C CONTINUED ON NEXT PAGE *****) ) l 1
d.' GENERAL OPERATING CHARACTERISTfCS, PAGE24 QUESTION C.03 (1.00) Attached Figure # 219 shows a POWER HISTORY and four possible XENON _ traces (Reactivity vs. Time). SELECT the most accurate curve for-displaying:the expected XENON transient. i i l s (***** CATEGORY C CONTINUED ON NEXT PAGE *****)
C .~ GENERAL OPERATING CHARACTERfSTICS ' PAGE' 25 l 1
-QUESTION C.04 (1.00) ,
l WHICH ONE (1) of the following Control Blades has the LEAST l amount of integral rod worth. )
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- a. Safety Blade #1 ;
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- b. Safety Blade #2 ;
- c. Safety Blade #3
- d. Regulating Blade e
a k 1 (***** CATEGORY C CONTINUED ON NEXT PAGE *****)
,C. GENERALJPERATING CHARACTERISTICS PAGE 26 -QUESTION C.05 (1.00) NHICH ONE (1) of the following is the expected maximum equilibrium Stack Monitor level usually indicated at 100 KWth power, a t.
- c. .,c ps
- d. 2000 cps
(***** CATEGORY C CONTINUED ON NEXT PAGE *****)
J. GENERAL OPERATING CHARACTEBj_STICS PAdE 27 QUESTION C.06 (2.50) FILL IN THE BLANKS with the normal operating values at
'iOO % Reactor power with the main secondary cooling system in operation (Except for part e),
- a. Primary. Coolant normal flow rate .
- b. Reactor inlet temperature .
- c. Reactor outlet temperature .
d., Temperature Coefficient of Reactivity ,
- e. Increase in above temperatures ( b&c )
using the backup secondary cooling system . O l l i l l
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(***** CATEGORY C CONTINUED ON NEXT PAGE *****)
C.- GENERAL OPERATING CHARACTER 2STICS PAGE 28 QUESTION C.07 (1.25) It is-desirable' to. operate a Reactor with.a negative moderator coefficient. Hence, I conclude " The more negative the better ". STATE whether you agree or disagree with this statement and EXPLAIN your answer. (***** CATEGORY C CONTINUED ON NEXT PAGE *****)
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..Co GENERAL' OPERATING CHARACTERISTICS PAGE 29 i
OUESTION C.08 (2.00)
- a. STATE the I;FTR monthly energy generation limit. , (0.S)
- b. EXPLAIN the DAGES fc>, this limitation. (1.S) 4 J
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(***** CATtiCORY C CON 1INUED ON NEXT PAGE *****) I i I i
I. C. GENERAL OPERATING;C_HARACTERISTICS PAGE 30
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GUESTION C.09 (2.00) '
- a. DRAW and-LABEL, on the, sketch below, the variation of' thermal s neutron flux through'th'o core and the reflector. ,
- b. SUPERIMPOSE on the sketch below the shape of the. thermal neutron flux without a reflector present. (Disregard areaa labeled graphite)
I G i F 1 G 1 F I G I I R I U i R 1 U l R I I A I E I A 1 E i A I
! P 1 L I P I L 1 P 1 1 H I I H I 1 H I
! I ! I I i 1 I I I T , I T I I T 1
! E I I E I I E I
! I I ! ! I I I I I i 1
! ! I ! ! l t
(***** END OF CATEGORY C *****) ! i l I I i
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D. INSTRUMENTS AND CONTROLS t PAGE 31 s I QUESTION P.01 (2.00) ANSWER EACH of the.following questions TRUE or FALSE.
- a. The console " Power ON " switch centrols power to all pa.e b d N control circuits and nuclear instrumentation channels. ,
- b. Control Blade magnet power is controlled through the '
3-position " OPERATE " key switch,
- c. Depressing a Control Blade backlit ON switch will cause that Blade to return to the full in position.
- d. A key operated switch on the back of the console controls the Secondary System City Water Valve.
(***** CATEGORY D CONTINUED'ON NEXT PAGE *****)
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,D. INSTRUl1ENTS AND' CONTROLS PAGE 32 QUESTION D.02 (2.30)
- LIST five (5) conditions which will initiate a "ull Trip of the Reactor and STATE the Nuclear Instrument Channel that is associated with each Trip. (#1,#2, both, or none ) ;
(NOTE: INCLUDE SETPOINTS IN YOUR ANSWER) I' l l I (***** CATEGORY D COi.TINUED ON NEXT PAGE *****) , I I q
D. INGTRUMENTS AND CONyROLS~ PAGE 33 3
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1 QUESTION D.03 (l'.00) \ STATE the inter',ck that is assor.iated with starting the
- Primary Coolani emp .
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D. INSTRUMENTS AND CONTROLS PAGE 34 QUESTION D.04 (1.00)_ WH' /. u Jt not necessary to gamma-companaate the Safety Pown- ::annels? 4 (***** CAIEGORY D CONTINUED ON NEXT PAGE *****) 9 __c. e-_._____ _ _ _ - _ _ _ . _ _ _ _ __ _ _ _ _ _ - - _ _ _ _ - _ _ _ . . _ - _ _ _ _ -- _ _ - - - _ _ _ - -
i D .' INSTRUMENTS AND CONTROLS PAGE 35 t P
-QUESTION D.05 (2.25) '
- a. DESCRIDE HOW the resistivity of the Primary Coolant is measured.
NOTE: INCLUDE IN YOUR ANSWER THE LOCATION OF ANY COMPONENTS USED. ' 3
- b. EXPLAIN HOW flow id maintained through the Purification '
System when the Purification pump'in secured. 6 l l I l I I I l (***** CATEGORY D CONTINUED ON NEXT PAGE *****)
i D.
- INSTRUMENTS AND CONTROLS PAGE 36 l
QUESTION D.06 (2.00) Answer the following questions concerning Radiation Detectors using the curve below,
- a. LABEL EACH of the Regions (I-IV) on the curve .
- b. For each Detector (s) listed below, STATE the Region of the curve in which it operates.
- i. B-10 (wide range ch)
- 2. NI ch 2 Safety channel
- 3. Reactw Vent Ef fluent Monitor 4 Portal Monitor ( PCi1-4 A )
l l 108- /
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E -. 1 .-- n = m i - w--. 10 e . Y>
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J 10 ' - 108- j f 0 $00 1000 voltos. Number of lors Detened versus Voltage for a Gas Filled Chmber (**t:4 CATEGORY D CONTINUED ON NEXT PAGE ****V)
I p,. INSTRUMENTS AND CONTROLS PAGE 37 l L 1
-QUESTION D.07 '.2.25)-
- a. DRAW a one line diagran of the Neutron Flux Control System and LABEL the inputs,. outputs and components. (1.75)
- b. State the fastest period obtainable in Auto Flux Control. (0.S) t A
w 6 l l 1 i 1 (***** END OF CATEGORY D *****) f
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E. SAFETY AND EMERGENCY SYSTEMS , PAGE 38 2.00 QUESTION E.0i (9r50) ANSWER EACH of the following questions TRUE or FALSE.
- a. Nuclear Instrumentation and Control Blade Drive Instrumentation
.are an absolute necessity for shutting the UFTR down, recuAway
- b. All"Control Systems in the UFTR facility have Safety Related Functions (as considered in the FSAR).
- c. Depressing the Manual Scram Trip Button will cause the Primary Coolant Dump Valve to open,
- d. A Sonic Probe in the top of the Reactor Shield Tank will Trip the Reactor when the water level exceeds a preset value.
e '# - Ccre averhectc, the ,cgatrc- c oid-end-t c.m aer a h m = coefficients will causs_Ahc CO,u to snut down even without C c r. 5 ; ; Oladc incerticr. p g e9 i t (t**** CATEGORY E CONTINUED ON NEXT PAGE *****) 1
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[g , SAFETY AND EMERGENCY SYSTEMS, PAGE 39
- 4. ,
d 5 . QUESTION. E.02 (2.50) . LIST five (5) conditions / interlocks that will function , to prevent Control Blade withdrawal. I ( e l (***** CATEGORY E CONTINUED ON NEXT PAGE *****) 1 i 4 1
( E. SAFETY AND EMERGFflCY SYSTEMS PAGE 40 4 OUESTION E 03 (1.50) LIST ALL ot the conditions that should result in both MANUAL and AUTOMATIC actuation of the Evacuation Alarm.
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. r E. SAFETY AND EMERGENCY SYSTEMS PAGE 41 is GUEEl TION E.04 (3.00) i LItiT twelve (12) conditions which will initiate a Reactor Trip . without dump of primary water (Blade-Drop Trips).
NOTE: INCLUDE SETPOINTS WHERE APPLICABLE (***** CATEGORY E CONTINUED ON NEXT PAGE *****)
- , - - - . ,_v - . ~ . , y y .---v
E. SAFETY AND EMERGENC7'! SYSTEMS PAGE 42
- 1 QUESTION E.03 (2.75)
LIST the sequence of automatic protective actions that occur when two-(2) Area Radiation Monitors detect a H).GH LEVEL of Radiation during Reactor' operation. Next to.'each event
,- STATE WHY that protective action occurred.
9 l' l (***** CATEGORY E CONliNUED ON NEXT PAGE *****) i l
E, ifAFETY AND EMERGENCY SYSTEMS PAGE 43
.f.
4 QUESTION E.06 (1,30) EXPLAIN WHY the Reactor Protection System is Fail Safe and requires no aux 1111ary power to ensure shutdown. INCLUDE in your answer a com:leter description of how the Reactor
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Tripslon loss of Offaite Power. , f
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[E, SAFETY Ai4D EMERGENCY SYSTEMS PAGE 44 t QUESTION E.07 (1.00) 1 DESCRIBE the Power Supply to the Area Radiation Monitors.
, e a
(***** END OF CATEGORY E ***** )
F.- ~ STANDARD AND EMERGENCY OPERATING PROCIDURES PAGE 45
-GUESTION F.01 (3.00)
Match the evolution / function in Column A to the ONE responsible person (s) in Column B (Answers in Column B may be used more than once.) Column A Column B
- 1. designates personnnel for the A. Licensed Reactor Operator-performance of maintenance B. Reactor Manager
- 2. circuit breaker operi. tion C. Radiation Control Officer
- 3. indicates specific codes, standards, and regulations D. Reactor Safety Review to be used or referenced in Subcommittee the various phases of a modification f^d qui cd te 'ign enly co-tain_.-
4rvc! ! P'" 'u cnd 211 L c"r b.-I-L c i t e. .. c S. completion of a TRIP EVENT DATA ANALYSIS AND EVALUATION
- 6. grants written authorization
' of major maintenance items l
(***** CATEGORY F CONTINUED ON NEXT PAGE *****) 1 1 _ _ ,~ _ , . , . - . _ . . - , . ..
'I
F. STANDARD AND EMERGENCY' OPERATING PROCEDURES PAGE 46-QUESTION F.02 (1.00) ANSWER EACH of the following concerning reporting and recording events. (FILL IN THE BLANKS)
- a. The NRC Operations Center shall be notified by telephone within minutes after discovery of any accidental criticalty,
- b. The initial telephone notification (stated.above) shall be followed within a period of ,_ days by a written report.
I a f (***** CATEGORY F CONTINUED ON NEXT PAGE *****)
i F. STANDARD AND EMERGENCY OPERATING PROCEDURES PAGE 47 4 F QUESTION F.03 (1.50) ANSWER EACH of the following questions concerning UFTR fuel handling. (FILL IN THE BLANKS),
- a. If a fuel plate or element is dropped from a height of about i or more, fuel handling operations must be secured and the or his designated alterate must be notified.
- b. Shield tank water should be sampled and analyzed for and radioactive contamination before and after work with irradiated fuel.
(***** CATEGORY F CONTINUED ON NEXT PAGE *****) F F
,, .-c. - - - - . ~ ,- ,- ,
F. STANDARD AND EMERGENCY OPERATING PROCEDURES PAGE 48 , l l i I GUESTION F.04 (1.00) i Who's approval {1f any) is required prior to the performance of any maintenance to CORRECT a significant primary coolant Inak.
\
t I l l (***** CATEGORY F CONTINUED'ON NEXT PAGE *****) i l l
F. STANDARD AND' EMERGENCY' OPERATING PROCEDURES PASE. 49 GUEST 10N F.03 (1.00) The immediate actions in the event of a. Radiological Embrgencyper SOP-D.i are independently specified..for WORKING and NON-WORKING HOURS. In this regard, what is the definition of WORKING' HOURS 7 t n e (***** CATEGORY F CONTINUED ON NEXT PAGE *****)
=F. STANDARD AND EMERGENCY OPERATING PROCEDURES PAGE 39 QUESTION F.06 (2.00) STATE the three (3) actions (in order) that are required if the Reactor is operating at 100 KWth and stack counts indicate SIGNIFICANTLY above the maximum equilibrium level. l l I (***** CATEGORY F CONTINUED ON NEXT PAGE *****) I l
,, . = _ . . - -
F. STANDARD AND EMERGENCY OPERATING PROCEDURES PAGE S1 QUESTION F.07 (1.50) > LIST the three (3) actions that are required if radiation level indications of about 1.5 mr/hr are indicated by the Area , Radiation Monitors while at S KWth power. (***** CATEGORY F CONTINUE 0 ON NEXT PAGE *****)
, - - .ae , ,
F, STANDARD AND EMERGENCY OPERATING PROCEDURES PAGE 52 l QUESTION F.08 (2.00) , STATE thw standard class of UFTR Facility Emergency Situation (Class 0,I,or II) that would be applicable for EACH of the following events: ,
- a. Hurricane
- b. Personnel injury complicated by the injured person having low level radiological contamination.
- c. Small fire in the Control Room,
- d. Severe fuel damage during fuel handling.
l l I l 1 l l (***** END OF CATEGORY F *****) l I
Ge RADIATION CONTROL AND SAFETY .PAGE S3 QUESTION G.01 (1.00) If you are in an 80 mrad /hr neutron radiation field (neutron energy 20 Mov), what is the dose in MREM that you would receive after 45 minutes?
- a. 60 MREM
- b. 120 MREM
- c. 180 MREM
- d. 600 MREM t
1 (***** CATEGORY G CONTINUED ON NEXT PAGE *****)
; G. RADIATION CONTROL _AN0' SAFETY PAGE- S4 QUESTION G.02 ( .50)
ANSWER whether the following statement is TRUE or FALSE. Shortly after power operations, a few drops of primary coolant could contaminate a swipe to 450 cpm beta-gamma activity. Adjusting for detec tor ef ficiency, this indicates approximately ten times the permissible UFTR limit. i 6 4 (***** CATEGORY G CONTINUED ON NEXT PAGE *****)
G. RADIATION CONTROL AND SAFETY PAGE SS l j u i I QUESTION G.03 ( .50) ANSWER whether the following statement is TRUE or FALSE. Samples, NOT LEAVING the UFTR building complex, that were irradiated via the pneumatic rapid sample transfer (RADSIT) system are required to have processed a completed UFTR form SOP-D.40, Sample Record Index. (***** CATEGORY G CONTINUED ON NEXT PAGE *****)
~Ge RADIATION CONTROLAND' SAFETY PAGE 56 QUESTION G.04 (1.00)
STATE the unshielded sample radiation levels (two) beyond which the Radiation ~ Control Officer or his designated alternate must authorize transfer. I i (***** CATEGORY G CONTINUED ON NEXT PAGE *****) I I
x, G. RADIATION-CONTROL AND SAFETY', PAGE 57
. s
\-
QUESTION G.05 (2.50)
- a. LIST <she'two (2) conditions specified by UFTR Technical Specifications in which the reactor vent system is required to be operated.
- b. LIST the three.(3) failure (s) or indication (s) that UFTR Technical
-Specification 3.4.3 requires for the reactor vent system to be immediately secured. s
=
l l 1 (***** CATEGORY G CONTINUED ON NEXT PAGE *****)
G. RADIATION CONTROL AND SAFETY PAGE 58 QUESTION G.06 -(2.00)
- a. STATE the maximum permissible concentration (MPC) of the gaseous effluent discharge of Argon-41 as specified in UFTR SOP-E.6 and UFTR Technical Specifications.
- b. STATE whether the associated sample of the core ventilation flow is taken PRIOR TO or AFTER dilution by the diluting fan.
- c. What factor is used to account for atmospheric dilution of Argon-41 in the determination of stack effluent concentrations as per UFTR Technical Specifications?
- d. STATE the minimum time required after a reactor startup to allow for the Argon-41 emission level indicated by the stack monitor to stabill:e.
e i l l i (***** CATEGORY G CONTINUED ON NEXT PAGE *****) i i l I
G. RADIATION CONTROL AND SAFETY PAGE S9 e. QUESTION O.07 (2.00? LIST the four (4) actions which .i.ust be'taken in the event that radiation levels following shielding alterations are found to be significantly in excess of anticipated radiation levels. i 1 (***** CATEGORY G CONTINUED ON NEXT PAGE **A**)
G. RADIATION CONTROL AND GAFETY PAGE .60 QUESTION G.00 (1.00) STATE the criterion (dpm/cm^2 above background) used to permit t h.e return to normal use of a potentially contaminated area that had been isolatsd. i t (***** CATEGORY G CONTINUED ON F PAGE *****)
G. RADIATION CONTROL AND SAFETY PAGE 61 QUESTION G.09 (1.00) A point source of gamma radiation given an exposure rate of 90 mR/hr at ONE meter. CALCULATE the exposure rate at THREE meters. (***** CA'EGORY G CONTINUED ON NEXT PAGE *****)
G. RADIATION CONTROL AND SAFETY . PAGE 62 e \ QUESTION G.10 (1.00)
- a. STATE the maximum reactor power level at which the opening of the ;
vertical ports for sample irradiation shall be considered a routine operation.
- b. Would such a routine operation require an RWP?
i l l I (***** CATEGORY G CONTINUED ON NEXT PAGE *****) l 1 l
I G. RADIATION CONTROL AND GAFETY PAGE 63 e
-QUESTION G.11 (1,50)
~
STATE the normal working dose rates (in MREM /wk for whole body, 1 extremities, and skin) which require preparation of a radiation work ! permit (RWP) dnd compliance with the provisions of UFTR SOP-D.2 prior to commencement af work or operations which have the potential (of -
, exceeding those. rates. ]
f I r i i (***** CATEGORY G CONTINUED ON NEXT PAGE *****) i
Q. G. RADI ATION CONTROLJ@ _ SAFETY PAGE' 64
< .. o ?
1 OUESTION ,G.12 (1.25) STATE the specific definitions of a "RADIATION AREA" and of a "HIGH RADIATION AREA." 4 l l l i (***** END OF CA/EGORY G *****) (************* END OF EXAMINATION ***************) J
3 h1 ASTER
~A . ' Pf< I NC I PL E S OF REACTOR OPERATION PAGE 63
(&O ANSWERS -- UNIVERSITY OF FLORIDA -88/06/08-ARILDSEN, J. ANSWER A.01 (1.00) d REFERENCE Westinghouse Design Technical Manual, Chapter 2 ANSWER A.02 (1.50)
- a. The fraction of thermal neutrons that escape leakage while thermal.
(0,5)
- b. If a reactor had a reflector, fast neutrons which escaped from the core can be thermalized and then reflected back into the core (0,5). The net result can be that more thermal neutrons enter the core than leak from it. (0.S)
REFERENCE General Electric, Reactor Theory, App. G ANSWER A.03 (1.00) P = Potexp (t/T) (0.4) T = t/In(P/Po) (0.4) l T = 240/In(2000/100) = 80 sec (0.2) l REFERENCE
)
General Electric, Reactor Theory, Chap. 3
A. ' PRINCf PLES OF REACTOR OPERATION PAGE 66 ANSWERS -- UNIVERSITY OF FLORIDA -88/06/08-ARILDSEN, J. ANSWER A.04 (2.00) Neg. reactivity added by all rods dropping (from IRW curve) a
~0.313e (SD 1) - 0.0132 (SD 2) - 0.0222 (SD 3) -0.0056 (RB) y . M c .p) /(x 4 g 4 u h d
" ~ - "" ( '*)
+
CUR -- 76.06 (lambda p detet) / (b ef4 - pk (0.8) y= (,otva- t .c5%M / C .cas e.. ossO
- o)
OUR 26. 06-*-te-eist t-eve 54Gh+-. c)-H ere065- -E-0. 054B3 )- (0.2) er a - 9 o s._ c (2 W d OUR - 0.29-BPM '; O . 02-4W41)_. (0.2) NOTE: APPLICABLE GRAPHS ARE ATTACHED I+6i n r.c t a ta r,. taught e t--t heteH i ty , the questio n i+1-t m yrn-fed ca-%e-iMivi-dtm4Mnowl edge vi the u vutup . , 11-SUR undet<xxh-- g r nr4 4 nn will % por-the.: unuwer-key. REFERENCE Wentinghouse Design Technology Manual, Chap. 2 UFTR: FSAR ANSWER A,05 (2.00)
- a. K-effective (0.5 each)
- b. Gamma Decay
- c. Period (Formi Age)
- d. Photoelectric Effect REFERENCE DPC, Fundamentals of Nuclear Reactor Engineering, p.56,89 :
General Electric, Reactor Theory, Chapters 1, 3 l l ANSWER A.06 (1.00) ) i (b) l l REl'ERENCE 1 NUS, Vol 2, pp 7.3-2 l l l i l I 1 I 1 l
*- 1 0
' l '
A. PRINCIPLES OF RFACTOR OPERATION PAGE- 67 '
. i ANSWERS ---UNIVERSITY OF FLORIDA -80/06/08-ARILDSEN, . J.
4 t i l I l ANSWER A.07 (1.00)
, (b) ,
REFERENCE i DPC, Fundamentals'of Nuclear Reactor Engineering, p. IS8 s : ANSWER A.08 (1.00) [ (d) i- , REFERENCE DPC, Fundamentals of Nuclear Reactor Engineering, pp.161-162 1
\
ANSWER A.09 (1.00) b i REFERENCE CR Training Ltr TRA 85-0013 DPC, Fundamentals of Nuclear Reactor Engineering, p.' 38, 39, 146' ANSWER A.10 (1.00) 4 C l REFERENCE General Electric, Reactor Theory, Chap. 5 4 1 l i ! I J
.c - .
y A.' PRINCIPLES OF REACTOR OPERATION . PAGE 68 h' r , ANSWERS -- UNIVERS TY OF FLORIDA -88/06/08-ARILDSEN, J. -
)
ANSWER A.11 (2.50)
> t
- a. Steady state neutron level higher than source alone due to the multiplication of fissionabin fuel.
- b. Material at core edges which reduces neutron leakage by scattering ,
neutrons back into the core. 4
- c. Removal of Xe-135 from the core by absorption of a neutron to Xe-136.
- d. Heat produced by the decay of radioactive nuclides. I i
- e. Reactivity change per unit of rod motion.
REFERENCE
- l t
' General Electric, Reactor Theory, App. G [
i , 4 I h 9 I 1
~
r l
?
i p I i b l I 6 l
D ' FEATURES OF FACILITY DESIGtf PAGE 69 ANSHERS -- UNIVERSITY OF FLORIDA -86/06/08-ARILDSEN, J. , ANSWER B.01 (2.00)
- a. TRUE
- b. FALSE
- c. FALSE
- d. TRUE REFERENCE UFTR FSAR CH S ANSWEP B.02 (2.50)
- a. .06% ^k/k
- b. 100 KWth
- c. 2.3% ^k/k
- d. 93% , uranium aluminum or u ra diu m 23f (0.5 each blank)
REFERENCE UFTR: FSAR CH 4.1 , TECH EF'EC 3.0 ANSWER B.03 (1.00) Fuel Bundle Aluminum Wedging Pins center of the fuel boxes) W t, ('J.'; s . o oinserted
)(a r'e into the REFERENCE UFTR: SOP C2,7.4.1.2 ANSWER B.04 (1.00) i Foils are installed in the slots for irradiation (0.5) and are used for flux mapping (0.5).
REFERENCE UFTR: FSAR CH 4.1.4 i i
4 D.' FEATURES OF FACILITY DES?GN, PAGE 70 ANSWERS -- UNIVERSITY OF FLORIDA -88/06/00-ARILDSEN, J. l ANSWER B.05 (2.00)
- a. Allows an air return, path to the top of the fuel boxes (0.5) to allow rapid dumping of the water ' rom the' boxes (0.5).
- b. Located at the base of the stacks before dilution occurs (0.5).
i l c. Prevents .the discharge of undilu ced air effluent (0.5). l REFERENCE l UFTR CH 9.4.2 l l l ANSWER B.06 (1.00) Functions as both a Moderator (.5) and a Reflector (.5). REFERENCE UFTR: Emergency Plan Ch. 1.3 ANSWER B.07 (2.00) 1
,a. Prevents diffusion of radioactive gases or- particulate matter into the Reactor Room during Reactor operation. (1.0)
- 6. Ar-41 N-16 (0.5 each)
REFERENCE UFTR: FSAR CH. 9 l ANSWER B.08 (1.50) Tap water is passed through 2 demineralizers in series (0.5) that are filled with nuclear grade resin (amberlite) (0,5). As the water passes through, it undergoes mechanical filtration (.25) and ionic impurities are exchanged with H+ and OH- Resin ions (through the process of adsorption) (.25).
D.' FEATURES OF FAC LITY DESIGN PAGE 71 ANSWERS -- UNIVERSITY OF FLORIDA -88/06/0!;-ARILDSEN, J. ANSWER B.09 (2.00)
- a. The Diffuser eliminates the formation of vortices inside the storage tank (as a result of the pump's suction) (0.S), by forcing the water to diffuse through the input line to the Primary Coolant Pump (0.5).
- b. The Baffle eliminates air being trapped in the coolant (0,5),
by suppressing the splas'11mg of water comming into the CST (0.25) and changing itu <lirection of flow (0.25). REFERENCE UFTR: FSAR CH S.1.1 i
r: , C.' GENERAL OPERATING CHARACTERISTICS PAGE 72 AN?WERS -- UNIVERSITY OF FLORIDA -G0/06/00-ARILDSEN, J. ANSWER C.01 (2.00) Subscript i refers to values when all rods are inserted. Subscript 2 refers to values when Rod A is withdrawn. Keffi = 1/(1-pl)
= 1/(1+0.1230) 4
= 0.09 (0.3)
CR1/CR2 = (1-Keff2)/(1-Keffi) => Keff2 = 1-[CR1/CR2 * (1-Keff1)]
= 1-C2/3 * (1-0.89)]
= 0.927 (0.6) p2 = (Keff2-1)/Kef12
= (0.927-1)/0.927 9
= -0.0790 (0.%)
Required reactivity addition needed a p2 - p1 = +0.0440 (0.54[4s 1.) m,u,_ % ea-From IRW curve, SB 1 must be 10?". .' 0%) withdmwn- M o OM h btNdswn- u c, (0.K) \ SD 2 must be M %,' SD 3 must be 54% ( 2%) ;Fthdrawn- Sco (0 9 ) ) Rh -t u " ' ( 0. 3Q ) )
%o (.i to ) (p, ))
REFERENCE General Electric, Reactor Theory, Chap. 3 UFTR FSAR ANSWER C t2 (1.00) (d) REFERENCE DPC, Fundamentals cf Nuclear Reactor Engineering, p. 106 VEGP, Training Text, Vol. 9, p. 21-47 Westinghouse Reactor Physics, pp. 1-3.17 & 19
y. l C.
- GENERAL OPERATING CHARACTERISTICS' PAGE 73 ANSWERS -- UNIVERSITY.OF FLORIDA -88/06/08-ARILDSEN, J. ;
e ANSWER C.03 (1.00) r (c) i REFERENCE DPC, Fundamentals of Nuclear Reactor Engineering, p.163 General Electric, Reactor Theory, Chapter 6 E!H GPNT,Vol VII, Chapter 10.1-83-06 , DSEP: L/P 02-2/3-A, pp 172 - 1763 02-OG-A, pp S7 - 60 ANSWER C.04; (1.00) , d (1.0) REFERENCE UFTR: FSAR CH 4.6 ANSWER C.05 (1.00) d (1.0) REFERENCE
- UFTR SDP ' T.3 , 4.6.1 6
ANSWER C.06 (2.50)
- a. 40 (+or-1) gpm l
- b. 06 (+or-2) dag F or ' SIN d'5 F
- c. 103 (+or-2) deg F 12 0U ' b) d **cI
- d. -0.3 X 10 exp -4 delta k/k per de'g F ,
e, approx 40 deg F (0.5 each! l REFERENCE j UFTR FSAR CH 4.1.2 ! i, w e l f I l
O. ' GENERAL OPERATING CHARACTERISTICS PRGE 74 ANSWERS -- UNIVERSITY OF FLORIDA -GO/06/08-ARILDSEN, J. ANSWER C.07 (1.25) DISAGREE (0.5) More excess reactivity must be added to get to power (.25)- a higher loaded core is more hazardous (.25). Also, cold water accidents are more severe (.25). REFERENCE UFTR: SRO TEST S/30/84 ANSWER C.08 (2,00)
- a. 23535 KWHR / month crs 13 5 F PH / m. 4 h (0.5)
- b. The principal routine emmission from the UFTR facility is AR-41 (0.5). The concentration of AR-41 from the stack after dilution is approximately 3.1 X MPC as recommended by the Florida Division of Health (0.5). Reac tor operations are limited to limit the Argon-41 discharges to MPC when averaged over a month (0.5).
REFERENCE UFTR FSAR CH 11 ANSWER C.09 (2.00)
! G I F 1 G I F 1 G I 1 R ! U ! R I U i R I I A I E I A 1 E I A I l P l L I P I L 1 P 1 i H I I H I I H I l
1 MM J ! 1 E . I
~
l l 1 . ! I . I WITH I 1 1 q jg-REFLECTOR WITHOUT (1.0 each curve) REFLECTOR
- ,. - . _ . _ . _ . - -m__ ,,
C.' GENERAL OPER4 TING CHARACTERISTICS PAGE 75 ANSWERS -- UNIVERSITY OF FLORIDA -00/06/00-ARILDGEN, J. REFERENCE UFTR SRO TEST 5/30/84 l l l l
a 0.' INSTRUMENTS AND CONTROLS PAGE 76 ANSWERS -- UNIVERSITY OF FLORIDA -88/06/08;ARILDSEN, J. ANSWER D.01 (2.00)
- a. FALSE
- b. TRUE
- c. TRUE
- d. FALSE REFERENCE UFTR: FSAR CH 7 ANSWER D.02 (2.50)
- 1) fast period <= 3 sec (.25) ch #1 ( 25)
- 2) high power >= 125 % (.25) both (.25)
- 3) reduction of HV to neutron chambers of >= 10 % (.25) both (.25)
- 4) turning off the console magnet power switch (.25) none (.25)
- 5) AC power failure (.25) none (.25)
REFERENCE UFTR FSAR CH 7 ANSWER D.03 (1.00) The Purification Pump shuts cif when the Primary Coolant Pump is running. (1.0) -oR-d a<A h t uden W Av.m g %\,ve. Thh .ch 7 - dw .
-f( Cbo) m b .e t, h g w M REFERENCE UFTR: FSAR 9.2.4 ANSWER D.04 (1.00)
This channel operates at power levels at which the gamma radiation is negligible compared to the neutron level. Therefore, it is not necessary to use a gamma comprensated detector. (1.0) J REFERENCE j UFTR FSAR CH 9 i
D. INSTRUMENTS AND CONTROLG PAGE 77-ANSWERS'-- UNIVERSITY OF FLORIDA -G0/06/09-ARILDSEN, J. l
- r ANSWER D.05 (2.25) f i a..An in line (wall mounted) resistivity bridge (0.5) receives (so
+ signals f rom + conductivity cells (0.5) located upstream -e4 omi clue / ream o8 !
- the demineralizer in the_ Purification System (.25). !
i 'a . i: j b. The Primary Coolant Pump gerneates suf ficient driving head, to j Maintain a flow through the Purification Loop when it is in ; operation (1.0). REFERENCE UFTR FSAR S,i.4 , 9.2.4 f: i - ANSWER D.06 (2.00) I
- a. !
I RECOMBINATION
- II IONIZATION CHAMBER
- III PROPORTIONAL i IV G-M i i b. 1. PROPORTIONAL , 2. ION CHAMBER
- 3. G-M
- 4. G-M REFERENCE l a NUCLEAR POWER SYSTEMS CH 7 ,
t I i ' 4 i ANSWER D.07 (2.25) i ! ) a. (
- i
~
NTCHANN(4 c eg y, N '
; . pg s% g,g Lemste t ' ' '
conw L. A A l (l.75) b
- b. 30 sec (0.7) Y* DEMAND PERIOD C 5?
i l REFERENCE UFTR FSAR CH 9 ! , i i 1 l 2 l f. l
E.' GAFETY AND EMERGENCY SYSTEMS PAGE 78 ANSWERS -- UNIVERSITY OF FLORIDA -88/06/08-ARILDSEN, J. ANSWER E.01 (2.50)
- a. FALSE
- b. TRUE
- c. FALSE
- d. FALSE
- e. TRUE REFERENCE UFTR: FSAR CH 7, CH 15 ANSWER E.02 (2.50)
- 1. cource counts < 2 cps
- 2. reactor perjad $6 10 seconds
- 3. attempt to raise any two or more Blades simultaneously.
- 4. Safety Channels 1 and 2 and Wide Range Drawer Calibrate (or Safety 1 Trip Test) switches not in OPERr.TE.
- 5. Power is raised in AUTO control at a period faster than 30 sec.
(0.5 each) REFERENCE UFTR: FSAR CH 7 ANSWER E.03 (1.50)
- 1) 2 Area Radiation Monitors Alarm in coincidence (at>=25mr/hr)-(.25)(0f) m.t___1 . ,
me1 ,
- 2) h r h$rtAculatb Monitor with valid alarm condition 4we6t(0.71 Manual (.25)
- 3) Reactor operator detects a potentially hazardous radiological condition (and preventive actions are required to protect personnel). W (0 O {
Manual (.25) l REFERENCE UFTR TECH SPEC 3.6.1 i l l 1 Y
1 I E. ' SAFE TY AND EMERGENCY SYSTEMS PAGE 79 I l ANSWERS -- UNIVERSITY OF FLORIDA -88/06/08-ARILDSEN, J. ANSWER E.04 (3.00)
- 1) Loss of power to the Reactor Vent Blower System. (.25)
- 2) Primary Cooling Pump (.25)
- 3) Vent Diluting System (.25)
- 4) " "
Secondary System Well Pump (.15) when above 1 KW and using this system for cooling. (0.1) S) Less than 60 gpm Secondary System Flow when using Well Water for cooling (.15) and above i KW power (0.1).
- 6) Less than 8 gpm Secondary System Flow when using city water for cooling (.15) and above 1 KW power (0.1).
- 7) Drop in Water Level of the Shield Tank ( about 4 in.). (.25)
O) Reduction of Primary Coolant Flow <= 30 gpm (.25)
- 9) Loss of Primary coolant Flow (return line < 10gpm) (.25)
- 10) Reduction of Primary Coolant Level (.25)
- 11) High Temp Primary Coolant return 1SS deg F (.25)
- 12) Manual Reactor Trip Button depressed. (.25)
REFERENCE UFTR: FSAR CH 7.3.2 ANSWER E.05 (2.75) Evacuation Alarm Actuates (0.S) due to 2 RAD Monitors (.25) alarming Reactor Cell AC trips (0,5) due to actuation of the (.25) Reactor Vent Sys trips (0.5) Evacuation Alarm (diluting fan, vent fan and damper close) Reactor Trips (0.5) due to loss of power to (.25) (blade trip) Diluting Fan, Vent Fan REFERENCE UFTR:-FSAR CH 7.6 , 9.4.2 ANSWER E.06 (1."3) The lens of Offsite Power drops out the Scram Relays (.25) and deenergizes the Magnetic Clutches (.2S) to Trip the Reactor by dropping the Control Rods under gravity completely into the core (.5). It is Fail Safe since a loss of power will result in a Reactor Trip (.5). 6
- . , , , - - - , - ,, , . - - , ,~ ,- ,-
. , - + . - ,- , ,---,n. ,- n- - - . .-c., - , , . ., -=,-,..,m. , , . , ,
g,* SAFETY AND EMERGENCY SYSTEMS PAGE 80 ANSWERS -- UNIVERSITY OF FLORIDA -88/06/08-ARILDSEN, J. REFERENCE UFTR: FSAR CH 8.2 ANSWER E.07 (1.00) 24VDC power supply (0.5) backed up with a floating battery pack (0.5). REFERENCE UFTR: FSAR CH 8.4 i
\
l 1 i l l i
F.* STANDARD AND EMERGENCY OPERATING PROCEDURES PAGE 91 ANSWERS -- UNIVERSITY OF FLORIDA -G8/06/08-ARILDSEN, J. ANSWER F.01 (!.00) (2,fo)
- 1. B
- 2. A
- 3. B
- 4. C 06'c MO S. A
- 6. B (0.5 each)
REFERENCE UFTR: SOP-0.2, 7.2.2 and 7.2.2.3 SOP-0.2, APPENDIX I Form O.2A SOP-0.3, 3.3.4.1 SOP-0.6, 7.1.2.11 ANSWER F.02 (1.00)
- a. 60
- b. 30 (0.5 each)
REFERENCE UFTR SDP F.8 , 7.1 AND 7.3.1 ANSWER F.03 (1.50)
- a. i ft.
Reactor Manager
- b. conductivity (0.5 each) i REFERENCE !
UFTR SOP-C.4, 4.10 and 4.13 j l 4 i D
F. ' STANDARD AND EMERGENCY OPERATING PROCEDURES PAGE 82 ANSWERS -- UNIVERSITY OF FLORIDA -08/06/08-ARILDSEN, J. ANSWER F.04 (l'.00) The Reactor Manager or his authorized representative (1.0) REFERENCE UFTR: SOP-D.3, 4.3.1 ANSWER F.45 (1.00) Any time that e.,thorized personnel are in the Reactor Cell. (1.0) REFERENCE UFTR: SOP-B.1, 7.1.1 ANSWER F.06 (2.00)
- 1) Shutdown the Reactor
- 2) Notify the SRO on call
- 3) Determine the cause O'd d *#""5 l
S C''M h'".
(0 "5 eac h and 0. 5 f or 4 being listed Mt) C,-4 ) REFERENCE UTTR: SOP - A.3 , 4.6.3 ANSWER F.07 (1.30)
- 1) Determine the cause
- 2) implement appropriate corrective ac tion.
- 3) Notify the SRO on call.
(0.S each) REFERENCE UFTR SDP - A 3 , 4.S.2 I I I i l I 1
F.* STANDARD AND EMERGENCY OPERATING PROCEDURES PAGE 83 l ANSWERS -- UNIVERSITY OF FLORIDA -88/06/08-ARILDSEN, J. ANSWER F.08 (2.00)
- a. Class I
- b. Class O
- c. Class I
- d. C l ass XI -
CL"^ (0.5 each) REFERENCE UFTR: EMERGENCY PLAN 4.1,4.2,4.3 1-
G.* RADIATION CONTROL AND SAFETY PAGE 04 ANSWERS -- UNIVERSITY OF FLORIDA -88/06/08-ARILDSEN, J. ANSWER G.01 (1.00)
-b- d GF=10 (80)(45/60)(10)=600 (1.0)
REFERENCE
.10 CFR 20.4 ANSWER G.02 ( .50)
TRUE (0.5) REFERENCE UFTR: SOP-D.3, 4.3 ANSWER G.0J ( .50) FAL3E (0,5) REFERENCE UFTR SOP-D.4, 7.7 ANSWER G.04 (1.00)
'.O 1.5 R/hr at one foot Daf5) or (200 mR/hr at the surface of the transfercontainer) LD<&T' REFERENCE UFTR: SOF-D.4, 7.3 i l
U.* RADIATf0N CONTROL AND SAFETY PAGE 85 ANSWERS -- UNIVERSITY OF FLORIDA -88/06/08-ARILDSEN, J. ANSWER ,0.05 (2.50)
- a. 1. During reactor operations
- 2. Stack monitor indicates greater than 10 cps
- b. 1. Failure in the monitoring system .
- 2. Failure of the absolute filter
- 3. Unanticipated high stack count rate (0.5 each)
REFERENCE UFTR: Tech. Spec. 3.4.3 4NSWER G.06 (2.00)
- a. 4.0 E-8 microC/ml
- b. PRIOR TO
- c. 200
- d. 4 hours (0.S each)
REFERENCE UFTR: SOP-E.6 UFTR: Tech. Spec. 3.4.2 l l ANSWER G.07 (2.00) I l
- i. Shutdown the reactor immediately 1
- 2. Promptly replace the shielding
- 3. Notify the Reactor Manager or his designated representative 1
- 4. Evaluate the situation and determine tbn cause of the higher. l radiation levels (0.S each)
REFERENCE UFTR: SOP-E.2, 7.1.3
U.* RADIATION CONTROL AND SAFETY PAGE 86 ANSWERS -- UNIVERSITY OF FLORIDA -88/06/08-ARILDSEN,.J. ANSWER G.08 (1.00) 20 dpm/cm^2 (1.0) REFERENCE Emergency Plan for the UFTR, 7.1.2.3 ANSWER G.09 (1.00) 10 mR/hr (1.0) REFERENCE UFTR: FSAR 12.10 ANSWER G.10 (1.00)
- a. 1 KW
- b. No (0.5 each)
REFERENCE UFTR: SOP-E.2, 7.2 ANSWER G.11 (1.50) 75 MREM /wk whole body 500 MREM /wk extremities 400 MREM /wk skin (0.5 each) REFERENCE I UFTR: SOP-D.1, 4.4
O.* RADIATION CONTROL AND SAFETY PAGE 87 ANSWERS -- UNIVERSITY OF FLORIDA -88/06/08-ARILDSEN, J. ANSWER G.12 (1.25)
"RADIATION AREA" - Any area accessible to personnel (0.25) in which there exists radiation at such levels that a major portion of the body could receive in any one hour a dose in excess of 5 mhEM (0.25) or in any 5 consecutive days a dose in excess of 100 MREM (0.25).
"HIGH RADIATION AREA" - Any area aceusible to personnel (0.25) in which there exists radiation at such levels that a mejor portion of the body could receive in any one hour a dose in excess of 100 MREM (0.25).
REFERENCE UFTR: SOP-D.1, 3.2.3 and 3.2.4
+
P l l l l
TEST CROSS REFERENCE PAGE 1 QUESTION VALUE REFERENCE A.01 1.00 GTH0000846 A.02 1.50 GTH0000848 A.03 1.00 GTH0000849 A.04 2.00 GTH0000850 A.05 2.00 GTH0000853 A.06 1.00 GTH0000854 A.07 1.00 GTH0000857 A.08 1.00 GTH0000858 A.09 1.00 GTH0000860 A.10 1.00 GTH0000862 A.11 2.50 GTH0000863 15.00 B.01 2.00 GTH0000790 D.02 2.50 GTH0000794 B.03 1.00 GTH0000'96 B 04 1.00 GTH0000708 D.05 2.00 GTH0000789 B.06 1.00 GTH0000792 B.07 2.00 GTH0000793 B.08 1.50 GTH0000787 B.09 2.00 GTH0000791 15.00 C.01 2.00 GTH0000851 C.02 1.00 GTH0000852 C.03 1.00 GTH0000855 C.04 1.00 GTH0000796 C.05 1.00 GTH0000880 C.06 2.50 GTH000079G C.07 1.25 GTH0000795 C.08 2.00 GTH0000799 C.09 2.00 GTH0000797 13.75 D.01 2.00 GTH000t'804 D.02 2.50 GTH0000802 D.03 1.00 GTH0000805 D.04 1.00 GTH0000800 D.05 2.25 GTH0000806 D.06 2.00 GTH0000803 D.07 2.25 GTH0000801 13.00 E.01 2.50 GTH0000808 E.02 2.50 GTH0000807
TEST' CROSS REFERENCE PAGE 2 QUESTION VALUE REFERENCE E.03 1.50 GTH0000810 C.04 3.00 GTH0000811 E.05 2.75 GTH0000813 E.06 1.50 GTH0000809 E.07 1.00 GTH0000812 14.7S F.01 3.00 GTH0000870 F002 1.00 GTH0000878 F.03 1.50 GTH0000881 F.04 1.00 GTH0000820 F.05 1.00 GTH0000830 F.06 2.00 GTH0000873 F.07 1.50 GTH0000874 F.08 2.00 GTH0000882 13.00 G.01 1.00 GTH0000814 G.02 .50 GTH000081/- G.03 .50 GTH0000824 G.04 1.00 GTH0000817 G.05 2.50 GTH0000818 G.06 2.00 GTH0000819 G.07 2.00 GTH0000821 G.08 1.00 GTH0000822 G.09 1.00 GTH0000823 G.10 1.00 GTH0000827 G.11 1.50 GTH0000828 G,12 1.25 GTH0000829 15.25 79.75 DOCKET NO 83 i l l
- ' y qv angrco t-
- Ro- ,
-)
1,
\
s SRO / R0 . c UNIVERSITY OF FLORIDA TEST REACTOR'
, LICENSE EXAMINATION 88/06/08 1
HANDOUTS EQUATION SHEET ------ 1 PAGE STEAM TAl(LES -------- 7 PAGES FIGURE #219 FIGURE 4-26 FIGURE 4-27 FIGURE 4-28 FIGURE 4-29 e
\
l +
#e
- l
. k;,
- - - _ . . , , - .- - - . . - _- . . . . - , . . . - - - - _ - - , - - , - , . _ - - - - , . . . . ....-.-.U
.., l. f o ca , v o S/t Cycle efficiency o (Net work out)/(Energy la) 2
, , mg s = V,t + 1/2 at E = me- -
KE = 1/2 mv 2
,, , (yf ,.j,)ft 4 , 33 4 , 3,,-it PE = mgn vf = V, + at * = e/t x = In2/t1/2 = 0.693/t1/2 y,y , p nD 2 1/2' 'b" A= 4 [(t1/2) + (te ))
AE = 931 am
. m = V,yAo - r.x I"l'o Q " hh I Q = mCpat Q = UA6 T I=Iec pwr = w ah f I = 1,10-*/ M TYL = 1.3/u sur(t) HVL = -0.693/u P = P,10 t
P = Po e /T SUR = 26.06/T SCR = S/(1 - K,ff) l CR x = S/(1 - K,ffx) j SUR = 26e/t* + (a - o)T CR;(1 - K,ff;) = CR2 (I
- keff2) i T = (t*/o) + [(8 - o VIo] M = 1/(1 - K,ff) = CR j/CR, l T = t/(o s) M = (1 - K,ff,)/(1 - K,ff)) ;
T = (s - o)/(Io) SDM = ( -K,ff)/K,ff l o = (K,ff-1)/K ,ff = AK,ff/K,ff t' = 10 seconos i I = 0.1 seconds o = ((t*/(T K,ff)] + [s,ff /(1 + IT)] I jd) = I d P = (t4V)/(3 x 1010) Ij d) 2 =2 1d22 2 I = oN R/hr = (0.5 CE)/d2 (,,g,73) R/hr = 5 CE/d2 (f,,g) . Water Parameters Miscellaneous Conversions 1 gal. = 8.345 lem. 1 curie = 3.1 x 1010 ap3 , 1ga[,=3.78 liters 1 kg = 2.21 lem l 1 fte = 7.48 gal. 1np=2.54x10]Stu/nr l Density = 62.4 lbqi/ft3 1 nw = 3.41 x 100 5tu/br l Density = 1 gm/enP lin = 2.54 cm Heat of vaporization = 970 Btu /lem 'F = 9/5'C + 32 Heat of fusion = 14> Stu/lbm ,
'C = 5/9 ('F-32) 1 Atm = 14.7 psi = W .9 in. Hg. 1 BTU = 778 ft-lbf 1 f t. H2 O = 0.4335 icf/in.
e = 2.718 w
'~
v_ _
( . EMhelpy. Stv/lb (Mropy. 91s/lb u F Yolume. ft'/lb mP Water tvep Steam Water Evep Steem Water 6vep Steam [, hp Ag A, s, sg s,
's We 's 1075.5 0.0000 2.1873 2.1873 32 0.01602 3305 3305 -0.02 1075.5 32 0.06859 1076.8 0.0061 2.1706 2.1767 35 2948 2948 3.00 1073.8 35 0.09991 0.01602 1079.0 0.0162 2.1432 2.1594 40 2446 2446 8.03 1071.0 40 0.12163 0 01602 1081.2 0 0262 2.1164 2.1426 45 2037.8 13.04 1068.1 45 0.1474? C.01602 2037.7 0.0361 2.0901 2.1262 50 1704.8 18.05 1065.3 1083.4 50 0.1779* 0.01602 1704.8 0.0555 2.0391 2.0946 60 1207.6 28.06 1059.7 1087.7 50 0.2561 0.01603 1207.6 1054.0 1092.1 0.0745 1.9900 2.0645 70 0.01605 868.3 868.4 38.05 80 70 0.3629 48.04 1048.4 1096.4 0.0932 1.9426 2.0359 0.5068 0.01607 6333 633.3 2.0086 90 SO 58.02 1042.7 1100.8 0.1115 1.8970 0.01610 468.1 468.1 100 90 0.6981 1037.1 1105.1 0.1295 1.8530 1.9825 350.4 350.4 68.00 100 0.9492 0.01613 1109.3 0.1472 1.8105 1.9577 110 265.4 77.98 1031.4 110 1.2750 0.01617 265.4 1113.6 0.1646 1.7693 1.9339 120 0.01620 203.25 203.26 8737 1025.6 120 1.6927 1019.8 1117.8 0.1817 1.7295 1.9112 130 0.01625 157.32 157.33 97.96 130 2.2230 1014.0 1122.0 0.1985 1.6910 1.8895 140 0.01629 122.98 123.00 107.95 140 2.8892 1008.2 1126.1 0.2150 1.6536 1.8686 150 0.01634 97.05 97.07 117.95 150 3.718 1002.2 1130.2 0.2313 1.6174 1.8487 160 0.01640 77.27 77.29 127.96 160 4.741 996.2 1134.2 0.2473 1.5822 1.8295 170 0.01645 62.04 62.06 137.97 170 5.993 990.2 1138.2 0.2631 1.5480 1.8111 180 0.01651 50.21 50.22 148.00 180 7.511 984.1 1142.1 0.2787 1.514S 1.7934 100 0.01657 40.94 40.96 1*5.04 190 9.340 977.9 1146.0 0.2940 1.4824 1.77 04 200 0.01664 33.62 33.64 168.09 200 11.526 971.6 1149.7 0.3091 1.4509 1.7600 210 0.01671 27.80 27.82 178.15 210 14.123 970.3 1150.5 D.3121 1.4447 1.7568 212 0.01672 26.78 26.80 180.17 212 14.696 965.2 1153 4 0.3241 1.4201 1.7442 220 0.01678 23.13 23.15 188.23 220 17.186 958.7 1157.1 0.3388 1.3902 1.7290 230 20.779 0.01685 19364 19381 19833 240 130 952.1 1160.6 0.3533 13609 1.7152 0.01693 16.304 16.321 208.45 240 24.968 945.4 1164.0 0.3677 1.3323 1.7000 250 0,01701 13.802 13.819 218.59 250 29.825 938.6 1167.4 0.3819 13043 1.6862 260 35.427 0.01709 11.745 11.762 228.76 240 931.7 1170.6 03960 1.2769 1.6729 270 41.856 0.01718 10.042 10.060 238.95 270 924.6 1173.8 0.4098 1.2501 1.6599 280 49.200 0.01726 8.627 8.644 249.17 290 917.4 1176.8 0.4236 1.2238 1.6473 290 57.550 0.01736 7.443 7A60 259.4 290 910.0 1179.7 0.4372 1.1979 1.6351 300 67.005 0.01745 6.448 6.4 M 269.7 300 902.5 1182.5 0.4506 1.1726 1.6232 310 0.01755 5.609 5.626 280.0 810 77.67 894.8 1185.2 0.4640 1.1477 1.6116 320 89.64 0.01766 4.896 4.914 290.4 320 311.3 878.8 1190.1 0.4902 1.0990 1.5892 340 117.99 0.01787 3.770 3.788 360 840 332.3 862.1 1194.4 0.5161 1.0517 1.5678 153.01 0.01811 2.939 2.957 380 360 353.6 844.5 1198.0 0.5416 1.0057 1.5473 195.73 0.01836 2.317 2.335 380 825.9 1201.0 0.5667 0.9607 1.5274 400 0.01864 1.8444 1.8630 375.1 400 247.26 806.2 1203.1 0.5915 0.9165 1.5080 420 0.01694 1.4808 1.4997 396.9 420 30S.78 785.4 1204.4 0.6161 0.8729 1.4890 440 0.01926 1.1976 1.2169 419.0 440 381.54 763.2 1204.8 0.6405 0.8299 1.4704 460 0.0196 0.9746 0.9942 441.5 460 466.9 1204.1 0.6648 0.7871 1.4516 480 0.0200 0.7972 0.8172 464.5 739.6 460 566.2 0.6749 487.9 714.3 1202.2 0.6890 0.7443 1.4333 500 500 680.9 0.0204 0.6545 0.7013 1.4146 520 0.5386 0.5596 512.0 687.0 1199.0 0.7133 520 812.5 0.0209 0.7378 0.6577 13954 540 0 4437 0.4651 536'8 ' 6S7.5 1194.3 540 962.8 0.0215 0.6132 1.3757 560 0.3651 0.3871 562.4 625.3 1187.7 0.7615 560 1133.4 0.0221 1.3550 580 0.2994 0.3222 589.1 589.9 1179.0 0.7876 0.5673 550 1326.2 0.0228 0.2675 617.1 550 6 1167.7 08134 0.5196 1.3330 Goo 600 1543.2 0.0236 0 2438 0.46S9 1.3002 620 0.1962 0.2208 646.9 506.3 1153.2 0 8403 620 17869 0.0247 0.8666 0.4134 1.2821 640 0.1543 0.1802 679.1 454.6 1133.7 640 2059 9 0.0260 0.3502 1.2498 660 0.1166 0.1443 714.9 392.1 1107.0 0.8995 660 2365.7 0.0277 1.2086 680 0.0808 0.1112 758.5 310.1 1068.5 0.9365 0.2720
&% 2708.6 0.0304 0.0752 822.4' 172.7 995.2 0.9901 0.1490 1.1390 700 700 30943 0.0166 0.0386 0 1.0612 705.5 0 0.0508 906.0 0 906 0 1.0612 705.5 3203 2 0.0508 TABLE A.2 PROPERTIES OF SATURATED STEAM AND SATURATED WATER (TEMPERATURE:
A.3
Wme, fte/ib 'Irithelpy. Dts/lb tttripy. Stw/sb a F tm.egy. Stu/le 7 y e., E., , w.. em, t-, m.. w.i., t.., .... w., .... T
, . , a, a. f, 4, .. 4 , 4 3302.4 0.00 1075.5 1075 5 0 2.1872 2.1872 0 1021.3 0.0886 0.0846 32.018 0.01602 3302.4 35.023 0.01602 2945.5 2945.5 3.03 1073 8 1076.8 0 006) 2.1705 2.17M SA3 1022.3 0.10 0.10 0 0271 2.1140 2.1411 13.50 1025.7 0.15 0.15 45.453 0 01602 2004.7 2004.7 13.50 1067.9 1081.4 53.160 0.01603 1526.3 1526.3 21.22 10635 1084.7 0 0422 2 0778 2.1160 21.22 1028 3 8.20 0.20 0 0641 2.0168 2.0809 32.54 1032.0 0.30 OJO 64 484 0 01604 1039.7 1039.7 32.54 1057.1 1069.7 0.01606 792.0 792.1 40.92 1052.4 10933 0.0799 1.9762 2.0 %2 40.92 1034.7 0.40 OA0 72.863 79.586 0.01607 641.0 641.5 47.62 1048 6 1096.3 0.0925 1.9446 f.0370 4722 1036.9 0.5 0.5 0.1028 1.9186 2.0215 h3.24 1038.7 0.6 0.6 85.218 0.01609 540.0 640.1 53.25 10455 1098.7 0.01610 466.93 466 94 58 10 1042 7 11008 03 1.8966 2.0083 58.10 1040.3 0.7 6.7 90 09 94.38 0.01611 411.67 411.69 62.39 1040.3 1102.6 0.1117 1A775 1.9970 6239 1041.7 0.8 OA 0.1264 1A606 1.9870 HJ4 1042.9 0.9 0.9 98.24 0.01612 368.41 368.43 66.24 1038.1 1104.3 101.74 0.01614 333.59 333.60 69.73 1036.1 1105.8 0.1326 13455 1.9781 69.73 1044.1 1.0 1 1.0 0.1750 1.7450 1.9200 94A3 10513 2.0 3.0 126.07 0.01623 173.74 173.76 94.03 1022.1 1116.2 i 141 47 0.01630 118.71 118.73 109.42 1013.2 1122 6 0.2009 1.6854 1.8864 109.41 10 %.7 3.0 3.0 0.2199 1.6418 1.8626 120.90 1060.2 4.0 4.0 152.96 0.01636 90 63 90.64 120.92 1006.4 1127.3 8.0 162 24 0.01641 73.515 73.53 130 20 1000.9 1131.1 0.2349 1.6094 1A443 130 18 1063.1 5.0 61.98 138.03 996.2 1134.2 0 2474 1.5820 1 A294 138.01 1065.4' 6.0 1 6.0 170.05 0.01645 61.967 7.0 176 84 0.01649 53 634 53.65 144.83 992.1 1136 9 02581 1.5587 13168 14431 1067.4 7.0 0.0 182.86 0.01653 47328 47.35 150.87 988.5 1139.3 02676 1.5384 1A060 15034 1069.2 8.0 42.385 42.40 1 %.30 985.1 1141.4 0.2760 1.5204 1.7964 156.28 1070.8 9.0 1 9.0 188.27 0.01656 193.21 0.01659 38.404 38 42 161.26 982.1 1143.3 0.2836 1.5043 1.7879 161.23 1072 3 to l 10 14.696 212.00- 0.01672 26.782 2610 180.17 9703 1150.5 0.3121 1.4447 1.7568 180.12 1077.6 14.696 15 213.03 0.01673 26.274 26.29 181.21 969.7 1150.9 0 3137 1.4415 1.7552 181.16 1077.9 15 !
20 227.96 0.01683 20.070 20.06*/ 19627 960.1 1156.3 0.3358 1.3962 1.7320 196.21 1042.0 90 30 250.34 0.01701 13.7266 13.744 218.9 945.2 1164.1 0.3682 1.3313 1.6995 2183 1087.9 30 40 267.25 0 01715 10.4794 10.497 236.1 933.6 1169A 0.3921 1.2844 1.6765 236.0 1092.1 40 80 281.02 0.01727 4.4967 8.514 250.2 923.9 1174.1 0.4112 1.2474 ).6586 250.1 1095.3 50 80 292.71 0.01738 7.1562 7.174 262.2 915.4 1177.6 c 0.4273 1.2167 1.6440 262.0 1098.0 80 70 302.93 0.01748 6.1875 6 205 272.7 907A 1180.6 0 4411 1.1905 1.6316 272.5 1100.2 70 80 312.04 0.01757 5 4536 5 471 232.1 900.9 1183.1 0.4534 1.1675 1.6208 281.9 1102.1 to 90 320.28 0 01766 4.8777 4.895 290.7 894.6 1185.3 0.4643 1.1470 1.6113 290.4 1103.7 to ) 100 327A2 0.01774 4.4133 4.431 298.5 888.6 1187.2 0.47=3 1.1284 1.6027 298.2 1105.2 100 320 341.27 0.01789 37097 3.728 312.6 877A 1190.4 0.4919 1.0960 1.5879 3122 1107.6 120 140 353 04 0 01803 3.2010 3 219 325.0 868.0 1193 0 0.5071 1.0681 1.5752 3245 1109.6 140 360 363 55 0.01815 2.8155 2A34 336.1 859.0 1195.1 0.5206 1.0435 1.5641 3M.5 1111.2 160 180 373 08 0.01827 2.5129 2.531 346.2 850.7 1196.9 0 5328 1.0215 1.5543 345.6 1112.5 180 300 351.80 0 01839 2.2689 2.287 355.5 842 3 1198.3 0.5438 1.0016 1.5454 3543 1113.7 200 250 400 97 0.01865 1A245 1A432 376.1 825 0 1201.1 0.5679 0 9585 1.5264 3753 1115.8 250 300 417 35 0 01889 1.523S 1.5427 394 0 808.9 1202 9 0.5682 0.9223 1.5105 392.9 1117.2 300 350 411.73 0.01913 1.3064 1.3255 409A 794.2 12M 0 0 6055 0 8909 1.4968 408.6 1118 1 350 400 444 60 0 0193 1.14162 1.1610 424.2 7804 1204 6 0 6217 0.8630 1.4847 422.7 1118 7 400 450 4% 28 0 0195 1.01224 .l.0318 437.3 767.5 1204.8 0.6360 0.8378 14738 435.7 1118.9 450 500 46701 0 0199 0 90787 0 9276 449.5 755.1 1204.7 0.6490 0 8148 1.4639 447.7 1118A 500 550 476 94 0 0199 0 82183 0.8418 460.9 743.3 1204 3 0 6611 0.7936 1.4547 456.9 1118 6 550 l 400 48520 0 0201 0 74962 0.7698 471.7 732.0 1203 7 0.6723 0.7738 1.4461 4695 1116.2 600 700 ,503 08 0 0205 063505 0 6556 491.6 710.2 1201.8 06928 07377 1.4304 488.9 1116 9 700 800 51& 21 0 0209 0.54809 0. % 90 509.8 689.6 1193 4 0.7111 0 7051 1.4163 506.7 1115.2 soo 900 t's! 93 0 0212 0 47968 05009 526 7 669 7 11 % 4 0 7279 06753 1.4032 5232 1113 0 900 1000 544.B 0OMo 042435 04460 54 2.6 650 4 1192 9 0 7434 06476 1.3910 53',6 1110.4 1000 1100 ti! 2r C0720 0 378f 3 0 4005 557.5 631 5 1169 1 07575 06216 1.3794 5531 1107.5 1100 1200 67.M 0 0223 0 34013 0252b 571 9 613 0 1164 8 0 7714 O b969 1.3633 5569 1104 3 1200 1300 l. :8.9 420 0227 0 30722 0.3299 585.6 544.6 1180 2 0.7843 05733 1.1577 5SO.! 1100 9 1300 1400 537 07 0 0231 02Y8/1 0 3018 $99 8 576L 1175 3 0.7966 0 5507 1.3474 592.9 1037.1 1400 1500 5 % 20 0 0235 025372 0.2772 611.7 550 4 1170 1 0.8035 0 52&3 1.3373 6052 1093.1 1500 2000 635 80 0.0257 0 16200 0.1883 672.1 466 2 1133.3 0 8625 0 4256 1.7881 662 6 10036 2000 2500 666 11 0 0?M 010209 0 1307 731.7 3616 1093 3 0 9139 0 3206 1.2345 718.5 1032.9 2500 3000 695 33 0 0343 0 050/3 0 0850 801 8 218 4 1070 3 0 9728 01891 1.1619 7822 973.1 3000 3298.2 70147 0 0$08 0 0 0508 906 0 0 906 0 1.0612 0 1.0612 875.9 875.9 3208.2 TABLE A.3 PROPERTIES OF SATURATED STEAM AND SATURATED WATER (PRESSURE) A.4
Abe peen. T**Po'*l**.F 300 400 900 600 700 000 900 1000 1100 1200 1300 1400 150C 6s p) 100 200 y Obl61 392 5 452.3 511.9 571.5 431.1 690.7 3 8 68 00 ISO 2 1195.7 1241.8 1788 6 13M 1 1984 5 (103.74) s 0.1295 2 0509 2.1152 2.1722 2.2137 23708 2J144 s 0.0161 78 14 90.24 102.24 114.21 126 15 138 08 150 01 161.94 173 86 185 78 197.70 209 62 22 6 6 68 01 1148 6 1194 8 1241.3 1288 2 1335.9 1384 3 1433 6 1483 7 1534.7 1586 7 1639.6 1693 3 (162.24) s 0.1295 1.8716 1.9369 1.9943 2.0460 2.0932 2.1369 2.1776 2 2159 2 2521 2.2866 2.3194 23509
, 00161 38 84 44 93 5103 57.04 63 03 69 00 74 98 80 94 86 91 92 87 98A4 104 80 110.76 116.7 10 6 68 02 1146 6 11937 1240 6 1287A 1335.5 1384 0 1433 4 1483 5 1534 6 1586 6 1639.5 1693.3 (192.21) s 0.1295 1.7928 1.8593 1.9173 1.9692 2.01 % 2.0603 2.1011 2.1394 2.1757 2.2101 2.2430 2.2744 y 0 0161 0.01 % 29 899 33 963 $7.985 41.966 45.978 49 964 53 946 57.926 61.905 65.882 69A58 73A3 35 6 58.04 168 09 1192 5 1239.9 1287.3 1335.2 13833 1433 2 1483 4 1534.5 1586 5 1639.4 19332 1747 (213.03) s 0 1295 0.2940 1.8134 1A720 1.9242 1.9717 2 A155 2.0563 2.094f 2.1309 2.1653 2.1982 2 2297 2.25 v 0.0161 0 01 % 22356 25.428 28 457 31.4 % 34 465 37.458 40 447 43 435 46 420 49.405 52.388 55.3 to 6 68.05 168 11 1191.4 1239.2 1286.9 1334.9 1383 5 1432.9 14832 1534.3 1586.3 1639.3 1693.1 174 (227.96) s 0.1295 0.2940 1.7805 11397 1A921 1.9397 1.9836 2.0244 2.0628 2 0991 2.13M 2.1H5 2.1979 2.22 v 0.0161 0 0166 11 035 12.624 14.165 15 685 17.195 18 699 70 199 21 697 23 194 24 689 2ti.183 2 40 h 68.10 168 15 1186 6 1226.4 1285.0 1333 6 1382.5 1432.1 1482.5 1533.7 1585 8 1638 8 1992 7 17 (267.25) : 0.1291 0 2940 1.6992 1.7608 12143 1.8624 1.9065 1.9476 1.9660 2.0224 2.0569 2.0899 2.1224 2 e 0.0161 0.0156 7.257 8354 9.400 10 425 11.433 12 446 13.450 14.452 15.452 16.450 17.448 18.44 60 4 68.15 168 20 1181 6 1233.5 1283.2 1332.3 2381.5 1431.3 1481A 1533.2 1585.3 1638.4 1692.4 174 (292.71) s 0.1295 0.2939 1.6492 1.7134 1.7681 1A168 13612 1.9024 1.9410 1.9774 2.0110 2.0450 2D765 2.106 e 0.0l61 0 0166 0.0175 6.218 7.018 7.794 8.560 9.319 10.075 10 829 11 581 12.331 13D81 13 A29 14.577 80 6 6821 168.24 269.74 1230.5 1.6790 1282.3 1330.9 1380 5 1430.5 1481.1 1532 6 1584.9 1638.0 1692.0 17MA 1802 1.7349 1.7842 1A289 1A702 1.9089 1.9454 1.8800 2.0131 2.0446 2.0750 2.1041 (312D4) s 0.1295 0 2939 0 1371 e 0.0161 0.0166 0 0175 4 935 5.588 6.216 6333 7.443 S t60 8.655 9258 9360 10.460 11.060 11.659 100 h 68.26 168.29 269.77 1227.4 1279.3 1329 6 1379.5 1429.7 1480 4 1532.0 1584.4 1637.6 1991.6 1746.5 1802.2 (327A2) s 0.1295 0.2939 0.4371 14516 1.7088 1.7586 13036 13451 1.883) 1.9205 1.9552 1.9883 2A199 2.0502 2.0794
, 0 0161 0 01 % 0 0175 4 0786 4.6341 5.1637 5.fa31 6.192% 6.7006 7'.2060 7.7096 8.2119 8.7130 9.2134 9.71 120 A 68.31 168.33 269 81 1224.1 1277.4 1328.1 1378 4 1428 8 1479.8 1531.4 1583.9 1637.1 1991J 17462 1802D (341.27) s 0.1295 0 2939 0.4371 1.6286 1.6872 1.7376 1.7829 13246 13635 1.9001 1.9349 1.9680 1.999G 2.0300 2.0592
, 0 0161 0 0166 0 0175 3 4651 3 9526 4 4119 4A585 52995 5.7364 6.1709 6.6036 74349 7.4652 7A946 6.3233 140 1 68.37 168 38 269 85 1220 8 1275.3 1326.8 1377.4 1428 0 1479.1 1530 8 1583 4 16M 7 1990.9 1745.9 1801.7 (353 04) s 0.1295 0 2939 0 4370 1.6085 1.6666 1.7196 1.7652 14071 13461 1A828 1.9176 1.9508 1.9825 2.0129 2.0421 e 0.0161 0 0166 0.0175 3 0060 3 4413 3.8480 4 2420 4 6295 5.0132 5.3945 5.7741 6.1522 6.5293 '6.9055 7.2811 leo n 68 42 168 42 269A9 1217.4 1273 3 1325 4 1376 4 1427.2 1478 4 1530.3 1542.9 1636.3 1990.5 1745.6 1801.4 (363.55) s 0.1294 0 2938 0.4370 1.5906 1.6522 1.7039 1.7499 1.7919 1A310 13678 1.9027 1.9359 1.9676 1.9980 2.0273
, 0 0161 Ct0166 0 0174 2 6474 3 0433 3 4093 3.7(21 4.1064 4.4505 4.7907 5.1289 5 4457 5A014 6.1363 6.4704 140 e 68 47 16847 269 9/ 1213 8 1271.2 1324 0 1375.3 1426.3 1477.7 1529 7 1582.4 1635.9 1640.2 17453 1801.2 (373.C81 s C.1294 0.2938 0 4370 1.5743 1.6376 1.6900 17%2 1.7784 1A176 1.8545 1.8894 1.9227 1.9545 1.9849 2.0142 e 0 0161 0 0166 0 0174 23598 2.7247 3 0583. 3 3783 3 6915 4.0008 4.3077 4.6128 4.9165 52191 5.5209 5A219 200 h 68 52 168 51 269 96 12101 1269.0 1322.6 1374.3 1425.5~ 1477.0 15291 1581.9 1635.4 16898 1745.0 1800.9 (36140) s 0 1294 0 2938 0 4359 1.5593 1.6242 1.6770 1.7239 1.7663 1.8057 1.8426 1A776 1.9109 1.9427 1.9732 2.0025 e OC161 0 0165 0 0174 0 0186' 2.1504 24M2 2.6872 2.9410 3.1909 3.4382 3 6837 3 9278 4.1709 4.4131 4.6546 250 6 68 65 168 63 270 05 3/5 10 1263.5 1319 0 1371 6 1423 4 1475.3 1527.6 1580 6 1634.4 1688.9 1744.2 1800.2 (400 97) s 01294 0 2937 0 4368 0.% 67 1.5951 1.65C2 1.6976 1.7405 1.7601 1.8173 1.8524 1Ad58 1.9177 1.9482 1.9776
, 00161 00165 00174 00186 1.7655 2.0044 2 2263 2.4407 2.6509 2 6585 3 0643 32688 3 4721 3 6746 3 8764 300 4 68 79 1 % 74 27v l4 3 4.15 1237 7 13152 1368 9 1421.3 1473 E 1526 2 1579 4 1633 3 16S8 0 1743 4 1799.6 1.5703 1.6214 1.6/58 1.7192 1.7591 1.7964 1.8317 1.8652 18372 1.9278 1.9572 (417.35) s 0.1294 0 2937 04.%7 05%5 e O'0161 0 01 % 0 0174 0 018C 1.4913 1.7028 13970 2 0332 2.2652 2 4445 2 6219 2.7980 2.9730 3.1471 3.3205 350 h 68 92 163 85 270 24 375 21 1251 5 1311.4 1366 2 1419 2 1471 8 1524 7 1578.2 1632.3 1C87.1 1742 6 17980 (431.73) s 0 1293 0 29 % 0 4357 05%4 1.b483 1.6077 1.6571 1.7009 1.7411 1.7787 1.8141 13477 12793 1.9105 1.9400
, 0 0161 0 0166 0 0174 0 0162 12841 1.4763 1 6490 1.8151 1.9759 2.1339 2.2901 2.4450 2 5967 2.7515 2.9037 400 a 69 05 168 97 270 33 37527 1245 1 1307.4 1%34 1417.0 14701 1523 3 1576 9 1631.2 1656 2 1741 9 1793 2 (444.60) s 01293 0 2935 0 4365 00M3 1.5282 1.5901 1 6406 16350 1.7255 1.7632 1.7988 1.8325 IA647 1.8955 1.9250 v 0 0161 0 01 % 0 0174 0 0186 0 9919 1.1584 1 2.037 1.A397 1.5708 1 6992 1.8256 1.9507 24746 2.1977 2.3200 500 h 69 32 It914 27051 3M 38 12312 1299 1 1357.7 1417 7 1466 6 lb20 3 1574 4 16291 1634 4 1740 3 1796.9 (457.01) s 0 1292 0 2334 04354 0 5660 14971 1%% 1 6{23 165/8 16990 17371 1.7730 1.8069 12393 1 TABLE A.4 PROPERTIES OF SUPERHEATED STEAM AND COMPRESSED WATER (TEMPERATURE AND PRE! SURE)
A.5
t Abs pesos. TimP'telete. F C/sqla. (ut. temp) 100 200 300 400 500 600 700 800 900 100G 1100 1 00 1300 1400 1500
, 0 0161 0 01 % 0.0174 0 0186 0 7944 0 94 % 1 0726 1.1892 13008 1409, 1.5160 14211 1.7252 1 8284 1.9309 600 6 69.58 169 42 27030 375 49 1215 9 1290 3 1 %1.8 1408 3 1463 0 1517.4 1571.9 1627.0 1682 6 1738 8 !?95 6 (48620) s 0.1292 0.2933 04%2 05657 1 4590 1.5329 1.5844 1.63bl 16769 1.71 % 17517 1.7859 1 A184 13494 13792 l
, 0.0161 0 01 % 0 0174 0 0186 0 0204 0 7928 0 9072 1.0102 1.1078 12023 1.2948 1.3858 1.4757 1.% 47 3.6530 I 700 4 69.04 169 65 270 89 375 61 487 93 1281 0 1345 6 14033 Im4 1514 4 1%94 1624 8 1660 7 1737.2 1794.3 1.5090 1.% 73 1 6154 1.6580 3.6970 1 7335 11679 IS005 1 8318 18617 (503.C8) s 0 1291 02932 04%0 0 % % 06889
, 0 0161 0 01 % 0 0174 0 0186 0 0704 0.5774 0 7m 0.8759 0 9631 1 0470 1.1289 1.2093 12835 1.3M9 1.4446 800 4 70.11 169 88 271 07 375 73 48738 1271.6 1339 2 1399.1 14% R 1511 4 1%69 1622.7 167E9 1735 0 1792.9 (518 2.) 6 0.1290 0 2930 0.4358 0 % 52 0.6885 1.4869 1.5484 1.5980 1.6413 16807 1.7175 17522 1.7851 1 8164 1.5464 e 0.0161 0.01% 0 0174 0 0186 0 C204 0 5869 0 6858 0.7713 0 8504 0 9262 0 9999 1.0720 1.1430 1.2131 1.2825 4 900 4 70.37 170 10 27116 375 34 487.83 1260 6 13323 1394 4 14522 15C6 5 1%44 1620 6 1677.1 1734.1 1791.6 !
02929 0.4357 0. % 49 0.6881 1.4659 1.5311 1.5822 1.6263 1.M62 13033 1.7382 1.7713 1.5028 13329 i (531.95) s 0.1290
, 0.0161 0.01 % 0.0174 0 0186 0 0204 0SD7 06080 0 6875 0 7603 0 8295 0 89 % 0 9622 1.02 % 3.0901 1.1529 2000 6 70.63 170 33 271.44 375.96 487.79 1249.3 1325.9 1389.6 1448.5 15044 1%1.9 1018 4 1675.3 1732.5 1790 3 l
(544.58) s 0.1269 0.2928 0.43 % 0. % 47 0.6876 1.4457 1.5149 1.M77 1.6126 16530 1.6905 132 % 1.7589 1.7905 1A207
, 0.0161 0 01 % 0 0174 0,0185 0 0203 0 's!31 0 5440 0 618e 0 6865 0 7505 0 8121 0 8723 0 9313 0 9894 1.0468 f 1100 6 70 90 170 % 271.63 376 08 487.75 1237.3 1318 8 1384 7 1444.7 1502 4 1559.4 1616 3 1673.5 1731.0 1789.0 (5%23)s 0.1269 0.2927 0 4353 0 5644 0 6872 1.4259 1.4996 1.5542 1. 0 00 1.6410 1.6787 1.7141 1.7475 1.7793 12097 e 0 0161 0 0166 0.0174 0.0185 0 0203 0 4016 0 4905 0.%15 0 6250 0 6845 0 7418 C2974 0 8519 0.9055 V.9584 1200 6 71.16 170.78 271A2 376.20 487.72 1224 2 1311.5 1379.7 1440.9 1449 4 15 % 9 1614.2 1671.6 1729.4 1787.6 (567.19) s 0.1288 0 2926 0.4351 0.% 42 0.6868 1.4061 1.485 1.5415 1.5883 1.6298 1.% 79 1.7035 1.7371 1.7691 1.7996
, 0.01(1 0 0166 0 0174 0 0185 0 0203 0.3176 0 4059 0.4712 0 5282 0 5809 0.6311 0 6798 0 7272 0.7737 0 8195 1400 6 71.68 171.24 272.19 376 44 487.65 1194.1 12961 1369.3 1433 2 1493 2 1 % 1.8 1609.9 1664 0 1726.3 1785.0 (b87A7)s 0.1287 02923 0.4344 0.M36 0.6859 1.3652 1.4575 1.5182 1.5670 1.6096 1.6484 1.6845 1.7185 1.7508 1.7815
, 0.0161 0.0166 0.0173 0 0185 0 0202 0.0236 0.3415 0.4ta2 0.45 % 0.5031 0 5482 0 5915 0 6336 0.6748 0.7153 1600 4 72.21 171.69 272.57 376 69 487.60 616.77 1279.4 1358.5 14252 1486.9 1546.6 1605.6 1664.3 1723.2 1782J (604.87) s 0.1286 0 2921 0.4M4 0.% 31 0.6851 0A129 1.4312 1.4963 1.5478 1.5916 1.6312 1.M 78 1.7022 1.7344 1.7657 e 0.0160 0.0165 0 0173 0.0185 0.0202 0.0235 0 2906 0.3500 0.3988 0 4426 0 4836 0.5229 0.% 09 0.5980 0 6243 1800 m 72.73 172.15 272.95 376.93 487.% 615.58 1261.1 12,47.2 1417.1 1480 6 1541.1 16012 16603 1720.1 17791 (621.02) : 0.1284 02918 0.4H1 0.5626 0.68*.3 0.8109 1.4054 1.4768 1. 0 02 1.5753 1.61 % 1.6523 1.6876 1.7204 IJ516
, 0 0160 0.0165 0.0173 0.0184 0.0201 0.0233 0.2488 0.3072 0.35M 0.3942 0 4320 0.4680 0.5027 0.5365 0.5695 3000 6 7326 172 to 273.32 377.19 487.53 614.48 1240.9 1353.4 14087 1447.1 1536.2 1596.9 1657.0 1717.0 1777.1 (63580)s 0.12&3 02916 0.4337 0 % 21 0.6834 03091 1.3794 1.4578 1.5138 1. % 03 1.6014 1.6391 1.6743 1.7075 1.7389
, 0.0160 c.0165 0.0173 0.0184 0.0200 0.0230 0.1681 0.2293 01712 0.3068 0.3390 0.M92 03980 0.4259 0.4529 2500 6 74.57 17334 274.27 37722 487.50 612.08 1176.7 1303.4 1386.7 1457.5 1522.9 1585.9 1647A 1709.2 1770.4 (668.11) s 0.1283 0 2910 0.4329 0 % 09 0.6815 0.8048 1.3076 1.4129 1.47 % 1.5269 1.5703 1A094 1.64 % 1.6796 1.7116 1
, 0 0160 0.0165 0 0172 0 0183 0 0200 0.0228 0 0982 0 1759 0.2161 0.2484 0.2770 0 3033 0.3282 0.3522 0.3753 3000 h 75 83 17t. 88 27522 378 47 487.52 610.08 1060.5 1267.0 1363 2 14402 15014 1574.8 1635 5 1701.4 17(1.8 (695.33) s 0.1277 0 2904 0.4320 0.% 97 0.6796 0302) 1.1966 1.3692 1.4429 1.4976 1.5434 1.5641 14214 1.C'61 1.688J v 0.0160 0 0165 0.0172 0.0183 0.0199 0 0227 0.0335 0.1588 0.1987 0.2301 0.2576 0.2827 0.3065 0.3291 0.3310 3200 6 76.4 175.3 275 6 378 7 487.5 609 4 8008 1250 9 1353 4 1433.1 1503.8 1570.3 16343 1698.3 1761.2 (705.C4) s 0 1276 0.2902 0.4317 0.5592 0 6768 0.7994 0.9708 1.3515 1.4300 1.48 % 1.5335 1.5749 14126 1.6477 1.6806 i 1
e 0 0160 0 0164 0 0172 0.0183 0 0199 0 0225 0.0307 0.1364 0.1764 0.2066 0 2326 0.2 % 3 0.2784 0.2995 0.3198 3500 6 77.2 176 0 276.2 379 1 487.6 608 4 779.4 1224 6 1334 2 1422 2 1495 5 1%3.3 16292 1693 6 17b7.2 s 0.1274 0.2899 0 4312 0 5585 '0 6777 0.7973 0 9508 1.3242 1.4112 ~ -1.4709 1.5194 - 1.M18 1.6002 1.6358 1.6691
, 0 0159 0.0164 0 0172 0.0182 0.0198 0 0223 0 0287 0.1052 0 1463 0.1752 0 1994 0.2210 0 2411 0.2601 02783 4000 h 78.5 1772 277.1 379 8 487.7 606 5 763 0 117a.) 1311.6 14036 1481.3 1552.2 1619 8 1685 7 1750 6 !
e D1271 0 2a93 0 4304 0 % 73 0 6760 0 7940 09M3 12754 1 3807 1.441 1.4976 1.5417 1.5812 1.6177 1.6516 y E0159 00164 0 0171 0 0181 0.01 % 0 0219 0.0263 0.0591 0.1038 0 1312 0 1579 0.1718 0 1660 0 2050 0.2103 5000 6 81 1 179 5 2791 381.2 488.1 604 6 746.0 1042 9 1252 9 13(46 1452.1 1529.1 16(A)9 1670 0 1737.4 s 0.1265 0.2861 0 4?B7 0.5 % 0 0 6726 03880 0 9153 1.1593 1.3207 1.4001 1.4582 1.5061 1.f,481 1.58 63 1.6216 r 0 0159 0.0163 0 0170 0 0160 0 0195 0 0216 0 02 % 0$0397 0 0717 0.1020 0.1221 0.1391 0.1M4 0.1684 0.1817 6000 6 837 181.7 281 0 382 7 AP8 6 602 9 7361 9451 116e 8 1323 6 1422.3 1505 9 1%20 1651 2 17241 s 0 1258 0.2670 0 4271 0 5528 0 M93 0 7826 ,0 9026 1.0176 1.2615 1.35?4 1.4229 1.4743 1.5194 1.5593 15 %.2 e 0.01!4 0.0163 00170 00180 00193 0 0713 00248 0.03M 0 0573 0 0316 0.1004 0 1160 0.1298 0 1424 0.1542 7C00 4 86.2 184 4 283 0 3842 489 3 601 3 729 3 901.8 1124 9 1281 7 1392 2 1482 6 1%31 16386 17111 s 0 1252 0 2859 0 4256 0 5',07 0 6563 0 7/77 0 8926 1 0350 1 20 % 1.3 D I 11904 1.44v6 1.4938 153 5 1.5735 TABLE A.4 PROPERTIES OF SUPERHEATED STEAM AND COMPRESSED WATER (TEMPEPATURE AND PRESSURE) (CONTINUED) A.6
e
- y. ~,;., , .. ,,
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.INropy. Bev/lb. F S 0 2., gy ,p FIGURE A.S MOLLIER ENTHALPY-ENTROPY DIAGRAM A.7
~ '
l PROPEHTIES OF WATER Donalt?e ! (Ibstfti l PIIA Temp Saturated _ 2300 2400 2500 8000 2000 3100 2200 (*F) Liquid 10_00 62.909 62.93 62.951 63 056 62.637 62.846 62.867 62.888 32 62.414. 62.822 62.846 62.87 62.99 62.55' 62.75 62.774 62.798 60 62.38 62.427 62.446 62.465 62.559 62.185 62.371 62.390 62.409 100 61.989 60.568 60.587 60.606 60.702 60.314 60.511 60.53 80.549 200 60.118 57.836 67.859 57.862 67.998 67.537 67.767 67.79 67.813 300 57.310 64.311 64.342 64.373 64.529 63.903 64.218 64.249 64.28 400 63.651 63.89 63.9ff6 63.95 64.11 63.475 63.79 63.825 63.86 410 $3.248 63.46 63.50 63.63 63A9 63.025 63.36 63.40 63.425 420 62.798 63.02 63.065 63.09 63.205 62.675 62.925 62.95 62.99 430 62.356 62.51 62.64 62.56 62.275 E2.125 62.42 62.45 62.475 440 61.921 62.175 62.21 62.41 62.025 62.065 62.10 62.14 450 ' 51.546 61.66 61.76 61.96 61.64 61.68 61.725 61.020 61.175 61.66 61.61 460 61.22 61.25 61.30 61.50 61.1 61.14 61.175 470 '- 60.505 60.70 60.74 60.78 60.825 61.035 60.20 60.62 60.66 60.7 480 60.00 60.31 60.35 60 575 60.13 60.175 60.22 60265 490 49.505 49.685 49.858 60.098 49.666 49.714 49.762 49.81 500 48.943 49.097 49.618 49.56 49.152 49.203 49.254 49.305 4831 48.51 49.05 49.101 610 48.68 48.735 49.01 48.46 48.515 /A.57 48.625 620 47.85 47.91 48.156 48.45 47.919 47.978 48.037 48.056 630 47.17 47.29 47.86 47A9 47.362 47.428 47.494 47.56 46.51 47.23 47.296 640 46.794 46.862 46.93 47.27 45.87 46.59 46.658 46.7'0d 650 46.142 46.216 46.29 46A6 45.92 45.994 46.068 660 45.25 45.54 45.62 46.02 45.22 45.30 45.38 45.46 I 670 44.64 44.844 44.93 45.36 44.50 44.586 44.672 44.758 680 4386 44.11 44.205 44.68 43.ll25 43.92 44.015
$90 43.10 43.73 43D56 43226 43.33 43.434 42.913 43.017 43.122 600 42.321 42.432 42.55 43.14 41.96 42.08 42.196 42.314 610 41.49 41.483 41.816 42283 40.950 41.063 41.217 41.35 620 40.552 41.44 630 39.53 40.388 '
640 38491 39.26 650 37.31 38.000 660 36.01 36.52 670 34.48 34.638 630 32.744 32.144 690 30.516 TABLE A.6 PROPERTIES OF WATER, DENSITY A.8
- Tetde i. Saturated Steam: Temperature Tattle l 5,etit N,4 vat lattaipy Entropy AM Pint
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r-MAST 6L NRC Offic.ial Use Only gg i j l f 6 Nuclear Regulatory bommission Operator Licensing Examination This document is removed from . Official Use Only category on l date of examination. l NRC Official Use Only . I u_______.._..
e , t s / 4 U. S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATIUN FACILITY: _UN7VERSITY OF FLORIDA REACTOR TYPE: TEST DATE ADMINISTERED: 8S/06/09 EXAMINER: ARILDSEN. J. CANDIDATE: ___ INSTRUC,TIONS TO CANDIDATE: Use separate paper for the answers. Write answers on one side enly. 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 20.50 20.50 H. REACTOR THEORY 19.75 19.75 I. RADIOACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS 19.7S 19.75 J. SPECIFIC OPERATING CHARACTERISTICS !
l 19.00 19.00 K. FUEL HANDLING AND CORE ; PARAPETERS l 2; .00-~~ aet.00 L. ADMIrilSTRATIVE PROCEDURES, COND'TIONS AND LIMITATIONS
!?O.?? % Totals l Final Grade All work done on this examination is my owr- .
- ave neither given .
nor received aid, l Candicete's Signature f
NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS I 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. Une 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 +he upper right-hand corner of the first page of each section of the answer sheet.
- 8. Consecutively number each z.nswer sheet, write "End of Category _ _ " as appropriate, start each category on a new page, write only en onc :ide of the paper, and write "Last Page" on the last answer sheet.
- 9. Number each answer as to category and nunber, 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 in 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.
iS. Partial credit mav be given. Therefore, ANSWER ALL PARTS OF THE OUESTION AND DO NOT LEAVE ANY ANSWER BLANK.
- 16. If parts of the a< amination 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.
7
- 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.
y c. ' Turn in all scrap paper aid 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.
4 j
r
. i'
=H. REACTOR THEORY LPAGE 2 OUESTION H.01 (1.00)
A reactor has been operating for an extended period of time at 50% reactor power. WHICH ONE of'the following statements most accurately describes the concentration of samarium-149 if power were increased'to g. and maintained at 75% reactor power 7 e-
- a. The concentration of Sm-149 initially. increases and then levels off to a new equilibrium level higher thannthe equilibrium level at 50% reactor power.
- b. The concentration of Sm-149 initially increases but then decreases to an equilibrium level equal to the equilibrium level at 50% reactor power.
- c. The concentration of Sm-149 initially decreases and then levels off to e new equilibrium level lower than<the equilibrium level at 50% reactor power.
d..The concentration of Sm-149 initially decreases but then increases to an equilibrium level equal to the equilibrium level at 50% reactor power. d (***** CATEGORY H CONTINUED ON NEXT PAGE *****)
F. -
+
9, . . H.- REACTOR THEORY - PAGE. - QUESTION H.02 (1.50)
- a. DEFINE "delayed neutron". (0.S)
- b. EXPLAIN WHY delayed neutrons are important. (l'.0)
J 1 a I. 1 e i
\
4 (***** CATEGORY H CONTINUED ON NEXT PAGE *****) 1
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- m. __
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-H. REACTOR THEORY PAGE- 4 QUESTION H.03 (1.50)
- a. DEFINE "thermal nonleakage factor". 3 (0,5)
- 6. EXPLAIN HOW the thermal nonleakage factor can be (1.0) greater than one.
k I t l l 1 1 (***** CATEGORY H CONTINUED ON NEXT PAGE *****) 1 I _ . - _ _ _ _ _ _ _ _ _l
i H. REACTOR THEORY PAGE S<s t QUESTION H.04 (1.00) Reactor power is 100 watts and increasing with a constant reactor ' period. FOUR (4). minuter, later,~ reactor power is 2 KW. CALCULATE the reactor period during the'last four minutes. SHOW ALL WORK! , y 4 s i i 4 1 .; (***** CATEGORY H CONTINUED ON NEXT PAGE **.***) ., 4
,, ,__ ,-,m-, , . _ _ . - - , . - - - , , . .-- -, y _ , L p ,-,~ , . . , , . v..%., -~<
9-
'F H. . REACTOR THEORY ,
PAGE 6-GUESTION H.05 (2,00) Reactivity.in the core has been determined to be -0.1230 delta k/k.
- OALCULATE how much the Safety. Blades must be withdrawn to increase the present count rate by 50%. SHOW AlL WORK 8 iOTE:
t APPLICABLE CURVES ARE' ATTACHED FOR REFERENCE - ASSUME ALL-RODS WERE INITIALLY FULLY INSERTED ASSUME ALL ROD WITHDRAWALS ARE PERFORMED IN SEQUENCE AND THAT THE FIRST ROD,IS FULLY WITHDRAWN BEFORE THE-NEXT ROD BEGINS ANY WITHDRAWAL o
' S a
9 w
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I a j l (***** CATEGORY H CONTINL.'ED ON NEXT PAGE *****) 1 l
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, q: ; ,
,\
H. REACTOR THEORY PAGE' 7 1 QUEGTION H.06 (1.00) a WHECH ONE of the'following is the reason f or', the -80 second period following a reactor' scram?
- a. The doppler effeet adding positive reactivity dueito the temperature decrease'foll.owing a scram.- ,
- b. The ability of U-235 to fission with source neutrons.
- c. The amount of negative-reactivity added on a scram being greater '
than the Shutdown Margin.
- d. The decay constant of the longest-lived group of delayed neutrons.
J t 4 1 1 i 1 L 4 1 l l in b l I i < 1 i (***** CATEGORY H CONTINUED ON NEXT PAGE *****) u l
t H .' REACTOR THEORY PAGE O QUESTION H.07 (2.00) For each of the following definitions, STATE tha term that is defined.
- a. The factor by which neutron population changeo between generations (from fission).
- b. The decay of an excited nucleus into a stable nucleus with the simultaneous ejection of electromagnetic energy.
- c. The amount of time required for the neutron population to increase by a factor of a" (2.718).
- d. A gemma ray causes the ejection of an electron from a target atom; the gamma ray's energy is totally transmitted to the electron for ejection.
(***** CATEGORY H CONTIN)dD ON NEXT PAGE *****)
iii REACTOR THEORY PAGE 9 i. a 1 i QUESTION H.08 ( i . 00 ) - (4hich one of the following describes the beta decay of a nuclide? ,.
- a. Atomic Mass'# decreases by 1, number of protons remains constant t
- b. Atomic Mass # remains the same, number of protons increases by i-3
- c. Atomic Masu # remains the same, number of protons remains constant
- d. Atomic Mass H decreases by 1, numberiof protons decreases by 1 .g. -
1
'4 e
4 a F s l l (***** CATEGORY H CONTINUED ON NEXT PAGE *****) I l i
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3; v.
\. N.
e H. REACTOR THEORY i PAGE 10
.i GUESTION H.09 (1.00)
Attached Figure il 219 shows o. POWER HISTDi1Y and four possible XENON traces (Reactivity vs.' Time). SELECT the most accu.mte curve for displaying the expected XENON transient. i I l 1 l l l 1 (*t34* CATEGORY H CONTINUED ON NEXT PAGE *****)
F ti H. REACTOR THEORY PAGE 11 '! t s l
'1 I
GUESTION H.10 (1.00) l l Explain how neutrons are produced from the Plutonium-Beryllium (PuBe) sour e. (***** CATEGORY H CONTINUED ON NEXT PAGE *****)
*s t
\
.. , 1 H. REACTOR THEQRX ,
PAGE 12 GUESTION H.ii (1.00) Which one of the following terms of the six factor formula is most affected by "Poisons".
- a. Fast Fission Factor
- b. Thermal Utilization Factor
- c. Thermal Non-Leakage Probability
- d. Reproduction Factor l
l l l l l l l (***** CATEGORY H CONTINUED ON NE:t T PAGE * * * * * ) l l l
H. REACTOR THEORY, PAGE 13 OUESTION H.12 (1.00) MATCH the terms in Column A with the correct relationship in column D. Column A Column 8 a) Specific Entropy 1) DTU/deg F b) Enthalpy 2) Ratio of local b to Critical Heat Flux
- 3) Internal energy of a substance
- 4) % steam mass to total steam & water mass
- 5) BTU /lbm-deg R
- 6) Ratio of Critical Heat Flux to local O
- 7) Internal Energy plus Flow Energy of a substance
- 8) % steam volume to total steam & Water volume i
l l l 1 j (***** CATEGORY H CONTINUED ON NEXT PAGE *****) l I 1
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- t-e, . ,
H. REACTO3 THEORY ,. PAGE 14
\
t QUESTION H.13 (1.00) The ratio of Pu-239 and Pu-240 atome to U-235 atoms changes over core life. Which one of the following pairs of parameters is most affected by-thiu ; change 7 a). Moderator TempeEature coefficient and Doppler Coefficient 4 b). Doppler Coef ficient and Beta c). Beta and Moderator Temperature Coefficient t , d). Moderator Temperature Coefficient and Neutron Generation Time i k
?
l 6 1 l
- l
- I
, I (***** CATEGORY H CONTINUED ON NEXT PAGE *****)
, 2 t!-
H.F REACTOR THE7Y , PAGE .1S
.c 4 i
QUESTION H.14 (1.00)
-Indicate whether each of the following will cause the Differential Rod i Worth to INCREASE, DECREASE or have NO EFFECT. (Consider eacti case ,
separately) a). An adjacent rod is inserted to the same height. b). Moderator Temperature is INCREASED. s 4 k e -) I il i i t i (***** CATEGORY H CONTINUED ON NEXT PAGE *****) j
1 H. REACTOR THEORY PAGE 16 QUESTION ,,H.15 (1.00) Which statement below describes centrifugal pump RUNOUT conditions?
- a. High Pressure, Low Flow, High Power Demand
- b. High Pressure, Low Flow, Low Power Demand
- c. Low Pressure, High Flow, High Power Demand
- d. Low Pressure, High Flow, Low Power Demand
- e. Low Pressure, Low Flow, High Power Demand J
l 4 J l (***** CATEGORY H CONTINUED ON NEXT PAGE * * * * * )
' /
H. ' REACTOR THEORY' .
, PAGE. 17 l'
r. 3 '
.l.
i s QUESTION H.16 ( 2 . S f' ) DEFINE EACH of the following ' terms: +
- a. Subcritical multiplication i !
- b. Reflector
.l. !
'! c., Xenon. burnout
- d. Decay. heat
- e. Differential rod worth J
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j I. RADICACTIVE' MATERIALS HANDLING DISPOSAL AND/fAZARDS. PAGE 18
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QUESTION I.01 (1.00) If you are in an 80 mrad /hr neutron radiation field (noutron energy 20 Mev), what is the dose in MREM that you would receive after 45 minutes? I
- a. 60 MREM b, 120 MREM
- c. 180 ' MREM
- d. 600 MREM i
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I. ' RADIOACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS PAGE 19 s -i : L s i 1 QUESTION I.02 ( .50) ANSWER Whether the following statement is TRUE or FALSE. chnrily after power operations, a few drops of primary coolant could , contaminate a swipe to 450 cpm beta-gamma activity. Adjusting for detector efficiency, this indicates approximately ten times the permissible UFTR limit. t 1 'l r 4 a 4
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s I. RADIOACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS = PAGE 20 QUESTION I.03 ( .50) ANSWER whether the following statement is TRUE or FALSE. Samples, NOT LEAVING the UFTR building complex, thest were irradiated via the pneumatic rapid sarAple transfer (RABBIT) system are required ! to have processed a completed UFTR form SOP-D.48, Sample Record Index. ,
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e-t I. RADIOACTIVE MATERIqyS_ HANDLING _ DISPOSAL AND HAZARDS PAGE 21
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, QUESTION I.04 (1.00) $ What UFTR form must be untid to assure that all requirements have been met before containers holding radioactive, reactor waste atin transferred ' j to a carrier or licensed waste processor.' l v I i e W
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. i I. RADIDACTI /E MATERI ALS HANDLING DISPOSAL AND HAZARDS . PAGE 22 i
i e QUESTION I.05 (1.00) STATE the unshielded cample radiation levels (two) 'beyond which the Radiation Control Officer or his designated alternate must authorire transfer.
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I. RADIOACTIVE f1ATERI ALS HpNDLING DISPOSAL AND HAZARDS PAGE 23 OUESTION I.06 (2.50)
- a. LIST the two (2) conditions specified by UFTR Technical Specifications in which the reactor vent system is required to be operated,
- b. LIST the three (3) failure (s) or indication (p) that UFTR Technical Specification 3.4.3 requires for the reactor vent system to be immediately secured.
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T. RADf0 ACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS PAGE 24 QUESTION I.07 (2.00)
- a. STATE the maximum permissible concentration (MPC) of the gaseous effluent discharge of Argon-41 as specified in UFTR SOP-E.6 and UFTR Technical Specifications.
- b. STATE whether the associated sample of the core ventilation flow is taken PRIOR TO or AFTER dilution by the diluting fan.
- c. What factor is used to account for atmospheric dilution of Argon-41 in the determination of stack effluent concentrations as per UFTR Technical Specifications?
- d. STATE the minimum time required after a reactor startup,to allow for the Argon-41 emission level indicated by the stack monitor to stabilize.
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q I. RADf0ACYIVE MATERIALS HANDLING DISPOSAL AND HAZARDS.- PAGE 25 .' i QUESTION I.08 (1.00) , Who's approval (if any) is required prior to the performance of any j maintenant:e to CORRECT a significant primary coolant leak. ! I s P 6 a 1 , e i 'I i t i 1 5 [ Y I 4 i ,{ 1 1 l f 4 l (***** CATEGORY I CONTINUED ON NEXT PAGE *****) [ l
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1. I. RADIOACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS PAGE 26 P k QUESTION I.09 (2.00) LIST the four (4) actions which must be taken in the event that radiation levels following shielding alterations are found to be significantly in excess of anticipated radiation levels.
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N 1. RADIDACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS _ PAGE 27 , J
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GUESTION I.10 (J 00) l i ! . STATE the criterion-(dpm/cm^2 above background) used to permit the ' return to normal use of a potentially contaminated area that had been isolated. -! l 4' 9 I l i n' s i i 1 (***** CATEGORY I CONTINUED ON NEXT PAGE *****) ! l l 1
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'I o RADIOACTIVE MATERIALS HANDLING DfSPOSAL AND HAZARDS PAGE 28 OUESTION .I.11 (1.00)
A point source of gamma radiation gives an exposure rate of 90 mR/hr-at ONE meter, CALCULATE the exposure rate at THREE meters, j ..- l 1 l l
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I. RADIOACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS TAGE 29 QUESTION I.12 (1.50) What radiation reading would prohibit the changing of primary resins? (Identify the type instrument used,-level, and location.) i i l l i e (***** CATEGORY I CONTINUED ON NEXT PAGE *****) l l
I. RADIOACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS PAGE 30 QUESTION .I.13 (1 00) '
' State the shield water tank water resistivity (kilohm-cm) at which the domineralizer cartridge needs replacement.
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. . s I. RADIOACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS PAGE 3i L
QUESTION I.14 (i 00)
- a. STATE the maximum reactor power level at which the opening of the vertical ports for sample irradiation shall be considered a routine operation.
- b. Would such a routine operation require an RWP7 y r
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I. RADIOACTIVE MATERIALS HANDLING DISPOGAL AND HAZARDS PAGE 32
)
QUESTION I.15 (1.50) STATE the normal working done rates (in MREM /wk for whole body, extremities, and skin) which require preparation of a radiation work permit (RWP) and comp 1.iance with the provisions of UFTR SOP-D.2 prior to commencement of work or operations which have the potential of exceeding those rates.
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a i I. RADIOACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS .PAGE 33 (1.25) OUESTION I.16 , STATE.the specific definitions of a "RADIATION AREA" and of a "HIGH RADIATION AREA." t, I i
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.. s J. SPECIFIC OPERATING CHARACTERISTICS PAGE. 34 <
GUESTION 'J.01 (2.00) ANSWER EACH of the following questions TRUE or FALSE.
- a. Thrt console " Power ON " switch controls power -to all &+b d i k control circuits and nuclear instrumentation channels,
- b. Control Blade magnet power is controlled through the 3 position " OPERATE " key switch,
- c. Depressing a Control Blade backlit DN switch will cause that Blade to return'to the full in position. *
- d. A key operated switch on the back of the console controls ,
the Secondary System City Water Valve. A t t (***** CATEGORY J CONTINUED ON NEXT PAGE *****)
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. J. SPECIFIC OPERATING CHARACTERISTICE PAGE 35' QUESTION J.02 (1.00)
, STATE the purpose of the sixteen (16) vertical foil slots in the Reactor.
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. s J. SPECIFIC OPERATING CHARACTERISTICS PAGE 36 GUESTION J.03 (2.00) ANSWER EACH of the following questions con,cerning the Core Vent System.
- a. STATE the purpose of the Vacuum Breaker Vent Lines. (1.0)
'b. Where is the Effluent Gamma Detector located 7 (0.5)
- c. The Vent Damper is electrically interlocked so th5t it cannot be opened unless the dilution fan is energized.
STATE the purpose of this interlock. -(0.5) 1 I l l I
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- J. SPECIFIC-OPERAT,ING' CHARACTERISTICS ', - PAGE,'3 i
h 3 . QUESTION J . 04_. (1.00) , s STATE'two.(2)' purposes of.the graphite. blocks in the core.
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.k.z s-Y. D .- SPECIFIC OPERATING CHARACTERIGTICS PAGE~ 38' 4
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.GUESTION J.05- (2.50) f ..k'
't,IST five~=(S)-conditions which will initiate a Full Trip of' '
the -Reactor and STATE the Nuclear instrument' Channel that is. ' associated with each Trip. -(tti,tt2, both, or' n on e' . ) i L (NOTES INCLUDE SETPOINTS IN YOUR ANSWER)
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l s l ,- , . i LJ . SPECIFIC OPERATING CHARACTERISTICS PAGE 39 l-
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l QUESTION. J.06 (1.00) STATE.the interlock that is associated Aith-starting the <
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J SPECIFIC OPERATING CHARACTERISTICS ; PAGE 40 i i
.Gb ESTION J.07 (2.50)
LIST five (5) conditions / interlocks that will function to prevent Control Blade withdrawal. 1 1 6- l (***** CATEGORY J CONYINUED ON NEXT PAGE *****) u
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,- 3 J, SPECIFIC OPERATING _ CHARACTERISTICS PAGE 41.
t I j 7 , ,. GUESTION J.08 (1.50) LIST ALL ot the conditions that should result in both MANUAL and AUTOMATIC actuation of the Evacuation Alarm. l T I l l l
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1 J. SPECIFIC OPERAT'.NG CHARACTERISTICS PAGE- 42 [t; p. QUESTION J.09 (1.50) 9 ' ',1 City tap water is used for makeup.to the Primary System. ;.
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EXPLAIN HOW this water is purified to comply with Tech Spec requirements. Include in your answer a discussion of the physical processes by which the water is purified. 4 f 1 i , 1 1 4 i (***** CATEGORY J CONTINUED ON-NEAI PAGE *****) i i , .
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% i J. SPECIF7C OPERATING CHARACTERISTICS PAGE 43 GUESTION J.10 (2.25)
- a. DESCRIBE.HOW the resistivity of the Primary Coolant is measured.
NOTE: INCLUDE IN YOUR ANSWER THE LOCATION OF ANY COMPONENTS USED.
- b. EXPLAIN HOW flow is maintained through the Purification System when the Purification pump is secured.
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-s I e J. SPECIFIC OPERATING CHARACTERISTICS PAGE ,
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OUESTION J.11 (1.S0) , EXPLAIN WHY the Reactor Protection System is Fail Safe and requires no auxilliary power to ensure shutdown. INCLUDE \ in your answer e, complete description of how the Reactor ' 4 Trips on loss at Of f site Power. ,
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Y QUESTION J.12 (1.00)
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DESCRIBE the Power Supply to the Area Radiation Monitors. 1 l l l (***** END OF CATEGORY J *****) i
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i l Kn, FUELHANDLINGANDCORE_hARAMETERS / PAGE 46 i GUESTION K.01 (2.00) ANSWER EACH of the following statements as TRUE or FALSE. o i \'
- a. Partial elements from which new fuel elements can be assembled may be fastened together with non-standard material.
- b. The Reactor Manager may authorize special tests with irradiated fuel to be performed outside of the shield tank.
- c. During fuel element disassembly, the Clamp bperating Tool is used to permit the clamp jaws to grapple only the bottom plate.
- d. Only a licensed operator or a trainee under the direct supervision 6 of a licensed operator may insert fuel into the reactor.
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; .r . 1 K. FUELHANDLINGANDCOREPARAMkTERS PAGE 47 h
= 4 3 dUESTION KJ02 ( .50) , ,
e e t ? . _ . j~ ' Answer whether the following. statement in TRUE or FALSE. ,. Placing an unaltered fuel' assembly in its origina1' position in the core af ter h'aving removed it f or. inspection is not. considered to be T-
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fuel;1oading. 6
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y-. K. FUEL HANDLING AND+ CORE PARAMETERS PAGE ~48-4 7
, / )
0 GUESTION K.03 (3.00) ,
. FILL IN THE BLANKS.with the appropriate numbers,
- a. The fuel putte uranium enrichment is pif rcen t .
3
- b. The core .is presergtly composed of fuel bundles and- ,
dummy bun'dles arransjed in water filled aluminum boxes. , c. Each fuel bund.1'e is composed of fuel plates. ,
- d. The ACTUAL available excess reactivity in the ' presen't configuration is itbout percent delta N / K.
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K. FUEL HANDLING AND CORE PARAMETERS PAGE 49 R 1
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j- QUESTION K.04 (1.00) The immedihte actions in the event of a Radiological Emergency per SOP-B.i are independently specified for' WORKING and NON-WORKING HOURS. In this - regard, wiiat is .the definition o/ WURKING HOURS 7
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K. FUEL HANDLING'AND CORE PARAMETERS PAGE 50 1' . , s QUESTION K.05 (1.00) State the limit of Keff (under optimum con'ditions of moderation and ~ reflection) for the geometry of fuel element et- fuel device storage and handling out of the core. l o t t l s (***** CATEGORY K CONTINUED ON NEXT PAGE * * * * * ) ! l 1 l l i
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K. FUEL HANDLING AND CORE PARAMETERS PAGE S1 i QUESTION K.06 (1.00) What weight 12.mit is placed on loads lifted over-the control blade drive units when all the control blades are not fully inserted? f k' (***** CATEGORY K CONTINUED ON NEXT PAGE * **** ) e + 4 - -~, ---.,,m - _ , s , -. ,. , , , . , , ,,, ._ , , _ , ,
t K. FUEL HANDLING AND CORE PARAMETERS -PAGE S2 ;
. QUESTION K.07 (1.00)
State the manner of designation and required. qualification for the "Supervisor-in-Charge" of directing irradiated-fuel transfer.
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. i 1 K. FUEL HANDLING AND CORE PARAMETERS PAGE 53 l l l l QUESTION K.08 (1.00) State what are used and where they are placed in order to separate and secure fuel assemblies to prevent lateral and vertical movement to assure proper flow and a constant fuel-to-moderator ratio. (***** CATEGORY K CONTINUED ON NEXT PAGE *****)
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K. FUEL HANDLING AND CORE PARAMETERS PAGE 54 i 4
-QUESTION K.09 (2.00)
State the minimum staffing requirements for fuel transfer operations.
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K. FUEL HANDL.f NG AND CORE PARAMETERS PAGE .55
- ;D:
GUESTION K.10 (1.50) l e
, State specifically how-the fuel handling tool disengagement from the fuel assembly is verified following a fuel transfer.from the transfer-cask to the spent fuel pit. .
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K, FUEL HANDLING AND CORE PARAMETERS PAGE S6
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OUESTION K ii (2.00) In accordance with fuel loading protec;ure UFTR SOP-C.2,
- a. State the required number of independent neutron monitoring channels that must be installed and operational for monitoring the f approach-to-criticality.
[ b. S t a t <e the number of independent neutron monitoring channels l available an permanently installed control console nuclear instrumentation. 1 I l l i 1 (***** CATEGORY K CONTINUED ON NEXT PAGE *****)
K. FUEL ~ HAND' LING'AND CORE PARAMETERS PAGE 57 b GUESTION K.12 (1.00) State the radiological limitation (s), if any, pertaining to the readjustment of the fuel assembly Jig table level with an irradiated element or plate on the jig table. , 4 3 (***** CATEGORY K CONTINUED ON NEXT PAGE *****)
;g K.- FUEL HANDLING AND CORE PARAMETERS PAGE 59 QUESTION K.13 (1.00)
Describe how the fuel handling tool is designed to prevent the inadvertent dropping of a fuel element.
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e i. j9 K. FUgL HANDLING AND_ CORE PARAMETERS PAGE- 59 i i 1 l GUESTION K.14 (1.00) i !- Describe how the HEX HEAD NUTS presently installed on some fuel l ' elements are removed during fuel element disassembly. l; t
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Le ' ADMINISTRATIVE PROCEDUF<ES. CONDITIONS AND LIMITATIONS PAGE 68 OUESTION L.01 (1.00) Which one of the following items is NOT required to be posted in the control room?
- a. Form NRC-3, "Notice to Employees"
- b. All UFTR Emergency Call Lists (#1,*M2, and #3)
- c. Current Operator Licenses for all operators
- d. Limits on energy production for Argon-41 effluent
- e. Form RC-4., "Safety Rules for a Radioisotope Laboratory" '
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L. ADMINISTRATIVE PROCEDURES. CONDITIONS AND LIMITATIONS PAGE 6i 9
-t .
OUESTION L.02 (1.00) Which one of the following is NOT always a reportable occurrence? a..A violation of Safety Limits
- b. An unanticipated change in reactivity greater than one dollar (not resulting from a reactor trip due to a known cause) <
- c. A Reactor Safety System Component malfunction that renders the system incapable of performing its intended safety function that was discovered during a meintenance test
- d. An observed inadequacy in the-implementation of administrative controjo such that the inadequacy could have caused the existence or development of an unsafe condition with regard to reactor operations
- e. Operation with actual Safety System Settings for required systems less conservative than the Limiting Safety System Settings (LSSS) specified in Technical Specifications 4
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L. ADMINISTRATIVE PROCEDURES. CONDITIONS AND. LIMITATIONS PAGE 62 OUESTION L.03 ( .50) ANSWER whether the following statement is TRUE or FALSE. The Secondary Flow by the City Water System has an associated Reactor Trip set at 8 gpm (as measured by a flow"switch) to initiate at or above 1KW after a 10-second warning. (***** CATEGORY L CONTINUED ON NEXT PAGE *****)
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L. ADMINISTRATIVE PROCEDURES. CONDITIONS AND L]MfTATIONS P9CE 63 .
- 1 GUESTION L.04 '3.00) (2.ib)
Match the evolution / function in Column A to the ONE responsible person (s) in Column B (Answers in Column B may be used more than . once.) Column A , Column B
- 1. designates personnnel for the A. Licensed Reactor Operator performance of maintenance B. Reactor Manager
- 2. circuit breaker operation C. Radiation Control Officer
- 3. indicates specific codes,
-standards, and regulations D. Reactor Safety Review to be used or referenced in Subcommittee the various phases of.a modification 460 9 M4_ e>q u i - M to eign only cr-t+4n.
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- 5. completion of a TRIP EVENT DATA ANALYSIS AND EVALUATION
- 6. grants written authoriza tion of major maintenance items 9
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c.. . . , t-L. ADMINISTRATIVE PROCEDURES. CONDITIONS AND LIMITATIONS PAGE 64 e QUESTION L.05 (1.00) ANSWER EACH of the following.concerning reporting and recording events. (FILL IN THE BLANKS)
- a. The NRC Operations Center shall be notified by telephone within minutes after discovery of any accidental criticalty,
- b. The initial telephone notitication (stated above)'shall be fellowed within a period of days by a written report.
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L. ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS PAGE 65-A 4 QUESTION L.06 (1.00) < With what publication are the Special Test Procedurgs (having attached Special Test Control coversheets) that have general or repeated applicability maintained? m i 4 9 V t f. (***** CATEGORY L CONT 7NUED ON NEXT PAGE *****)
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a F2 y L. DMINISTRATIVE PROCEDURES, CONDITIONS AND-LIMITATIONS > .PAGE- 66 ,
, 4 QUESTION L.07. (3.00) i State the minimum staffing required by UFTR Technical Specifications
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t when the reactor is not secured . (FCIR EACH POSITION include personnel qualification requirements, personnel location requirements, and the time limits of when required to be at the: location), t-N (#
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,L. ADMINISTRATIVE PROCEDURES. CONDITIONS AND LIMITATIONS PAGE 67 GUESTION L.08 (2.00)
Answer the followirig questionu concerning making changes to procedures.
- a. Wh6 is permitted to make minor modifications 'to original procedures which DO NOT change their original intent?
- b. What-approval requirement must follow (include' time requirement)?
- c. Who is permitted to make Temporary deviations from procedures in order to deal with special or. unusual circumstances or conditions?.
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L '. ADMINISTRATIVE PROCEDURES. CONDITIONS AND LIMITATIONS. PAGE 69 . t QUESTION L.09 (1.00) State,the response (s) and / or notification (s) required by the UFTR Emergency Plan upon receipt of "vague threatts" via advisories from friendly agencies such as the Sheriff's Office. a
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L. ADMINISTRATIVE PROCEDURES. CONDITIONS AND' LIMITATIONS PAGE 69 ' QUESTION L.10 (1.00) State who activates the emergency organization in'the event of a Notification of Unusual Event, and to whom (phone # or organization) the request for support external to the UFTR' facility is:made. . 4-0 L
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L'. ADM_INISTRATIVE PROCEDURES. CONDITIONS AND LIMITATIONQ PAGE 70 s QUESTION L.11 (2.00). STATE the three (3) actions (in order) that are required if the
-Reactor'is operating at 100 KWth and stack counts indicate i
SIGNIFICANTLY above the maximum equilibrium level. 1 h i 1 i i 6 k i (***** CATEGORY L CONTINUED ON NEXT PAGE *****)
p e . L. ADMINISTRATIVE PROCEDURES. CONDITIONS AND LIMITATIONS PAGE 71 .i' OUESTION L.12 (1.50) LIST the three (3) actions that are required if radiation level indications of about 1.5 mr/hr are indicated by the Atea Radiation Monitors while at 5 KWth power. t 1 1 l (*****. CATEGORY L CONTINUED ON NEXT PAGE *****) l l l l i
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L. ADMINISTRATIVE PROCEDURES. CONDITIONS'AND LIMITATIONS ,PAGE 77 t q-i , , t OUESTION L.13 (1.00) During Reactor Power operations,.what is the maximum period of time that the~ Primary Coolant demineralizer System can remain tiecured ? 1 s
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- I
(***** CATEGORY L CONTINUED ON NEXT PAGE *****) 4 i f
-i L. ADMINISTRATIVE PROCEDURES. CONDITIONS AND LIMITATIONS PAGE; 73
/
QUESTION L.14 (1.00)
- a. STATE the time within which a record must be made of any discovered vulnerability in the Safeguards System that could have allowed undetected access to the, Reactor Cell had compensatory measures not been established.
- 6. Does this time limit INCLUDE TIME FOR DISCOVERY by UFTR ,
4 staff personnel or by University Police Department personnel acting on behalf of the staff. (YES or NO) , j t 5 V i i I l 1 (***** CATEGORY L CONTINUED ON NEXT PAGE *****) 1
OP ' i h i L. ADMINISTRATIVE PROCEDURES. CONDITIONS AND LJMITATIONS PAGE' -74~ GUNSTION L.15 (1.00) What is.used to determine the efficiency of the detector system used to measure the Argon-41 activity in the UFTR Coro Vent air samples, > s 4 f L i 1: i h I i
.;. I i- l
(***** END OF CATEGORY L *****) (************* END OF EXAMINATION *********4 i o l l
y _. y. ,
.. ., u. l l MSTEtt H. hEACTORThEORY PAGE 7S ANSWERS -- UNIVERSITY OF FLORIDA -88/06/08-ARILDSEN, J.
SRO ANSWER H.01 (1.00) d REFERENCE Westinghouse Design Technical Manual, Chapter 2 ANSWER H.02 (1.50)
- a. A neutron born sometime after fisslon (time greater than 10E-14 sec) from the decay of fission fragments (delayed neutron precursor).
- b. Delayed neutrons allow control of the reactor by increasing the average neutron lifetime.
REFERENCE General Electric, Reactor Theory, Chap. 4 I ANSWER H.03 (1.50)
- a. The fraction of thermal neutrons that escape leakage while thermal.
(0.5)
- b. If a reactor had a reflector, fant neutrons which escaped from the core can be thermalized and then reflected back into the core (0.5). The net result can be that more thermal rirutrons enter the core than leak from it. (0.5)
REFERENCE General Electric, Reactor Theory, App. G l l
)
l l
y
. 4 H. REACTOR THEORY PAGE' 76-ANSWERS -- UNIVERSITY OF FLORIDA -89 / 06 / 0!3- AR I LDSEN , J.
ANSWER H.04 (1.00) - P = Po*exp (t/T) (0.4) T = t/In(P/Po) . (0.4) Tx 240/In(2000/100) = 80 sec (0.2) i REFERENCE General Electric, Reactor Theory, Chap. 3 ANSWER H.05 (2.00) Subscript i refers to values when all rods are inserted. Subscript 2 refers to values when Rod A is withdrawn. Keffl = 1/(1-pi)
= 1/(1+0.1230)
= 0.89 (O.
CR1/CR2 = (1-Keff2)/(1-Keff1) => Keff2 = 1-[CR1/CR2 * (1-Koff1))
= 1-(2/3 * (1-0.09)]
= 0.927 \(0.6) i p2 = (Keff2-1)/Keff2 '
= (0.927-1)/0.927 4 1
= -0.0790 (0.%) l 1
Required reactivity addition needed = p2 - p1 = +0.0440 (0.2) ! l w lk h ( - 3*/r)-witherw l From IRW curve, SB 1 rreus t be 400% e n 4ph so) ( 0.Mi ) j SB 2 must be 100 */. (* 3%+ withdrawn 4puca) (0.R1) i SD 3 tr.ust be yt+--X41 withdrawn (y=4Aimsel ( 0.N ) j REFERFNCE R,b r m e., b. ,. % 1 b y w % n o (.1 2.0) C(. t ) General Electric, Reactor Theory, Chap. 3 UF1R FSAR 1 l i J
C ^
' 'f.
,, .t, ,
' 4+
' i ,'
, l
.. . H '. REACTOR THEORY. > PAGE. '77 ANSWERS -- UNIVERSITY OF FLORIDA -88/06/08-ARILDSEN, J. F ANSWER H.06 (1.00)
(d) ,, t REFERENCE DPC, Fundamentals of Nuclear Reactor Engineering, p. 106 VEGP, Training Text,.Vol. 9 p. 21-47 , Westinghouse Reactor Physics,;pp. I-3.17 & 19 I ANSWER H.07 (2.00)
- a. K-effective (0.5 each)
- b. Gamma Decay
- c. Period (Fermi Age)
- d. Photoelec tr!.c Ef f ec t - ca " - b'g*h Sb nu o i .r REFERENCE ,
DPC, Fundamentais of Nuclear Reactor Engineering, p.56,09 General Electric, Reactor Theory, Chapters 1, 3 ANSWER H.08 (1.00) i (b) REFERENCE NUS, Vol 2, pp 7.3-2 , I i l AN!iWER H 09 (1.00) ' (c) REFERENCE i DPC, Fundamentals of Nuclear Reactor Engineering, p.163 l General Electric, Reactor Theory, Chapter 6 l EIH: GPNT,Vol VII, Chapter 10.1-83-86 , BSEP: L/P 02-2/3-A, pp 172 - 176; 02-OG-A', pp 57 - 60 l 1 l 4 I I
. -- '.. ,/
. 1 H. REACTOR THEORY
'PAGE 78
-ANSWERS -- UNIVERSITY OF FLORIDA -89/06/94 -t < N, J.
t ANSWER H.10 (L.00) 4 239 235 4 Pu --> U + alpha (0,5) 94 92 2 9 4 12 1 De + alpha --> C + '
. (0.5) 4 2 6 E REFERENCE DCP, Fundamentals of Nuclear Reactor Engineering, p.113 ANSWER H.11 (1.00)
(b) REFERENCE DPC, Fundamentals of Nuclear Reactor Engineering, p. ISO 1 ANSWER H.12 (1.00) a) 5 b)fd' "7 (0.5 each) REFERENCE NUS, Vol 4, pp 1.4-2, 1.4-4, 3.5-4, 6.4-6
- ANSWER H.13 (1.00) b ,
l REFERENCE CR Training Ltr TRA B5-0013 DPC, Fundamentals of Nuclear Reactor Engineering, p. 38, 39, 146 l I l
]
- c. ,
- c '..
-H8- REACTOR THEORY .PAGE- 79 .
ANSWERS -- UNIVERSITY OF FLORIDA -88/06/00-ARILDSEN, J. , L ANSWER H.14 (1.00) a a). Decrease (0.5 each) b). Increase t REFERENCE i DPC, Fundamentals of Nuclear Reactor Engineering p. 134-136 SON /WBN License Requal Tr ain'ing, "Core Poisons" ANSWER H.iS (1.00) > C REFERENCE i NUS, Vol 4, pp G-8 ANSWER H.16 (2.50)
- a. Steady state neutron level higher than source alone due to the multiplication of fissionable fuel.
- b. Material at core edges,which reduces neutron leakage by scattering neutrons back into the core.
- c. Removal of Xe-135 from the core by absorption of a neutron to Xe-136.
- d. Heat produced by the decay of radioactive nuclides.
- e. Reactivity change per unit of rod motion.
REFERENCE d General Electric, Reactor Theory, App. G 4 i I l
- q. - . .
I.- RADIOACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS PAGE 80 ANSWERS -- UNIVERSITY OF FLORIDA -88/06/08-ARILUSEN, J. ANSWER I.01 (1.00)
-b- d QF=10 (80)(45/60)(10)=600 (1.0)
REFERENCE 10 CFR 20.4 ANSWER I.02 ( .50) TRUE (0.5) REFERENCE UFTR: SOP-D.3, 4.3 i ANSWER I.03 ( .50) FALSE (0.5) REFERENCE UF7R: SOP-D.4, 7.7 ANSWER I.04 (1.00) Radioactive Reactor Westo Shipment Ch?cklist (UFTR form SOP-D.SA) (1.0) REFERENCE UFTR: SOP-D.5, 4.12 ANSWER I.05 (1.00)
- 1. 0 1.5 R/hr at one foot 10757'
.or' (200mR/hrat the surface of the transfercontainer) J0hid' REFERENCE UFTR: SOP-D.4, 7.3 i
i I
T I. RADIOACTIVE MATERIALS HANDL!NG DISPOSAL AND' HAZARDS PAGE 01 ANSWERS -- UNIVERSITY OF FLORIDA ~88/06/08-ARILDSEN, J. t q t [ l ANSWER I.06 (2.30) !
- a. 1. During reactor operations ,
l' 2. Stack. monitor indicates greater than 10 cps
- b. 1. Failure in the monitoring system
- 2. Failure of the absolute filter
- 3. Unanticipated high' stack count rate (0.5 each) t REFERENCE j
UFTR: Tech. Spec. 3.4.3 i ANSWER I.07 (2.00)
- a. 4.0 E-8 microC/ml ,
! b. PRIOR TO ; i ,! c. 200 l
)
- d. 4 hours (0.5 each) i REFERENCE .i
- UFTR SOP-E.6 .
j- UFTR Tech. Spec. 3.4.2 { i ANSWER I.08 (1.00) l I The Reactor Manager or his authorized representative (1,0)
- REFERENCE 1 UFTR SOP-D.3. 4.3.1 l
1 1 I l 4 I a J I
,. n
. f -e ,
!. RADIOACTIVE MATERIALS HANDLING-DISPOSAL AND. HAZARDS PAGE 02 ,
. ANSWERS -- UNIVERSITY OF FLORIDA -88/06/08-ARILDSEN, .J..
l t ANSWER I.09 (2.00) ,
- 1. Shutdown the reactor immediately
- 2. Promptly replace the shielding
- 3. Notify the Reactor Manager or his designated' representative -
4 '. Evaluate the situation and determine the counc of the: higher radiation levels (0.5 each) REFERENCE UFTR: SOP-E.2, 7.1.3 ANSWER I.10 (1.00) 20 dpm/cm^2 (1.0) { REFEREr CE l Emergency Plan for the UFTR, 7.1.2.3 ANSWER I.11 (1.00) 10 mR/hr (1.0) REFERENCE UFTR FSAR 12.10 ' f
')
i ANSWER I.12 (1.S0) l A beta gamma survey instrument (0,5) indicating 200 MREM /hr (0,5) on contact with the demineralizer (0.S) :9 i REFERENCE l UFTRt SOP-E.1, 4.3 ;
/
i I 1
/ !
I
$ a,
' i s e, * ., / ,j.
. _( _ l J". - RADIOACTIVE MATERI ALS HANDLlRG DISPOSAL AM) HAZARDS PAGE 83
't.
k,ANSWERSf--UNIVERSITYOFFLORIDA -88/06/08-ARILDSEN, J. i i V 1
)
ANSWER I.13 (1.00) ' [ 600 kilohm-cm (1.0) )
-! 3
., ce REFERENCE I f/;
r UFTR SOP-E.3, 7.3 ANSWER I.14 (1.00) I
-a. 1 KW 1
- b. No (0.5 each) i REFERENCE UFTR: SOP-E.2, 7.2 i i
+
ANSWER I.15 (1.50) ! 75 MREM /wk whole body 500 MREM /wk extremities 400 MREM /wk skin (0.5 each) i REFERENCE UFTR SOP-D.1, 4.4 1 ONSWER I.16 (1.25) ,
"RADIATION AREA" - Any area accessible to personnel (0.25) in which there exists radiation at such levels that a' major portion of the :
body could receive in any one hour a dose in oxcess of 5 MREM (0.25) or in any 5 consecutive days.a dose in excess of 100 MREM , 4 (0.25). l j ,
) "HIGH RADIATION AREA" - Any area acessible to personnel (0.25) in t which there exists radiation at such levels that a major portion i of the body could receive in any one hour a dose in excess of 100 MREM (0.25).
i , AEFERENCE j i UFTR SOP-D.1, 3.2.3 and 3.2.4 i, s i.-_._____ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _
' J. ~ SPECIFIC OPERATING ~ chi.RACTERISTICS PAGE .84 i
- ' ANSWERS -- UNIVERSITY OF FLORIDA -88/06/08-ARILDSEN, J.
14 ANSWER J.01 (2.00) ,
-6.-FALSE
- b. TRUE
- c. TRUE
- d. FALSE
. REFERENCE UFTR: FSAR CH 7 ANSWER J.02 (1.00)
Foils are installed in the slots for irradiatien (0.5) and are used for flux mapping (0.5). REFERENCE UFTR FSAR CH 4.1.4 ANSWER J.03 (2.00)
- a. Allows an air return path to the top of the fuel boxes (0.5) to allow rapid dumping of the water from the boxes (0.5).
- 6. Located at the base of the stacks before dilution occurs (0.5),
~
- c. Prevents the discharge of undiluted air effluent (0.5).
REFERENCE UFTR: CH 9.4.2 ANSWER J.04 (1.00) l
. Functions as both a Moderator (.5) and a Reflector (.S).
REFERENCE UFTR: Emergency Plan Ch. 1.3
J. SPECIFIC OPERATING ~ CHARACTERISTICS, PAGE 85 ANSWERS -- UNIVERSITY OF FLORIDA -88/06/08-ARILDSEN, J. ANSWER J.05 (2.50)
- 1) fast pericd <n 3 sec (.23) ch #1 (.25)
- 2) high power >= 12S X ( 2S) ;h (.2S)
- 3) reduction of HV to neutron chambers of >= 13 % (.25) both (.25)
- 4) turning off the console magnet pcwer switch (.25) none (.25)
S) AC power failure (.25) none (.25) REFERENCE UFTR: FSAR CH 7 ANSWER J.06 (1.00) The Purification Pump shuts off when the Primary Coolant Pump is running. (1.0) - o u - Tk %- g Co.A4 9 n ot ht t An . h Au g o <d.u t
~
a dowck.O c) q wdl REFERENCE UFTR: FSAR 9.2.4 ANSWER J.07 (2.S0)
- 1. source counts < 2 cps
- 2. reactor period (d 10 seconds
- 3. attempt to raise any two or more Blades simultaneously.
- 4. Safety Channels i and 2 and Wide Range Drawer Calibrate (or Safety i Trip Test) switches not in OPERATE.
S. Power is raised in AUTO control at a period faster than 30 sec. 1 l (0.5 each) REFERENCE I UFTR: FSAR CH 7 l
+,' . J. SPECIFIC OPERATING CHARACTERISTICS PAGE 86 ANSWERS -- UNIVERSITY OF FLORIDA -88/06/08-ARILD5EN, J. ANSWER J.08 (1.50) (l90)
- 1) 2 Area Radiation Monitors Alarm in coincidence (at '>= 25 mr/hr)( .2SF (o.5)
^
.utc~-tic (.25)
- 2) Air Particulate Monitor with valid alarm condition -( .2L) (o.5)
"' ual (.25)
- 3) Reactor operator detects a potentially hazardous radiological condition (and preventive actions are required to protect personnel).-(.25) (o . 9 )
v, ,~1 e 7"y REFERENCF UFTR: TECH SPEC 3.6.1 ANSWER J.09 (1.50) Tap water is passed through 2 demineralizers in series (0.5) that are filled with nuclear grade resin (amberlite) (0.5). As the water perses through, it undergoes mechanical filtration (.25) and ionic impArities are exchanged with H+ and OH- Resin ions (through the process of adsorption) (.25). ANSWER J.10 (2.23)
- a. An in line (wall mounted) resistivity bridge (0.5) receives +wo
~+ signals f rom ar conductivity cells (0.S) located upstream e4 and dcunsd'ewm of the demineralizer in the Purification System (.25).
- u. The Primary Coolant Pump gerneates sufficient driving head to Maintain a flow through the Purification Loop when it is in operation (1.0).
REFERENCE UFTR: FSAR S.i.4 , 9,2,4 ANSWER J.ii (1.S0) The loss of Offsite Power drops out the Scram Relays (.25) and deenergizes the Magnetic Clutches (.2S) to Trip the Reactor by dropping the Control Rods under gravity contpletely into the core (.5). It is Fail Safe since a loss of power will result in a Reactor Trip (.S).
J. SPECIFIC OPERATING CHARACTERISTICS .PAGE ~87 ANSWERS -- UNIVERSITY OF FLORIDA -88/06/08-ARILDSEN,.J. REFERENCE
'UFTR: FSAR CH 8'.2
+
ANSWER J.12 (1.00). 24VDC power supply (0.S)-backed up with a-floating battery pack (0.5). REFERENCE UFTR FSAR CH 9.4 + 3 4 9
- h a
'l C ,
l 1 u i 1 i k
-~. m , ~ . - ~ , . - - - , . . - , , -st.n..- -- 4~_. , #7.., , , . --
- b. .,
K. ' FUEL HANDLING AND CORE PARAMETERS. PAGE 88 ANSWERS -- UNIVERSITY OF FLOR'IDA- -88/06/08-ARILDSEN, J.
. ANSWER. K.'01 (2.00)
- a. TRUE
- b. FALS-c.,TRUE
- a. CALSd (0.5 each)
REFERENCE UFTR: SOP-C.4, 4.16.1, 4.12, and 7.3.5.2 SOP-C.2, 4.3 ANSWER k.02 ( .50) TRUE (0.5) REFERENCE UFTR SOP -C.1, 3.1.1 ANSWER 'K.03 (3.00)
- a. 93.0 (accept + or - 1.0) l
- b. 21 3
6 1
- c. 11 )
- d. 1.0 (accept + or - 0.5) (0.5 each)
REFERENCE UFTR: FSAR 4.2 ! P l 4 ANSWER K.04 (1.00) Any time that authorized personnel are in the Reactor Cell'. (1.0)- REFERENCE UFTR SOP-B.1, 7.1.1 l 4
's i , , . - . . , - . - - . . - - , .. . . . . , . ,e :....x-~/-,
.- . . . _ _ = . .
K. ~ FUEL HANDLING AND CORE' PARAMETERS PAGE 89 ANSWERS -- UNIVERSITY OF FLORIDA -98/06/08-ARILDSEN,.J.; ANSWER K.05 (1.00) s Keff.< 0.0 (1.0) REFERENCE
.UFTR : Tech. Spec. 3.7 4
' ANSWER K.06 (1.00) 500 lbs. (1.0)
' REFERENCE UFTR: Tech. Spec. S.2 C ANSWE~, K.07 (1.00)
Decignated by the Reactor Manager Mutt hold an SRO license ' (0.5 each) REFERENCE UFTR SOP-C.1, 3.2.1 ANSWER K.08 (1.00)
- Fuel Bundle aluminum wedging pins (0.5) are inserted ~into the center- '
of the fuel boxes (0.S)c REFERENCE
.UFTR SOP-C.2, 7.4.1.2
= ANSWER K.09 (2.00) H Supervisor-in-Charge Radiation Control Person '
. Equipment Operator ! Control Room Operator (licensed RO) (0.S each) l i s REFERENCE UFTR SOP-C.1, 4.7 l
-1 l
'j s.
a; .
...4 _ ,, - 4 ,, __ , - . . . - - , ' ' v, ,t.. .-- - , - -
K. FUEL HANDLING AND CORE PARAMETERS PAGE 90 ANSWERS -- UNIVERSITY OF FLORIDA -88/06/08-ARILDSEN, J. ANSWER K.10 (1.50) A ' radiation detector (0.S) is used to check that the fuel does not rise as the tool is removed (0.5) ( 1, o ). REFERENCE UFTR: SOP-C.1, 7.6.10 ANSWER K 11 ( 2 . Or, )
- a. 3
- b. 1 (due to a common power supply) (1.0 each)
REFERENCE UFTR: SOP-C.2, 4.10 and 7.2.1.1.1 ANSWER K.12 (1.00) The jiq table may be readjusted provided that the radiation levels at 6 inches over the water surface (0,5) do not exceed 6 mR/hr (OLS). REFERENCE UFTR SOP-C.4, 7.1.1 AMSWER K.13 (1.00) Relear, can only be acceneplished by taking the weight of the assembly off tha tool by setting the assembly down onto a supporting surface. (1.0) REFERENCE UFTR: SOP-C.), 4.11.3 ANSWER K,14 (1.00) 4An appropriate long headled operator i s +44- a . a i l a b l e for the engaginc, of the HEX HEAD NUTS.' "'- ' ' E ' ' E ^ " '- U TC - - - '
.s to bc 2 .<
4 1 i '- ' :- - (1,0)
4- l q- .i
.s .
- j K. FUEL' HANDLING'AND CQR_E PARAMETERS- PAGE 91 !
s I s. ANSWE9S --- UNIVERSITY- OF FLORIDA -88/06/08-ARILDSEN,"J. .. ; 1 1 i I l
- REFERENCE- -
s-UF.TR : SOP-C.4,.7.3.7 .s . s
- t' N
s ' ( t 9 k 5 i s e
\
k,
,y.
t 4 I t
)
-g.
.'. ------_._.__.__------l-----_--__--_-__.------_.-__-.-_--'
^
.. ~ , L. ADMINISTRATIVE PROCEDURES. CONDITIONS AND LIMITATIONS PAGE 9? ANSWERS -- UNIVERSITY OF FLORIDA -88/06/08-ARIL DSEN, J. ANSWEP L.01 (1.00) b i REFERENCE UFTR: Quarterly Check of Posting Requireme,nts M6 s ANSWER L.02 (1.00) t c (1.0) REFERENCE UFTRi SOP-0.6, 3.2.3 ANSWER L.03 ( .50) FALSE (0.5) REFERENCE
.UFTR: FSAR S.6.2 ANSWER L.04 'T.99) ( 2,5o)
- 1. B
- 2. A
- 3. B
- . C p M TED S. A
- 6. D (0.S.ea;h)
OcFERENCE UFTR: SOP-0.2, 7.2.2 end 7.2.2.3 SOP-0.2, APPENDIX I Form O.2A SOP-0.3, 3.3.4.1 SOP-0.6, 7.1.2.11
^ ' - - -
77 ,(,. y_ t _.? . x Y , -\ - PAGE..,93
~
- L. ADMINISTRATIVE PROCEDURES. CONQITIONS AND LIMITATIONS ANdWEFjs - . UNIVERSITY OF t FLORIDA --88/06/08-ARILDSEN, J. , .
; 6 s
\
4
- ANSWER L.05 -(i.00) .
60-
- a. .g
- b. 30 (0.5.each)
\
4 REFERENCE , UFTR SOP-F.8 ,_7.1'AND 7 3.1 ; t N ANSWER L.06 (1.00) with the.AuxiliarV' Operating Procedures (1.0) REFERENCE-UFTR: SOP-0.5, 7.6.3.3.4.
. ANSWER L.07 (3.00)
- 1. Certified Reactor Operator (0,5) in control room (0.25)
, at all times 1(0.25)
- 2. Second Person able to carry out at the facility (0.25) perscribed written instructions unexpected absence is (including the first stages of the acceptable.provided Emergency Plan) (0,5) immediate. action is taken to obtain'a
_ replacement (0.25)
- 3. Designated Class A Reactor Operator . locatecIn to be available l (SRO) (0.5) on call-(0.25).
capable.of getting to~the reacter facility within approximately 30-minutes. (0.25) REFERENCE
- l UFTR: Tech. Spec. 6.2.3
+
b N. s s 5 s x.
- g p - , - w
- g* %
- g w- e u+y--' Wra 1* w y--'--s #'-e-T
y *.* . L. ADMINISTRATIVE PROCEDURES, CONDJTIONS AND LIMITATIONS PAGE 94 ANSWERS -- UNIVERSITY OF FLORIDA -88/06/0G-ARILDSEN, J. ANSWER L.08 'O.00) (1. F0 )
- a. Reactor Manager (Level 3 or higher) (0.5) ,
- b. Approval by Level 2 (or designated alternates) 40.07 (0.29,)
within 14 days ft;'37' ( o. 2 5 )
- c. Senior operating individual present (0,5)
REFERENCE UFTR: Tech. Spec. 6.3 ANOWER L.09 (1.00) The UFTR Staff (0.5) and Campus Police are alerted (0.5). REFERENCE Emergency Plan for the UFTR, 7.2.1 1 ANSWER L.10 (1.00) , l Emergency Director (0.5) The request is made (via the campus emergency system) through UPD , Dispatch (dialing 2-1111). (0.5) 'l REFERENCE Emergency Plan for the UFTR, 7.3.1 ) l ANSWER L.11 (2.00f
- 1) Shutdown the Reactor
- 2) Notify the SRO on call
- 3) Determine the cause [Eme rgem 3 pla- .e dic,s s u < < cpf e) )
(0.5 each and 0.5 fe,P M *1 being listed W O'rd ) REFERENCE UFTR: SOP - A.3 , 4.6.3
Y
~
L. ADMINISTRATIVE PROCEDUREF. CONDITIONS AND If1MITATIONS PAGE 95 ANSWERS -- UNIVERSITY OF FLORIDA -88/06/08-ARILDEEN, J. ANSWER L.12 (1.S0) i,
- 1) Determine the cause
- 2) implement appropriate corrective action.
- 3) Notify the SRO on call.
(0.5 each) 4 REFERENCE UFTR: SOP - A.3 , 4.5.2 1 i ANSWER L.13 (1.00) 3 HRS (1.0) REFERENCE UFTR: SOP E.8 4.7.1 ANSWER L.14 (1.00)
- e. 24 hrs,
- b. YES (0.5 each)
REFERENCE UFTR S0P F.8 7.6.2 ANSWER L.15 (1.00) Co - 60 standard (with two primary gamma energies) (1.0) s REFERENCE UFTR: FORM SOP - E.6A
'. l .
... e s TEST CROSS REFERENCE PAGE 1 GUESTION VALUE REFERENCE ________ ______ __________ l H.01 1.00 GTH0000846 H.02 1.50 GTH0000847 H.03 1.50 GTH0000848 H.04 ~1.00 GTH0000849 H.05 2.00 GTHOOOO851 H.06 1.00 GTH0000852 I H.07 2.00 GTH00008S3 l H.08 1.00 GTH0000854 H.09 1.00 GTH0000855 H.10 1.00 GTH0000856 H.11 1.00 GTH0000857 H.12 1.00 GTH0000859 H.13 1.00 GTH0000860 H.14 1.00 GTH0000861 H.15 1.00 GTH0000864 H.16 2.50 GTH0000863 20.50 I.01 1.00 GTH0000814 I.02 .50 GTH0000816 I.03 .50 GTH0000824 I.04 1.00 GTH0000815 I.05 1.00 GTH0000817 I.06 2.50 GTH0000818 I.07 2.00 GTH0000819 I.08 1.00 GTH0000820 I.09 2.00 GTH0000821 I.10 1.00 GTH0000822 I.11 1.00 GTH0000823 1.12 1.50 GTH0000825 I.13 1.00 GTH0000826 1.14 1.00 GTH0000827 - I.15 1.50 GTH0000828 I.16 1.25 GTH0000829 19.75 J.01 2.00 GTH0000804 J.02 1.00 GTH0000788 J.03 2.00 GTH0000789 ; J.04 1.00 GTH0000792 J.05 2.50 GTH0000802 J.06 1.00 GTH0000805 J.07 2.50 GTH0002807 J.06 1.50 GTH0000010 J.09 1.50 GTH0000787 J.10 2.25 GTH0000806 J.11 '1.50 GTH0000809 J.12 1.00 GTH0000812 l 1 i
ger s- n TEST CROSS REFERENCE < PAGE 2 QUESTION VALUE REFERENCE 19.75 K.01 2.00 GTH0000833 K.02 .50 GTH0000838 K.03 3.00 GTH0000843 K.04 1.00 GTH0000830 K.05 1.00 GTH0000831 K.06 1.00 GTH0000832 K.07 1.00 GTH0000834 K.08 1.00 GTH0000836 K.09 2.00 GTH0000839 K.10 1.50 GTHOOOO840 K.11 2.00 GTH0000841 K.12 1.00 GTH0000843-K.13 1.00 GTH0000835 K.14 1.00 GTH0000842 19.00 L.01 1.00 GTH0000866 L.02 1.00 GTH0000867 L.03 .50 GTH000087S L.04 3.00 GTH0000870 L.05 1.00 GTH0000878 L.06 1.00 GTH000086S L.07 3.00 GTH0000868 L.08 2.00 GTH0000869 L.09 1.00 GTH0000871 L.10 1.00 GTH0000872 L.11 2.00 GTH0000873 L.12 1.50 GTH0000874 L.13 1.00 GTH0000877 I L.14 1.00 GTH0000879 l L.15 1.00 GTH0000876 l 21.00 100.00 DOCKET NO 83 1
MASTGR SRo t SR0 / R0 UNIVERSITY OF FLORIDA TEST REACTOR LICENSE EXAMINATION 88/06/08 HAND 0UTS EQUATION SHEET ------ 1 PAGE STEAM TABLES -------- 7 PAGES FIGURE #219 FIGURE 4-26 FIGURE 4-27 FIGURE 4-28 FIGURE 4-29 l 1
'I
- f a ma v o s/t i Cycle efficiency o (Net work
,- ,3 cut)/(Energy in) 2
, = mg 9
5 = V,t + 1/2'at
, E = me- -
" 2 (E = 1/2 mv ,, , (yf . .fo )ft 4 , 23 ; ,3 ,-it 9
PE = mgn vf = V, + a t *
- e/t x = zn2/t1/2 = 0.693/t 1/2 y , , .p A= nD 2 1/2'N
- M /9 )
4 [(t 1/2 I
- Itb))
- .E = 931 am -
m = V,yAo -Ix Q .= fah I*Iec Qe mCpat Q = UAc T I = I,e p.,r = w ah f I = I,10-x/ m TVL = 1.3/u P = P 10 sur(t) O HVL = -0.693/u , t l P = P ,e / SUR = 26.06/T SCR = S/(1 - K,ff) CR x = S/(1 - K,ffx) l SUR = 26o/t* + (8 - p)T j (1 - Keffl) = CR2 (I ~ keff2) CR T = ( t*/o ) + [( A - o V Io ] M = 1/(1 - K,ff) = CR)/CR , T = t/(o - 8) M = (1 - K ,ff,)/(1 - Keff1) T = (8 - o)/(Io) SDM = ( - K'eff)/Keff o = (X,ff-1)/K,ff = M ,ff/K eff t' = 10 seconos I = 0.1 seconds ~I ) o = [(t*/(T K,ff)3 + [8 eff /(1 + IT)] l I d) =Id j l P = (tov)/(3 x 1010) I)d) 2 ,2gd 22 2 I = eN R/hr = (0.5 CE)/d (meters) 2 R/hr = 5 CE/d2 (f,,g) , Water Parameters Miscellaneous Conversions 1 gal. = 8.345 lbm. 1 curie = 3.7 x 1010 aps 1 ga1 . = 3.78 liters 1 kg = 2.21 lom 1 fts = 7.48 gal. Ihp=2.54x10]8tu/nr Density = 62.4 lbw/ft3 1 m = 3.41 x 100 5tu/hr Density = 1 gm/cm3 lin = 2.54 cm Heat of vaporization = 970 Stu/lom 'F = 9/5'C + 32 Heat of fusion = 144 Btu /lbm ,
'C = 5/9 (*F 32) 1 Atm = 14.7 psi = 29.9 in. Hg. 1 BTU = 778 ft-lbf 1 ft. H 2O = 0.4335 lbf/in.
e = 2.718 sng - - un -
V11ume, it'/lb Enthalpy, Stu/lb Entropy, Blu/lb a F 7 Water Evap Steam Water Evap Steam Water [ var Steam 'rmP VI 'Is V s hg h,e h, so s, o s, j 3305 3305 -0.02 1075.5 1075.5 0.0000 2.!873 2.1873 32 32 0.08859 0.01602 2948 2948 3.00 1073.8 1076.8 0.0061 2.1706 2.1767 35 35 0.09991 0.01602 2446 8 03 1071.0 1079.0 0.0162 2.1432 2.1594 40 40 0.12163 0 0160? 2446 I 2037.8 13.04 1068.1 1081.2 0 0262 2.1164 2.1426 45 45 0.14744 0.01602 2037.7 ' 1704.8 1704.8 18.05 1065.3 1083.4 0.0361 2.0901 2.1262 50 50 0.17795 0.01602 1207.6 28.06 1059.7 1087.7 0.0 M 5 2.0391 2.0946 60 60 0.2561 0.01603 1207.6 868.3 868.4 38.05 1054.0 1092.1 0.0745 1.9900 2.0645 70 70 0.3629 0.01605 633.3 633.3 40.04 1048.4 1096.4 0.0932 1.9426 2.0359 80 to 0.5068 0.01607 468.1 468.1 58.02 1042.7 1100.8 0.1115 1.8970 2.0086 50 90 0.6981 0.01610 350.4 350.4 68 00 1037.1 1105.1 0.1295 1.8530 1.9825 100 100 0.9492 0.01613 265.4 265.4 77.98 1031.4 1109.3 0.1472 1.8405 1.9577 110 110 1.2750 0.01617 203.25 203.26 87.97 1025.6 1113.6 0.1646 1.7693 1.9339 120 220 1.6927 0.01620 157.32 157.33 97.96 1019.8 1117.8 0.1817 1.7295 1.9112 130 130 2.2230 0.01625 122.98 123.00 107.95 1014.0 1122.0 0.1985 1.6910 1.8895 140 140 2.8892 0.01629 97.05 97.07 117.95 1008.2 1126.1 0.2150 1.6536 1.8686 150 150 3.718 0.01634 77.29 127.96 1002.2 1130.2 0.2313 1.6174 1.8487 160 160 4.741 0.01640 77.27 0.01h>45 62.04 62.06 137.97 996.2 1134.2 0.2473 1.5822 1.8295 170 170 5.993 I 50.21 50.22 148.00 930.2 1138.2 0.2631 1.5480 1.8111 180 180 7.511 0.01651 40.94 40.96 158.04 984.1 1142.1 0.2787 1.5148 1.7934 100 I 130 9.340 0.01657 33.62 33.64 168.09 977.9 1146.0 0.2940 1.4824 1.7.764 200 l 200 11.526 0.01664 0.01671 27.80 27.82 178.15 971.6 1149.7 0.3091 1.4509 1.7600 210 210 14.123 0.01672 26.78 26.80 180.17 970.3 1150.5 0.3121 1.4447 1.7568 212 212 14.696 0.01678 23.13 23.15 188.23 965.2 1153.4 0.3241 1.4201 1.7442 220 220 17.186 0.01685 19.3M 19.381 198.33 958.7 1157.1 0.3388 1.3902 1.7290 230 230 20.779 0.01693 16.304 16.321 208.45 952.1 1160.6 0.3533 1.3609 1.7142 240 240 24.963 0.01701 13.802 13.819 218.59 945.4 1164.0 0.3677 1.3323 1.7000 250 250 29.825 0.01709 11.745 11.762 228.76 938.6 1167.4 0.3819 1.3043 1.6862 260 l 260 35.427 41.856 0.01718 10.042 10.060 238.95 931.7 1170.6 0.3960 1.2769 1.6729 270 270 49.200 0.01726 8.627 8.644 249.17 924.6 1173.8 0.4098 1.2501 1.6599 280 280 l 57.550 0.01736 7.443 7.460 259.4 917.4 1176.8 0.4236 1.2238 1.6473 290 290 300 67.005 0.01745 6.448 6.466 269.7 910.0 1179.7 0.4372 1.1979 1.6351 300 77.67 0.01755 5 609 5.626 280.0 902.5 1182.5 0.4506 1.1726 1.6232 310 310 ) 0.4640 1.1477 1.6116 320 320 89.64 0.01766 4.896 4.914 290.4 894.8 1185.2 117.99 0.01787 3.770 3.788 311.3 878.8 1190.1 0.4902 1.0990 1.5892 340 340 153.01 0.01811 2.939 2.9 57 332.3 862.1 1194.4 0.5161 1.0517 1.5678 360 360 380 195.73 0.01836 '2.317 2.335 353.6 844.5 1198.0 0.5416 1.0057 1.5473 380 400 247.26 0.01864 1.8444 1.8630 375.1 825.9 1201.0 0.5667 0.9607 1.5274 400 0.01894 1.4808 1.4997 396.9 806.2 1203.1 0.5915 0.9165 1.5080 420 420 30S.78 440 381.54 0.01926 1.1976 1.2169 419.0 785.4 1204.4 0.6161 0.872'.) 1.4890 440 460 466.9 0.0196 0.9746 0.9942 441.5 763.2 1204.8 0.6405 0.8299 1.4704 460 0.0200 0.7972 0.8172 464.5 739.6 1204.1 0.6648 0.7871 1.4515 480 450 566.2 l 680.9 0.0204 0.6545 0.6749 487.9 714.3 1202.2 0.689C 0.7443 1.4333 500 500 812.5 0.0209 0.5386 0.5596 512.0 687.0 1199.0 0.7133 0.7013 1.4146 520 f 520 962.8 0.02:5 0.4437 0.4651 536.8 657.5 1194.3 0.7378 0.6577 1.3954 540 l 540 1133.4 0.0221 0.3651 0.3871 562.4 625.3 1187.7 0.7625 0.6132 1.3757 560 I' SCO 0.0228 0.2994 0.3222 589.1 589.9 1179.0 0.7876 0.5673 1.3550 580
$50 1326.2 600 1543.2 0.0236 0.2438 0.2675 617.1 550 6 1167.7 0.8134 0.5196 1.3330 Goo 0.0247 0.1962 0.2208 646.9 506.3 1153.2 0.8403 0.46S9 1.3092 620 620 1786.9 2059 9 0.0260 0.1543 0.1802 679.1 454.6 1133.7 0.8656 0.4134 1.2821 640 640 2365.7 00277 0.1166 0.1443 714.9 392.1 1107.0 0.8995 0.3502 1.2493 660 E60 0 0304 0.0808 0.1112 758 5 310.1 1068.5 0.9365 0.2720 1.20S6 680 6d 2708.6 l
.v)94.3 0.0366 0.0386 0.0752 822.4' 172.7 995.2 0.9001 0.1490 1.1390 700 700 705.5 9203 2 0.0508 0 0.0508 906.0 0 906.0 1.0612 0 1.0612 705.5 1_
TABLE A.2 PROPERTIES OF SATURATED STEAM AND SATURATED WATER (TEMPERATURE) A3
. Volume, fil /lb [nthalpy. Blu/lb Enterpy. Brubb a F Energy. Blu/1b Press. Temp Water Evep Steam Water Evap Steam Watet Steam ,
water Evap Steam g
's h, h, p by sg s,o :c, seg u,
't
'te _
32.018 0.01602 3302.4 3302.4 0.00 1075.5 1075 5 0 2.1872 2.1872 0 1021.3 0.0886 l 0.0d86 0.10 35.023 0.01602 2945.5 2945.5 3 03 1073 8 1076.8 0 006) 2.1705 2.1766 323 1022.3 0.10 0.15 45.453 0 01602 2004.7 2004 7 13.50 1067.9 1081.4 0 0271 2.1140 2.1411 13.50 1025.7 0.15 I 0.20 53.160 0 01603 1526 3 1526 3 21.22 1063 5 1084 7 0.0422 2 07?B 2.1160 1122 1028.3 0.20 1 0.30 64 464 0 01604 1039 7 1039.7 32.54 1057.1 1089.7 0 0641 2.0169 2.0809 0?.54 1032 0 0.30 1 0.4 D 72.809 0.01606 792.0 792.1 40.92 1052.4 1093.3 0.0799 1.9762 2.0562 4092 1034.7 0.40 l 0.5 79.586 0.01607 641.5 641.5 47.62 1048 6 1096.3 0.0925 1.9446 2.0370 47.62 1036.9 0.5 0.6 85.218 0 01609 540.0 540.1 53.25 1045.5 1098.7 0.1028 1.9186 2.0215 5324 1038.7 0.6 0.7 90 09 0.01610 466.93 46694 58 10 1042 7 1100 8 0.3 1.8966 2.0033 58.10 1040.3 0.7 0.8 94.38 0.01611 411.67 411.69 62.39 1040.3 1102.6 0.1117 1.8775 1.9970 6239 1041.7 0.8 0.9 93.24 0.01612 368.41 368.43 66.24 1038.1 1104.3 0.1264 1.8606 1.9870 6624 1042.9 0.9 I 1.0 101.74 0.01614 333.59 333.60 69.73 1036.1 1105& 0.1326 1.8455 1.9781 69.73 1044.1 3.0 2.0 126.07 0.01623 173.74 173.76 94.03 1022.1 1116.2 0.1750 1.7450 1.9200 94.03 1051.8 2.0 3.0 141 47 0.01630 118 71 118.73 109.42 1013.2 1122 6 0.2009 1.6854 1.8864 109 41 1056.7 3.0 4.0 152.96 0.01636 90 63 90.64 120.92 1006.4 1127.3 0.2199 1.6428 1.8626 120.93 1060.2 4.0 5.0 162.24 0.01641 73.515 73.53 130 20 1000.9 1131.1 0.2349 1.6094 1.8443 130.18 1063.1 5.0 f 6.0 170 05 0.01645 61.967 61.98 138.03 996.2 1134.2 02474 1.5820 1.8294 138.01 1065.4' 6.0 7.0 176 84 0.01649 53 634 53.65 144.83 992.1 1136 9 0.2581 1.5587 1.8168 144.81 1067.4 7.0 8.0 182.86 0.01653 47.328 47.35 150 87 938.5 1139.3 0 2676 1.5384 1.8050 15034 1069.2 8.0 1 9.0 18927 0 01656 42.385 42.40 156.30 985.1 1141.4 0.2760 1.5204 1.7964 15628 1070.8 *t.G 10 193.21 0.01659 38.404 38 42 161.26 982.1 1143.3 0.2836 1.5043 1.7879 16123 1072.3 10 14.696 212.00 0.01672 26.782 26 80 180.17 970.3 1150.5 0.3121 1.4447 1.756S 180.12 1077.6 14.696 15 213.03 0.01673 26.274 26.29 181.21 969.7 1150.9 0.3137 1.4415 1.7552 181.16 1077.9 15 20 227.96 0.01683 20.070 20 087 196 27 960.1 1156.3 0.3358 1.3962 1.7320 19621 1082.0 29 30 250.34 0.01701 13.7266 13 744 218.9 945.2 1164.1 0.36B2 1.3313 1.6995 218S 1087.9 30 40 267.25 0.01715 104794 10.497 236.1 933.6 1169.8 0.3921 1.2844 1.6765 236 0 1092.1 40 50 261.02 0.01727 8.4967 8.514 250,2 923.9 1174.1 0 4112 1.2474 1.6585 250.1 1095.3 50 60 292.71 0.01738 7.1562 7.174 262.2 915.4 1177.6 0.4273 1.2167 1.6440 262.0 1093.0 60 70 302.93 0.01748 6.1875 6 205 272.7 907.8 1180.6 0 4411 1.1905 1.6316 272.5 1100.2 70 80 312.04 0.01757 5 4536 5 471 232.1 900.9 1183.1 0.4534 1.1675 1.6208 281.9 1102.1 to 90 320.28 0.01766 4.8777 4.895 290.7 894.6 1185.3 0.4643 1.1470 1.6113 293.4 1103.7 90 100 327.82 0.01774 4.4133 4.431 298.5 888.6 1187.2 0.4743 1.1284 1.6027 2982 1105.2 100 120 341.27 0.01789 3.7097 3.728 312.6 877.8 1193 4 0.4919 1.0960 1.5879 312.2 1107.6 120 140 353 04 001803 3.2010 3 219 325.0 E68.0 1193.0 0.5071 1.0681 1.575 324.5 1109.6 140 160 363 55 0.0;B15 2.8155 2.834 336.1 859.0 1195.1 0.5206 1.0435 1.5641 335.5 1111.2 160 180 373 08 0.01827 2.5129 2.531 346.2 850.7 1196.9 0 5328 1.0?l5 1.5543 345.6 1112.5 180 200 351.80 0 01829 2.2639 2.287 355.5 842.8 1198.3 0 5438 1.0016 1.5454 3543 1113.7 200 250 40097 0 01865 1.8245 1.8432 376.1 825 0 1201.1 0.5679 0 9585 1.5264 375.3 1115.8 250 300 417 3b 0 01859 1.523B 1.5427 394 0 808.9 1202.9 0.5SS? 0.9223 1.5105 392.9 1117.2 300 350 4 1.73 0.01913 1.3064 1.3255 4098 7942 1204 0 0 60 % 08909 1.4958 4096 1118 1 350 400 4:4 60 0.0193 1.14162 1.1610 424.2 780 4 1204.6 0 6217 0 8630 1.4847 422.7 111E 7 400 450 AM 28 0 0195 1.01224 .l.0318 437.3 767.5 1204.8 0.6360 0.8378 1.4738 435.7 1118.9 450 500 467 01 00199 0 90787 0 9276 449.5 755.1 1204.7 06490 0.814S 1.4639 447.7 1118 8 500 550 47694 00199 0 82183 0.8418 460.9 743 3 1204 3 0.6611 0 7936 1.4547 456.9 1118 6 550 (00 48520 0 0201 0 74962 0.7698 471.7 732.0 1203.7 0.6723 0 7738 1.4461 469.5 1116.2 600 700 ,503 08 0 0205 0.63505 06556 491.6 710.2 1201.8 069?R 07377 1.4304 ASS.9 1116.9 700 800 513 21 0 0209 0.54809 0.5690 509.8 689 6 1199 4 0.7111 0.7051 1.4163 506 7 1115.2 800 900 Ei! 95 0 0212 0 47968 05009 526 7 659 7 1196 4 0 7279 0 6753 1.4032 5232 1113.0 900 1000 5 ' 4.5S O0216 042436 0 4460 542.6 (50 4 1192.9 0.7434 06476 1.3910 53'16 1110.4 1000 l 1100 til 2v 0.0??O O378f.3 04006 557.5 631.5 1IS91 0 757S 06216 1.3794 553 1 1107.5 1100 l 1200 ' :67.19 0 0223 0 34013 0.362b 571.9 6130 1184 8 07714 0.5969 1.3633 5559 1104 3 1200 J 1300 17742 0 0227 0 30722 0.3279 585 6 544.6 1180 2 0.7843 0 5733 1.3577 550.1 11009 1300 1400 537 07 0 0231 0 278/1 0 3018 59BB 576 5 1175 3 0.7966 05507 1.3474 592.9 1097.1 1400 1500 59620 0 0235 02b372 0 2712 611.7 558 4 11701 0.8015 0!?53 1.3373 605 2 1093.1 1500 2000 635 80 0.01S 7 016?66 0.1833 6721 4662 1133.3 086M 04256 1.?tiB 1 662 6 10*,8 6 2000 2500 ESS 11 0 02M 010209 01307 731.7 361.6 1093 3 0 9139 03206 1.2345 118.5 1032.9 2500 3000 695 33 0030 0 050/3 00S50 801 8 218 4 1020 3 0 9728 01891 1.1619 782 3 973.1 3000 320B2 70147 00W3 0 0 050d 906 0 0 906 0 1.0612 0 1.0612 875.9 875.9 37082 TABLE A.3 PROPERTIES OF SATURATED STEAM AND SATURATED WATER (PRESSURE) u !
hbs press. Tempetature, F f4 /sq in. 200 300 400 600 UJO 700 800 900 1000 11CO 1200 1300 1400 1500 (sat. temp) 100 v 0.0161 3925 452.3 511.9 571.5 631.1 690 7 3 A 68 00 11502 1195.7 1241.8 1288 6 13361 1384 5 (101.74) s 0.1295 2.0>09 2.1152 2.1722 2.2237 2.2706 2.3144 e 0.0161 7814 90.24 102.24 134.?! 126 15 138 08 150 01 161.94 173 86 185 78 197.70 209 62 221.53 233 45 5 A 68 01 1143 6 1194 8 1241.3 1286 2 1335.9 1384 3 1433 6 1483 7 1534.7 1585 7 1639 6 1693 3 1748 0 1803.5 (162 24) s 0.1795 1.8716 1.9369 1.9943 2.0460 2.0932 2.1309 2.1776 2 2159 2 252) 2.2866 2.3194 2.3509 2 3811 2.4101 v 00161 3B 84 44 93 5103 57.04 63 03 69 00 74 98 8094 8691 9287 98.84 104 80 110.76 116 72 10 h 68 02 1146 6 1193 7 1240 6 1787.8 1335.5 1384 0 1433 4 1483 5 1534 6 1586 6 16395 1693.3 1747.9 1803 4 (192.21) s 0.1295 1.7928 1.8593 1.9173 1.9692 2.0166 2.0603 2.1011 2.1394 2.1757 2.2101 2.2430 2.2744 2.3046 2.3337 y 0 0161 0.0166 29.899 33.963 37.985 41.966 e5.978 49 964 53 946 57.926 61.905 65.882 69,858 73.833 77.807 15 6 68.04 168 09 1192.5 1239 9 1287.3 1335 2 1383 8 1433 2 1483 4 1534.5 1586 5 1639 4 16932 1747.8 1803 4 (213.03) s 0.1295 0.2940 1.8134 3.8720 1.9242 1.9717 .1.9155 2.0563 2.0946 2.1309 2.1653 2.1982 2.2297 2.2599 2.2890 l v 0.0161 0 0166 22.356 25428 28.457 31.466 34 465 37.458 40 447 43 435 46420 49.405 52.388 55370 58.352 1 20 4 68.05 168 11 1191.4 1239.2 1286.9 1334.9 1383 5 1432 9 1483 2 1534.3 1586.3 1639.3 1693.1 17472 18033 (227.96) s 0.1295 0.2940 1.7805 1.8397 1.8921 1.9397 1.9836 2.0244 2 0628 2.0991 2.1336 2.1665 2.1979 2.2282 2.2572 v 0.0161 0 0166 11 035 12.624 14.165 15 685 17.195 18.699 20 19) 21.697 23.194 24 689 26.183 27J576 29.168 40 6 68.10 168 15 1186 6 1236.4 1285.0 1333 6 1382.5 1432.1 1482.5 1533.7 1585.8 1638 8 1992,7 1747.5 1803.0 1 (267.25) s 0.1295 0 2940 1.6992 1.7608 1.8143 1.8624 1.9065 1.9476 1.9860 P.0224 2.0569 2.0899 2.1224 2.1516 2.1807 1 I e 0.0161 0 0156 7.257 8354 9 400 10 425 1143B 12.446 13.450 14.452 15.452 16.450 17A48 18.445 19.441 i 60 A 68.15 16920 1181 6 1233.5 1283 2 1332.3 1381.5 1431.3 1481.8 1533 2 1595.3 1638.4 1692.4 1747.1 1802.8 (292.71) s 0.1295 0.2939 1.6492 1.7134 1.7681 1.9168 1.8612 1.9024 1.9410 1.9774 2.0120 2.0450 2.0765 2.1068 2.1359 l 9 0.01'61 0 0166 0.0175 6.218 7.018 7.794 8.560 9 319 10.075 10.829 11 581 12.331 13.081 13.829 14.577 80 A 68 21 168.24 269.74 1230.5 1281.3 1330.9 1380.5 1430.5 1481.1 1532 6 1584.9 1638 0 1692.0 1746S 1802.5 (312.04) s 0.1295 02939 0.4371 1.6790 1.7349 1.7842 1.8289 1.8702 1.9089 1.9454 1.9800 2.0131 2.0446 2.0750 2.1041 v 0.0161 0.0166 0 0175 4 935 5.588 6.216 6.833 7.443 8 050 8655 9.258 9.860 10.460 11.060 11.659 100 A 68.26 168 29 269 77 1227.4 1279.3 1329.6 1379.5 1429.7 1480.4 1532.0 1584 4 1637.6 1691.6 1746.5 1802.2 (327.82) : 0.1295 0.2939 0.4371 1.6516 1.7088 1.7586 1.8036 1.8451 1.8839 1.9205 1.9552 1.9883 2 4199 2.0502 2.0794 f v 0 0161 0 0166 0 0175 4 0786 4.6341 5.1637 5 6831 6 1923 6 7006 7.2060 7.7090 8.2119 8.7130 9.2134 9.7130 ! 120 A 68.31 168 33 269 81 1224.1 1277.4 1328.1 1378 4 1423 8 1479.8 1531.4 1583.9 1637.1 1691.3 1746.2 1802.0 (341.27) s 0.1295 02939 0 4371 1.6286 1.6872 1.7376 1.7829 12246 12635 1.9001 1.9349 1.9680 1.9996 2.0300 2.0592
, 0 0161 0 0166 0 0175 3 4651 3,9526 4 4119 4.8535 5.2995 5.7364 6.1709 6.6036 7.0349 7.4652 7.8946 8 3233 !
140 6 68 37 168 38 269 85 1220 8 1275 3 1326 8 1377.4 1428.0 1479.1 1530 8 1583 4 1636.7 1690.9 1745.9 1801.7 (353 04) s 0.1295 0 2939 0 4370 1.6085 1.6686 1.7196 1.7652 1.8071 1E461 1A828 1.9176 ISSOS 1.9825 2.0129 2.0421 l
, 0.0161 0 0165 0 0175 3 0060 3 4413 3.8480 4 2420 4 6295 5.0132 5 3945 5.7741 6 1522 6.5293 '6 9055 7.2811 160 A 68 42 168 42 269.89 1217.4 12733 1325 4 1376 4 1427.2 1478 4 1530.3 1582.9 1636.1 1690.5 1745.6 1801.4 1
l (363 55) s 0 1204 0 2935 0 4370 1.5906 1.65':2 1.7039 1.7499 1.7919 1.8310 1.8678 1.9027 1.9359 1.9676 1.9980 2.0273 l j v 0 0161 0 0166 0 0174 2 6474 3 0433 3 4093 3.7621 4.1084 4.4505 4.7907 5.1289 5 4657 53014 6.1363 6.4704 . 180 A 68 47 16847 269 9/ 1213 8 1271 2 1324 0 1375 3 1426.3 1477.7 1529.7 1582.4 1635.9 16W2 17453 1801.2 (373.08' s C.12 94 0.2338 04370 1 5743 1.6376 1.6900 17362 1.7784 1.8176 1.8M5 1.8894 1.9227 1 9545 1.9849 2.0142 1
, 0 0161 0 0166 0 0174 2 3598 2.7247 3.0583 3 3783 3 6915 4.0008 4.3077 4.6128 4.9165 53191 5.5203 5.8219 200 A 68 52 168 51 209 96 12101 1269.0 13225 1374.3 1425.5 1477.0 1529.1 1581.9 1635.4 1689 8 1745.0 1800.9 (351.80) s 0 1294 02938 043G9 1.5593 1.6242 1.6776 1.7239 1.7663 1.8057 1.8426 1.8776 1.9109 1.9427 1.9732 2.0025 l
, 06161 0 0165 0 0174 0 0186 2.1504 2 4662 2 6872 2.9410 3.1909 3.4382 3 6837 3 9278 4.1709 4.4131 4.6546 250 6 68 66 If 8 63 270 05 3/5.10 1263.5 1319.0 1371.3 1423 4 1475.3 1527.6 1580.6 1634.4 1688.9 1744 2 1800.2 )
(400 97) : 01294 0 2937 04368 0.5567 1.5951 1.6502 1.6976 1.7405 1.7601 1.8173 1.8524 1.8858 1.9177 1.9482 1.9776 l v 0 0161 0 01(6 0 0174 0 0186 1.76 % 2.0044 2 2263 2,4407 2.6509 2 65S5 3 0643 3 2688 3 4721 3.6746 3 8764 300 > 63 79 1 % 74 ??v id 375.15 1237 7 1315 2 1368 9 1421.3 1473 6 1526.2 1579 4 1633 3 1688 0 1743 4 1799.6 I (417.35) : 0.1294 0 2937 0 4337 0 5665 1.5703 1.6274 1.6758 1.7192 1.7591 1.7964 1.8317 1.8652 1.8372 1.9278 1.9572 e 0 0161 0 0165 0 0174 0 0186 1.4913 1.7028 1 8970 2 0332 2.2652 2 4445 2.6219 2.7980 2.9730 3.1471 3.3205 350 A 68 92 169 85 270 ?? 37521 1251 b 1311.4 1366.2 14192 14716 1124 7 1578.2 1632.3 1667.1 1742 6 17969 (431.73) a 01293 0 2936 0 43G7 0.5%4 1.5483 1.6077 1.6571 1.7009 1.7411 1.7787 1.8141 1.8477 12793 1.9105 1.9400 v 0 0161 0 0166 0 0174 0 0162 12841 1.4763 1.6493 1.8151 1 9759 2.1339 2.2901 2.4450 2.5937 2.7515 2.9037 400 e 69 05 168 97 270 33 375 27 124S 1 1307.4 1363 4 1417.0 14701 1523 3 1576 9 1631.2 1636 2 1741 9 1793.2 (444.60) s $1293 0 2935 0 4365 00%3 1.5?82 1.5901 1 6406 1.6850 1.7255 1.7632 1.798S 1.8325 IS647 1.8955 1.9250 e 0 0161 0 0166 0 0174 0 0106 0 9919 1.1584 1 3037 1.4397 1.570B 1 6932 1.B?$6 1.9507 2.0746 2.1977 2.3200 500 A 69 32 1r 919 270 51 375 E 12312 12991 1357.7 1412 7 1466 6 1520 3 1574 4 16291 1634 4 1740 3 1796.9 (457.01) s 0 1292 0?934 04354 0SRO 14971 15505 16123 165/8 16090 1.7371 1.7730 1.80t.9 1A393 1.8702 1.8998 TABLE A.4 PROPERTIES OF SUPERHEATED STEAM AND COMPRESSED WATER (TEMPERATURE AND PRESSURE) A.5
Abs prest. Temperetzte, F lt/H in. (sat.lemp) 100 200 300 400 600 600 700 800 900 1000 1100 3200 1300 1400 1500 v 0.01C1 0 0166 0 0174 0 0186 0 7944 0 9456 1 0726 1.1892 1.3008 1 4093 1.5160 1 6711 3.7752 1 8284 1.9309 600 6 69.58 169 42 270 70 37549 1215 9 1290 3 1351.8 1408 3 1463 G 1517.4 15719 1627.0 16b2 6 1738 8 1795 6 (46620) s 0.1292 0.2933 0 4362 0 '.,657 14590 1.53?9 1.5844 1.6351 16769 1.?!b5 1.7517 1.7859 1.8184 1.8494 1.8792 e 0 0161 0 0166 0 0174 0 0186 0 0204 0 7928 0 9072 1.0102 1.1078 12023 12948 1.3858 1.4757 1.5647 1.6530 700 6 69.04 169 65 270 69 375 61 487 93 1281.0 1345 6 1403.7 1459 4 1514 4 15694 1624.8 16D 7 1737 2 1794.3 (503.C8) e 0 1291 0.2932 0 4360 0 5455 0 6889 1.5090 1.5673 1 6154 1.65S0 1.6970 1 7335 3.7679 1 80 % 18318 18617 e 0 0161 0 0166 0 0174 0 0186 0 0704 0 6774 0 7829 0.8759 0 9631 1.0470 1.1289 1.2093 12825 1.3653 1.4446 800 h 70.11 169 88 271.0) 375 73 487.88 127).1 1339 2 1399.1 14558 1511 4 156'a 9 16?? ? 1678 9 1735 0 1792.9 (5182.) . 0,1290 02930 0 4358 0.5652 06485 1.4869 1.5484 1.5980 1.6413 1 6607 1.7175 17522 1.7851 1 8164 1.84 64 e 0.0161 0.0166 0 0174 0 0186 0 0234 0 5869 0 6858 0.7713 0 8504 0.9262 0 9998 1.0720 1.1430 1.2131 12825 900 6 70.37 170 10 27126 375.84 2 7.83 1260 6 1332.7 1394.4 1452 2 15C8 5 1564 4 1620 6 1677.1 1734 1 1791.6 (531E) s 0 1290 0.2929 0.4357 0.5649 0.6881 1.4659 1.5311 1.5822 1.6263 1.0662 1.7033 1.7382 1.7113 1.6028 18329 e 0.0161 0 0166 0.0174 0 0186 0 0204 0 5137 0 6080 0 6875 0.7603 0 8295 02966 0 9622 1.0266 1.0901 1.1529 1000 6 70.63 17033 271.44 375.96 487.79 1249.3 1325.9 1389.6 1448.5 1504.4 lb61.9 1618 4 1675.3 1732.5 1790.3 (544.58) s 0.1269 0.2928 0.4355 05647 0.6876 1.4457 1.5149 1.5677 1.6126 1.6530 1.6905 1.7256 1.7589 1.7905 1.8207 e 0 0161 0 0166 0 0174 0.0185 0 0203 0 4531 0 5440 0 6188 0 6B65 0 7505 0 8121 0 8723 0 9313 0 9894 1.0468 1100 4 70.90 170.56 271.63 376 08 487.75 1237.3 1318 8 1384.7 1444 2 15C24 1559.4 1616 3 1673.5 1731.0 1789.0 (55628) s 0.1269 02927 0.4353 0.5644 0.6872 1.4259 1.4996 1.5542 1.6000 1.6410 1.6787 1.7141 1.7475 1.7793 1.8097 e 0 0161 0.0166 0.0174 0.0185 0 0203 0 4016 0 4905 0.5615 0 6250 0 6845 0 7418 0.7974 0 8519 0.9055 0 9584' ! 1200 6 71.16 170.78 271.82 376 20 487.72 1224.2 1311.5 1379.7 1440 9 1449 4 1556 9 1614.2 1671.6 1729 4 1787.6 I (567.19) : 0.1288 0.2926 0.4351 0.5642 0.6868 1.4061 1.4851 1.5415 1.5883 1.6293 16679 1.7035 1.7371 1.7691 1.7996 e 00161 0 0166 0 0174 0 0185 0 0203 0.3176 0.4059 04712 0$282 0 1809 0 6311 0 6798 07272 0.7737 08195 1400 6 71.68 171.24 272.19 376 44 487.65 1194.1 1296.1 1369.3 1433 2 1493 2 1$5L8 1609 9 1668 0 1726.3 1785.0 (587.07) s 0.1287 02923 0.4348 0.5636 0.6859 1.3652 1.4575 1.5182 1.5670 1.6036 1.6434 1.6845 1.7185 1.7508 1.7815 1 e 0.0161 0 0166 0 0173 0.0185 0.0202 0.0236 0.3415 0 4032 04555 0.5031 0 5482 0 5915 0.6336 0 6748 0.7153 1600 A 72.21 171.69 272.57 376 69 487.60 616.77 1279.4 1358 5 1425.2 1486.9 15466 1605 6 1664.3 1723.2 1782.3 (604.87) s 0.1286 0 2921 0.4344 0.5631 0.6851 0.8129 1.4312 1.4963 1.5478 1.5916 1 6312 1.6678 1.7022 1.7344 1.7657 e 0.0160 0.0165 0 0173 0.0185 0.0202 0.0235 0 2906 0 3500 0.3988 0 4426 0.4836 0.5229 0 5609 0.5980 0 6?43 1800 > 72.73 172.15 272.95 376.93 487.56 615.58 1261.1 1347.2 1417.1 1480 6 1541.1 1601.2 1660.7 1720.1 1779.7 (621.02) s 0.1254 02918 0.4341 0.5626 0.68'3 0.8109 1.4054 1.4768 1.5302 1.5753 1.6156 1.6528 1.6876 1.7204 1.7516 e 0 0160 0.0165 0 0173 0.0184 0.0201 0.0233 0.2488 0.3072 0.3534 0.3942 0 4320 0 4680 0.5027 0 5365 0.5695 2000 6 73 26 172 60 273.32 377.19 487.53 614.48 1240.9 1353 4 1408.7 1447.1 1536 2 1596.9 1657.0 1717.0 1777.1 (635 80) : 0.1263 0 2916 0 4337 0 5621 0.6834 0.8091 1.3794 1.4578 1.5138 1.5603 1.6014 1.6391 1.6743 1.7075 1.7389 , I e 0 0160 0.0165 0.0173 0 0184 0.0200 0.0230 0.1681 0 2293 0 2712 0.3068 0.3390 0T692 0.3930 0 4259 0/.!?9 2500 6 74.57 173 74 274.27 377.82 487.50 612.08 1176.7 1303 4 1386.7 1457.5 1522.9 1585.9 1647.8 1709.2 1770 4 (668.11) s 0.1280 02910 0.4329 0 5609 0 6815 0 8048 1.3076 1.4129 1.4766 1.5269 1.5703 1.6094 1.6456 1.6796 1.7116
)
l v 0 0160 0.0165 0 0172 0 0183 0 0200 0.0228 0 0982 0.1759 0.2161 0.2484 0.N70 0.3033 0 3232 0.3522 0.3753 3000 A 75 83 17tB8 275.22 37347 487.52 610.08 10$0.5 1267.0 1363 2 1440.2 1500.4 1574.8 163J 5 1701.4 1761.8 (6#.33) s 0.1277 0.2904 0.4320 0 5597 0.6796 0 8009 1.1966 1.3692 1.4429 1.4975 1.5434 1.5541 1.621e 145M 1.6888 e 0 0160 0 0165 0.0172 0.0183 0.0199 0.0227 0.0335 0.1588 0 1987 0.2301 0 2576 0.2827 0.3065 0.3291 0.3510 3200 h 76.4 175.3 275 6 378 7 487.5 609.4 800 8 1250.9 1353.4 1433.1 1503 8 1570.3 16343 1698.3 1761.2 (705ta) s 01276 0 2902 0.4317 0.5592 0.6768 0.7994 0.9708 1.3515 1.4300 1.4866 1.5335 1.5/49 1.6126 1.6477 1.6806 l l e 0 0160 0 0164 0 0172 0 01E3 0 0199 0.0225 0.0307 0.1364 0.1764 0.2066 02326 0 2563 0.2784 0.2995 0.319?. l 3500 4 77.2 176 0 276.2 3791 487.6 608 4 779 4 1224 6 1338.2 1422 2 14955 1563.3 16292 1693 6 1757.2 s 0.1274 02899 0.4312 0 5585 0.6777 0.7973 0 9508 1.3242 1.4112 1.4709 1.5194 1.5618 1.f402 1.6353 1.6691 j e 0 0159 0.0164 0.0172 0.0182 0.0193 0 0223 0 0287 0.1052 0.1463 0.1712 0.1994 0.2210 02411 0.2601 0.2783 4000 A 76.5 177.2 277.1 379 8 487.7 606 5 763 0 1174.3 1311.6 1403 0 1481.3 1552.2 1619 F 16S5.7 17506 s 01271 0 2993 0.4304 0.5573 0 6760 0 7940 0 9343 12754 1.3807 1.4461 1.4976 1.5417 1.5812 1.6177 1.6516 v 0 0159 0.0164 0 0171 0 0181 0 0196 0 0219 0.0268 0.0591 0.1038 0.1312 0 1529 0 1718 016M 0 2050 0.2203 5000 4 81.1 !?9 5 2791 331.2 4 83.1 604.6 746 0 1042.9 1252.9 13446 1452.1 1529.1 160] 9 1670 0 1737.4 s 0.1765 0.2851 0 4287 0.55t0 0 6726 0.7880 0.9153 1.1593 1.3207 1.4001 1.4582 1.5061 1.!,481 1.5663 1.6216 e 0 01'A 0.0163 0 0170 0 0160 0 0195 0 0216 0 0256 0 0397 0.0757 0.1020 0.1221 0.1391 0.1544 0.16S4 0.1817 6000 6 83.7 181.7 281.0 362 7 APS 6 602 9 7361 945.1 1168 8 1323 6 1422.3 1505 9 1552 0 1654 2 1724.? s 0 1258 0.2670 0 4271 0 5528 0 6693 0 7826 0.9026 1.0176 1.2615 1.3574 1.4229 1.4743 1.5194 1.5593 15962 v 0.0158 0.0163 0 0170 0 0180 0 0193 0.0?l 3 0 0248 0.0334 0 0573 0 031 A 0 1004 0.1160 0.1298 0 1424 0.1542 7000 4 86.2 184 4 283 0 384.2 489 3 60).7 729 3 901.8 1124 9 1281 7 1392 2 1492 6 15631 163A 6 171).1 s 01752 0 2859 0 4256 0 5',07 0(463 0 7/?? O8926 1.0350 12055 1.3 D 1 1 1904 1.4406 14933 1.53'5 1.5735 TABLE A.4 PROPERTIES OF SUPERHEATED STEAM AND COMPRESSED WATER (TEMPERATURE AND PRESSURE) (CONTINUED) A.6
i 6 9
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RE A.5 NOLLIER ENT utpy_g A.7
PROPEHTIES OF WATER Density e , (Ibslit') PSIA Temp Salutated 2400 2500 3000 2300 Liquid 1000 2000 2100 2200 (*F) , 62.909 6'.93 2 62.951 63.056 62.414 62.637 62.846 62.867 62.888 32 62.846 62.87 62.99 62.55 62.75 62.774 62.798 62.822 50 62.38 62.465 62.559 62.390 62.409 62.427 62.446 100 61.989 62.185 62.371 60.549 60.558 60.587 60.606 60.702 200 60.118 60.314 60.511 60.53 57.813 57.836 57.859 57.882 57.993 300 57.310 57.537 57.767 57.79 54.28 !4.311 54.342 54.373 54.529 400 53.651 53.903 54.218 54.249 53.89 53.925 53.95 54.11 53.243 53.475 53.79 53.825 53.86 410 53.50 53.53 53.69 53.025 63.36 53.40 53.425 53.46 420 52.798 53.09 53265 52.925 52.95 52.99 53.02 53.065 430 52.356 52.575 52.475 52.51 52.54 52.56 52.275 440 51.921 52.125 52.42 52.45 52.14 52.175 52.21 52.41 450 ' 51.546 51.66 52.025 52.065 52.10 51.68 51.725 51.76 51.96 51.020 51.175 51.56 51.61 51.64 450 51.30 51.50
'- 51.1 51.14 51.175 51.22 51.25 470 50.505 50.70 50.7 50.74 50.78 50.825 51.035 480 50.00 50.20 50.62 50.66 50.22 50.265 50.31 50.35 50 575 4DO 49.505 49.685 50.13 50.175 49.714 49.762 49.81 49.858 50.098 500 48.943 49.097 49.618 49.666 49.152 49.203 49.254 49.305 49.56 510 48.31 48.51 49.05 49.101 48.57 48.625 48.68 48.735 49.01 520 47.85 47.91 48.46 48.515 47.978 .48.037 48.096 48.155 48.45 530 47.17 47.29 47.86 47.919 47.362 47.428 47.494 47.56 47.89 540 46.51 47.23 47.295 46.726 4S.794 46 862 46.93 47.27 550 45.87 46.59 46.658 46.068 46.142 46216 46.29 46.66 550 45.25 45.92 45.994 45.38 45.46 45.54 45.62 46.02 570 44.64 45.22 45.30 44.672 44.758.- 44.844 44.93 45.36 580 43.66 44.50 44.586 43.92 44.015 44.11 44.205 44.68 l 550 43.10 43.73 43.825 '
43.122 43226 43.33 43.434 43.956 600 42.321 42.913 43.017 42.314 42.432 42.55 43.14 l 600 41.49 41.96 42.08 42.196 41.083 4$;217 41.35 41.483 41.616 42283 l 620 40.552 40.950 41.44 630 39.53 40.388 ' 640 38491 39.26 - 650 37.31 38.008 660 36.01 38.52 670 34.48 34.638 630 32.744 32.144 690 3D.516 TABLE A.6 PROPERTIES OF WATER, DENSITY
- A.8 -
l 1
,.- - ; q s ,, y T;bt) 1. S:turated St:am: Ternpi?stura Tabl> _
Ass Press Specilic volume hthalpy ti,ltopy Ifmp (b 8ev Sat 5at ; Sat Sat. Sat Sal Temp f aht Sq in li0md Ivrp - Vat /d liquid leap Yapot - . tiqued [vap Vapor 18ht .. I p- 99 v tg 98 h,- h 8 hg 6, i ig i- /
, leg 32 0 ' .008We 0 0160?/. 3304 7 _3MJ4 7 - - 0 0179 1075 5 10E 5 0 0000 2 1873 2 1673 32 0 '
HI 0 1 % 00 0 0160?! D619 3061 9 1 996 ' 10N e 1076 4 0 0 Del 1 176?' 2 1807 34 I all 0 1039% 0 016020 2839 0 7839 0 4 008 10737 10772 - 0 0081 2 1651 21731 M9 38 0 0 066019 ' 2634 1 0)i?49 7634 7 6 014 1071 1 1078 1 00l?? 2154l 2 1663 38 0 - et t 017161 g 0 016019 2445 8 2445 8 8 0?? 1971 0 1079 0 0 0161 ? 432 2 1594 48 1 -
<' e2 I 0 0160l9 O 1314 s ???? 4 ??774 10 0h IM98 1079 9 00?O? ? 3M 25?7 47 8
/
44 0 0 1419? 0 016019 7112 8 . 2117 8 12 041 1064 7 10h0 ? 0 0i42 ? 217 2 459 44 9 46 9 0 15314 0 0160'O -1965 7 -1%57 14 047 - 10676 10416 0 0281 2 lli 2 393 es t
- 48 8 0 16514 00160ll 1830 0 1830 0 16 %! 1066 4 . 1682 5 0 03?l 2 '006 2 317 48 8 50 8 - 0177% 0016025 1704 8 -1704 8 18 M4 10 % 1 10814 00% 7 0901 2 1267 HI
,ul 0 19!65 0 0lW4 35*9 2 589 ? 20 057 10H 7 .10M 7 06:00 2 0798 21197 12 8 '
WI 0 706?5 0 0160:6 14814 4874 ??058 10631 10851 0 0439 2 0( 95 2 1134 ' 54 0 HI O ??l83 0 016078 13836 383 6 74 059 toti 9 1066 0 0 0478 - 2 0593 71070 66 0 58 I 0 23843 0 016031s I?91 2 292 2 26 060 1060 8 1086 9 0 0516 2 0491 2 1000 fHI i HI 0 75611 - 0 016033 1207 6 I?076 78 0t.0 1059 7 10877 0 05 % 2 0391 2 0946 HI-82 8 0 77494 0 0'6036
. 1179 2 11?9 2 30 059 1058 5 10886 0 059) 2 0?91 2 088s 82 1 H8 0 ?9497 0 016039 10 % 5 10% $ 37 058 10574 10695 0 063? 2 0192 2084 64 8 -
H8 0 316?6 0 016043 9810 989 1 340% 10% ) 10904 0 06 7t5 2 0094 ? 0764 64 8 68 8 ' 0 33889 0 016046 9?65 916 5 36 054 10552 1091 2 0 0708 1 9996 2 0704 HI FII 0 36?92 0 016050 868 3 868 4~ 38 057 1054 0 10921 0 0745 1 9900 20HS 71 8 77 8 0 38844 0 016044 814 3 814 3 40 049 10529 10930 0 0783 .9804 2 0587 72 1 74 9 041%0' 0 016058 164 1 764 1 42 046 1051 0 1093 4 4 0871 9708 2 05?9 14 8 fil 0 444?C , 0 016063 .717 4 FIF 4 44 043 10 % 7 1054 7 0 0858 %I4 2 047?. 76 8 ' 78 8 0 47461 0 016067 173 8 673 9 46040 10895 l095 6 0 0895 95?0 2 0415 78 6 Ill 0 506P3 - 0 01607? 033 633 3 48 037 10484 1096 4 0 0932 94?6 < 2 0959 M8 82 1 0 54993 0 016077 5% 5 5955 50 033 10473 10973 00969 9334 ' 2 0303 12 0 H8 0 5770? 0 016087 560 3 560 3 52 0?9 10461 1098 2 04006 9242 ' 2 0248 84 8 M8 0 61518 0 016087 5??5 5275 54 026 1045 0 10990 01043 9151 2 0193 Is t H8 0 65551 0 016093 4968 4%8 56 0?? 1043 9 10999 01079 .9060 2 0139 Is t BII 0 69813 0 016099 4681 268 1 58 018 - 104? ? 1100 8 0 115 f t'0 2 0066 90 0 92 6 0 74313 0 016105 < t413 441 J 60 014 1041 6 1101 6 0 IV 4881 2 0033 92 1 966 0 7M2 0 016111 4163 416 3 62 010 1040 5 1107 5 0 188 1792 19%0 ti l IF. 8 0 84072 0016117 39? 8 392 9 64 Fe6 10M 3 1103 3 0 724 8 704 1 9978 Is t F4 8 0 833 % 0 016123 370 9 370 9 . M 003 1038 2 1104 2 0 260 8617 1 9876 M4 III4 0 94924 0 014130 350 4 350 4 67 999 10371 1051 182 0 1 00789 0 295 - 8530 .9875 tm 8 0 016137 331 1 331 1 69 995 10M 9 105 9 0 331 164 8 1 069!5 8444 9775 182 8 0 016144 313 1 3131 10M I 196 8 11347 71 997 106 I 0 34 8M8 97h ' ils 8 0 016151 29616 29618 73 99 1033 6 1076 0 402 ' 8273 IIR 8 12030 0 016158 28028 28030 MPS . 188 9 75 94 10325 100 5 0.437 - 8188 9626 IIII 110 0 2750 0 016 65 26537 265 39 77 68 .031 4 117 8 3505 0 016 73 75137 75138 79 98 030 7 09 3 02 0147[ ' 0 150i 8105 % 77 Het 114 4 4799 80?! 9528 tilI
- 0 016 80 238 21 238 22 81 97 0?91 10 01542 1938 9480 ;14 0 IIII 5133 0 016 88 ??5 84 ??5 85 83 97 027 9 19 01577 78 %
,. till 6009 0 016196 214 20 214 28 9433 H60 85 97 0?68 27 0 1611 - 7774 9384 1 48 179 0 6927 0 016?04 203 ?5 ?03 76 8797 ' 1025 6 ,36 0 644 7693 1 9339 138 172 0 7891 0 0lul3 92 94 19295 89 % 44 0 680 1613 1 9?93
/ 124 0 8901 0 016??! $323 '024 5 172 0 18324 91 96 023 3 53 0 11 5 7533 1 9247 194 0 y IMI 9959 0 016??9 178 8 2 l068 0 016238 .
74 08 6545 174 09 93 96 '0?? ? al 0 74 9 : 7453 1 9?02 IMI 16547 95 % 021 0 10 0 783 7374 1 9157 INI IM 4 1230 0 016747 15732 157 33 97 % 132 8 1019 8 17 0 0 1817 , 72% 9112 1 80 3445 0 016?S4 14964 49 H 99 95 1018 7 iMt 4717 0 016765 42 40 42 41 18 6 0 851 - Fil? ' 9068 132 4 101 % 1017 5 19 5 0 884 7140 9024 1MS 1M I 2 6047 0 016274 3555 M 57 134 8 2 7438 10395 ~ 1016 4 20 3 0 91 8 7063 ,49s0 188 0 0 016184 29 09 .29 il 105 % 1015 2 :21 1 0 M1 6986 1 8937 138 0 148 I 2 8892 0 016?93 72 98 23 00 182 8 3 0411 107 95 0 40 l72 0 ( 1985 6910 6895 148 I 0 016303 1721 1722 1 09 % 0 19 72 8 0 201s 6534 4857 144 1 $ 199' 0016317 li fe 11 76 111 % 0 I? ?) 6 0 2051 6759 8810 142 0 144 0 144 0 33653 0 016322 06 58 06 59 113 95 0 05 188 0 3 5381 0 016332 01 68 24 5 0 ?064 644 8769 H88 01 70 115 95 . 009 3 - ?$ 3 02117 6610 8127 140 0
- IW 8 3 7184 0 016343 9705 9707
* , 17 9'r '008 7 26 1 0 21 % 6536 8646 IM8 Iu l .39XS 0 016353 92 64 97 68 t' 19 6 007 0 ?69
. 154 0 4 1025 0 016363 0 2183 - 6463 4646 1620 88 50 48 52 21 % 005 I 27 7 42716 IM I 4 3068 4390 8606 lie s i
iM I 4 5197 0 016374 64 % 64 57 AM 004 6 ?86 0224 6318 0%6 1M 8 0 016384 80 82 8083 d% ~ 003 4 29 4 0 2281 6245 .8526 . 191 8 IMS 4 7414 0 016395 ??!? 77?9 ;27 % 10022 182 8 4 9122 0 016406 73 90 30 2 0 2313 1 6174 ' l8447 - 188 8 - 7392 ?9 % 1001 0 31 0 02345 38103 tu t $ 2174 0 016417 70 70 70 72 )1 96 999 8 31 8 844I 142 8 114 1 5 4623 0 016428 6767 0 2377 1 6032 8409 164 8 6748 '3397 998 6 :32 6 02409 . 3 5961 4371 1H I 5 7223 0 016440 64 78 64 40 :35 97 188 8 997 4 L 33 4 02441 1 5892 8333 IIII e 178 1 5 99?6 0 016451 62 04 62 06 3797 996 7 34 2 0 2473 $822 8295 170 8
/ 172 1 62736 0 016463 5943 5945 39 98 9% 0 MO 174 0 4%A 0 7505 5753 8258 112 0 0 016474 - % 95 M 97 41 98 993 8 M8 02537 % 84 4??!
178 0 68690 0 016486 54 59 114 0 54 61 4399 992 6 .36 6 0?M8 5416 8184 176 1 178 8 71440 0 016498 52 35 52 36 45 99 991 4 37 4 12600 5548 8147 170 0
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