IR 05000005/1988003
| ML20155G673 | |
| Person / Time | |
|---|---|
| Site: | Pennsylvania State University |
| Issue date: | 09/28/1988 |
| From: | Eselgroth P, Denise Wallace NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20155G671 | List: |
| References | |
| 50-005-88-03OL, 50-5-88-3OL, NUDOCS 8810170323 | |
| Download: ML20155G673 (22) | |
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U.S. Nucle.ar Regulatory Commission Region I OPERATOR LICENSING EXAMINATION REPORT EXAMINATION REPORT NO: 88-03 (OL)
FACILITY DOCKET NO: 50-05 t
FACILITY LICENSE NO: R-2 LICENSEE: Pennsylvania State University FACILITY: Pennsylvania State Breazeale Reactor EXAMINATION DATE: August 30, 1988 CHIEF EXAMINER: c j g ff4 d - jP- 2 8 - S d David Wa.iace Date j Operations Engineer / Examiner r
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APPROVED BY: h // 6L- Z rt/ 7- Af'37 ter W. Esergroth Chief Oate fdR Section, Operation Branch, DRS SUMMARY: A written examination (Section H only) was administered to one
, Senior Reactor Operator (SRO) candidate. The candidate passed the 1 examination.
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TYPE OF EXAMINATION: SRO Retake Of Section H Administered At The Region I,
- NRC Office ,
j EXAMINATION RESULTS: The candidate passed the examination l
! Chief Examiner: David Wallace
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' During a telephone discussion on September 13, 1988, facility staff comunicated their comments regarding the examination to the Chief Examine ;
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! Attachments: i l 1. Written Examination and Answer Key l j Facility Coments of written examination and NRC Resolution t
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' ' ATTACfEENT 1 U. S. NUCLEAR REGULATORY COMMIS$!CN SENIOR REACTOR OPERATCR LICENSE ExAMINATICN FACILITY: PENNSVLVANIA STATE UNI ,
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_..__.._______..______ REACTCR TYPE: TRIGA Ill i
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DATE ADMINSTERED: OS/08/CO t
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EXAMINER: RCE5ENER, ....__.....___.....__..._
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CANDIDATE
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INSTRUCTIONS TO CANDIDATE:
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t use separate r *
for the answer Write answers on one sice cni Staple question .t on top of the answer sneot Potnts for eacn question are 1. ' i id in parentheses after the questio The passing grade requires ( *t 70% in eacn categor Examination papers a111 de picked up sis s after the examination starts.
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% OF !
t CATEGORY % OF CANDIDATE'S CATEGORY j VALUE TOTAL SCORE VALUE CATEGORY
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C0.00 10 REACTOR THEORY '
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j 20.00 % Totals '
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- Final Grade ,
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- All work done on this examination is my ow I have neither given j i nor received ai '
1 I Candidate's Stqnature '
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, NRC RULES AND GUIDELINES FCR LICENSE EXAMINAT!ONS During the administration of this examination the following rules apply: Cheating on the examination means an automatic dontal at your application and could result in more severe penaltie . Restroom trips are to be limited and only one candidate at a time may leav You must avoid all contacts with anyone outside the examination ecem to avoid even the appearance or possibility of cneatin . Use black ink or dark pencil only to facilitate legible reprocuctions.
, Print your name in the blank provided on the cover sheet o t' the examinatio , in the date on the cover sheet of the examinatten (tf necessary),
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- Use only the paper provided for answers.
1 Print your name in the upper rignt-hand corner of the first page of eacn section of the answer snee . Consecutively number eacn answer sneet, write "End of Category __" as appropetate, start eacn category on a new page, write onl y on one side 1 of the paper, and write "Last Page" on the last answer snee l Number each answer as to category and number, for example, . ,
10. Skip at least three lines between eacn answer.
11. Separate answer sheets from pad and place finishoo answer sneets face
down on your desk or table.
12. Use abbreviations only if they are commonly used in facility literature.
i 13. The point value for each question is indicated in parentheses after tne j Question and can be used as a guide for the depth of answer require !
l 14 Show all calculations, methods, or assumptions used to obtain an answer ,
] to mathematical problems wnether indicated in the cuestion or not.
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- 13. Partial credit may be give Therefore. ANSWER ALL PARTS Cr 'Hi 1 CUESTION AND 00 NOT LEAVE ANY ANSWER BLAN !
i 1 If parts of the examination are not clear as to intent, afk ouettions of the examiner only.
J I 17. You must sign the statement on the cover sheet that indicates that the work ts your own and you have not received or been given assistance in
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completing the examinatio This must be done atter the examination has been completed.
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18. When you complete your examination, you shall: Assemble ur examination as follows:
(1) Ex a a questions on to (2) Exam aids - figures, tables, et (3) Answer pages i ncludi ng f i gures whi ch are part of the answe Turn in your copy of the examination and all pages used to answer the examination question Turn in all scrap paper and the balance of the paper that you did not use for answering the question Leave the examination area, as defined by the examine If after 1 caving, you are found in this area while the examination is still in progress, your license may be denied or revoke l l
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. REACTOR THEORY Pogo 2
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OUESTION H.01 (2.00)
What is the effect (INCREASE. DECREASE or NO CHANGE) of an increase in fuel temperature ont L (Thermal non-leakage probability)?
th f (Thermal utilication factor)? p (Resonance escape probability)? Weff'
OUESTICN H.02 (2.00)
Given the following data All rods in: Reactor ts shutdown by $5.30 Count rate is 60 counts per second STANDBY: Transient rod at 600 units Safety red and snim red at 150 units each Regulating rod full i What would the count rate be with the reactor in STANCGY" $now all wor Rod worth curves are attache CLESTION H.03 (1.50)
State the THREE nuclear s characteristics of a acoc mocerating materia CUESTION H.04 (2.50s What are the TWO processes that produce :<enen cucina -eactor operatton?
(. 00) What operation?
are the TWO processes that remove xenon during reacter (1.00) How long after a shutdown from equilibrium xencn conditicns at 1 MW will the xenon peak occur?
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l (ses** CATEGORY H CONTIN'JED ON NEXT PAGE ***=a)
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H .~ REACTCR THECny pago :
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CUESTION H.05 (2.00)
Mcw would the following conditions change the critical red position 4cr a reactor startup (HIGHER, LOWER or NO CHANGE)? Consider itach separatel a.
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A new transtent rod is thstalled to replace the old on The bulk pool temperrture is increased 30 F.
I Two used fuel assemblies are replaced with new assemblie An additional boron-lis.*d neutron detector is installed near the Cor OUESTION H.06 (1.00)
TRUE or FALSE? As keff approaches unity, a larger change in neutron pcoulation results from a given enange in kef As Leff approaches unity, a shcrter period ot time i s requi reo to reach the equilibetum neutron population for a given change in ke4 !
l QUESTICN H.07 (1.50)
Assume the +ollowing about the pcol water heat exchanger:
The secondary side has expertenced a significant build up ot corroston products over months of operatio The primary side has remained clean.
! The primary and secondary flcws nave remained constan The secondary inlet temperature has remainea constant, j'
State how the following parameters will nave a_ ianged as the secendary side corroston product c
'uild-up increased (INCREASE, DECREASE. er AEMAIN THE SAME). !GNORE all neat losses to amotent.
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i j The temperature difference between inlet and outlet en the secondary
! sid The differenttal pressure across the secondary sic (***** CATEGORY H CCNTINUED CN NEXT PAGE *****)
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j CUESTICN H.QG (1.QQi Expiatn any the safety red ts worth appecximately $1.30 ecce than the shim red.
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CUESTION H.Q9 (l.00)
Why is Geta-effective greater than Beta ter 'the PSE9" :nclude in veue answer the phystcal reason AND the term affectec in 19e ef*0ctive multipiicaticn facto OwEST:CN H.lO (2.5Q)
While operating at low power, an expertnent is anserted wnten cluces tne reactor power to increas The fcliewing cata are roccedocs
TIME POWER POOL TEMPERATURE ;
3Q secones 1QQ Watts 24 C
! 6U seconds 630 Watts 24 C l
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j What is the worth of the experiment in collars? Assume uamcca * .l.
! Show all wor (1.tQ) Ustng the value calculated in part a, if the reactor opcPatcr tuas ,
j acticns to maintain the correct neutron scaling, sacn that nc scram cccurs, but dces not change rod position, at what aver 3Qe i del temperature will the reactor stacill:e? Assume a vlaue c' i-1.4 E -Q4 Del taK/K/C f or the temperature cceffic:ent C 9 c .s s'1
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wor (C.Sua J ! On the attached fuel cross-section crawing (r'iquee C-l?. Swetch tne !
tetDerature distributicn bwicre and after the adcaticn ci 19e 1
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caportmen (1.00) (
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1 REACTCR THCCRY Pogo 5
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CUESTICN H.11 (1.0Q)
Given the following parameters:
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Reactor power 1 M Heat exchanger flow 400 (m Pool temperature 24 Heat exchanger to pool return temperature of 28.9 Tank constant of 179.7 kW/C/h Conversten constant of 6 lem/ ga Calculate tha temperature increase in tne pcol in the next nou , 5 tate all assumption Show all work.
J GLESTION 95. 12 (2.00)
Assuming the following conditions:
A xenen free startup ts in pecgres There has been NO rod motion for 10 minute The power is approximately 10 Watts.
] Complete the ic11owing taole noting the oehavtcr you woula expect to observe on the startup meters (INCREASE. DECREASE, or NJ CHANGE).
I Sitghtly I Slightly I I Succrittcal I Supercritical I g_____________g_______________t I I I Pertoa mete I I I g___________._g_______________g I I I '
Count rate mete I I I 1_____________g_______________1
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(********** END OF EXAMINATICN :ss:**e***)
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EQUAT10:4 SHEET s
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Cycle efficiency = Not g, Vork (out) * --
t w = as s = v,t + \at
E = aC ,
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gg . he,2 ,t
,y , ,, A=W A = A,e o
yg = agh w = 4/t A * 18 2/84 = 0.693/tg .
W = v&P'
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(t..) ( ts ) -
AE = 931Am ,
( + )
4=f.C,ar -r
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x = t,e 5 , k=UAAT I = I,e ""
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y.y to M (t). M = 1.3/u ' HVI s 0.693/u O .t/T ~
j SUR = 26.06/T r = 1.44 or sca = s/(1 - x,gg)
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CR x =s/i1.E,gg,)
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T=lt*/o)+ [(i 'o)/1,gg ] o 1 C
efr)1 * 2II ~ *erf)'2 ~~
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7 ,= t*/ ( , . ;-) M = 1/(1 - K,gg) = CR g/CR0 T * II ~ ') eff
M = ('1 - x,gg) /(1 - x,gg)l
! * = (K.re-0/Kef = 'Kerr/ Kerf sex . (1 . x,,,)/x,,,
p= ~3
[1*/TK,'gg -] + (I/(1 + 1,ggt )] ,
t' = 1 x 10 seconds
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l y . I4v/(3 x 1010) 1,ggAy 0.1 seconds'I J I = No
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- UATTR PAMMETTR3 Id =Idg g
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1 gal. = 8.345 1ha R/hr = (0.5 CE)/d 2 g,,,,,,)
1 gal. = 3.78 liters R/hr = 6 CE/d (feec) .
l 1 ft = 7.48 ga MTSCEt,I. ant 0US CONYTR$ IONS .
l Density = 62.4 lbs/f t 3 1 Curie = 3.7 x 1010dps {
censity = 1 ge/cm 1 kg = 2.21 1ha l Heat of vag crisatiou = 970 f tu/lba 1 hp = 2.54 1 10 ETU/hr j
Heat of fusien = 144 stu/lba 1 N = 3.41 x 100 Itu/hr
, 1 Ata = 14.7 pst = 29.9 in. I Stu = 778 ft-lbf I 1 ft. H 2O = 0.4333 lbf/in 2 g inch = 2.34 cm i
F = 9/5'c + 32 l
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'C = 3/9 ('T - 32)
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- ,
._ , s e Cross - sec r ;on of Fvei Ofx) !
'
l J
.. .. REACTOR THEQpy PaQC 6
..................
ANSWER H.01 (2.00)
, DECREASE CECREASE
- . CECREASE DECREASE REFEiiENCE
!
FSDR Training Manual, Sections 2.20.2 and !
,
nNSWER H.00 (2.00)
Total ece wceths as fcilows with S1.00 equal to .GQ7 Deltar/At
>
(32.46 +
S.54 + S.52) A .007 DettaK/K/St.00 = .025 +/- .00 Del t aN / *:
b
,
C0.25 for preper value of beta effective, 0.25 fer a tctal P C c a c " t r. c-
! $3.52 +/- 5.0o. and .025 for correct equatten a p p i t e a t t e r. .
I
Shutccwn reactivtty j 55.00 x .007 DettaK/*./SI.00 = .037 Detta</K C o. 0" Count rate calculatt ent .
'
,
CR (1 -
K ) = CR (1 - K ),
1 1 2 O f
anc p = (1-K)/K ce < = 1/(1-p; wmere p =rno (reac-i. tty .
'
There+o o K = 1/(1 + .037) = .964 (+/- .001)CO.05
1 ,
,
I K =
I 1/(1 -( .037 * .0251) = 966 (+/- .002)Ca.05]
and CR = 60 (1 - 964)/(1 -
.980) =
100 ccunts cor secenc CO.*QJ
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- REFERENCE l PSBR Training Manual, Section PDSR SCP-1, "Reactor Oper'ating Proc edure, " step PSBR Rod worth curves cated march 1987 and feund in Traintrg Manual, Section i
1 l ANSWER H.03 (1.50) i
- High scattering Cross-sectio 'l
> High average logaritnmic energy decremen \
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- LCw aesception cross-sectio ,
)
AEFERENCE l PSBR Training Manual, Section i
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l ANSLER H.04 (2.50) i
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, . F tssio I lodine deca (1.00)
l . Radioactive decay.
! Burnup, it.00) {
l I I hours (+/- I hour) ( v . $ 0.s I l
- REFERENCE PSBR Training Manual, Section 2.23.2.
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ANSWER H.03 (2.00)
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a. HIGHER
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! e. HIGNER l i c. LOWER I 7 HIGHER l l 1
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PSDR Tratning Manual, Sections 0.20 to 2.03.
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i 1 TRUE
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, FALSE GEFERENCE PSSR Training Manual. Sectton 2.1 ANSWER H.07 (1.50) REMAIN THE SAM !
I INCREAS REFERENCE *
PsaR Tratning Manual. Section 3.1 Murray, R. Nuclear Energy p. 13 ,
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I ANSWER H.CG (1.00)
Because the safety rod is located in a regten of htqher +1ux as l comparea to the sntm rQ l l
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" * REACTOR THEORY Pago 9
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REFERENCE '
PSBR Training Manual, Sections 2.21 L 2.22.
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ANSWER H.09 (1.00)
]
Because deleved neutrons are born at lower energies than premet neutrons LO.503 and therefore have a greater fast non-leakage er:bacility (0.*03.
REFERENCE PSDR Training Manual, Section 2.1 I ANGWER H.10 (2.50)
I I T = t / In(P /P ) = 30 seconcs / In(630/100) = ;6.0 seconds (+<- .5 sec)
1 0 a
p(reactivity) = st/(1 + TsLambda) = st/(1 + 16.3 * .1) = S0.38 to.50 for correct pertoc (7), 0.50 for correct use of reacti vt t e equation D.4sec on ca. dilates calculateo perico3.
1 .,
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) T = T + (Change in reactivity /The negattve temperature coetftetentt
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= 24 C + ( .0038.DeltaK/K / -
1.4 E -Oa DeltaK/A/C) = 51 ;
i l to.50 point for correct use of NTC ecuation basec on candicates result .
i ior part Answer should show a straight line :or the before sketch (0.003 ano a convex line with the peak at the inside diameter for the after 1
) (0.203 sketc The after sketen shoulo De greater at ALL points '
l than the before sketch Co.20 The peak value should be greater
- than the average calculated in part b CO.203 and the value at the O.D. of the fuel should be less than that calculatec in part b
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C o. 20 3.
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. . . . . AE.tCTOR THEORY PCQs 10
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REFERENCE PSBR Train 1ng Manual, Sectiens 2.10, 2.16 2.17, O.2 Thermal-hydr aul i c Fr t nci pl es and Applications to tne Pressurized Water Reactor. Chapter P ANSWER H.11 (1.00)
Heat removal by neat eEChanQPri
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G = mc (Tout -Tin) =
p 400 galeman s 8 lbm/ gal 4 1 man /60 sec e 1 6tu/lem/r .
(26.9 C - 24 C, * i SC =
4'O BTU /sec e 1.0540 kW/ Btu /sec = 496 kW Therefore, heat beinQ added to cool is 504 kW 504 kW / 178.7 kW/C/hr = 2.8 C (5.1 F) +/- .2C ( 4 F)
C0.50 for ccerect calculation of heat removed av heat e x c h a s s e r* . C.50 for correct calculatton of temperature rise in pcol cased on candicates value of heat deposited in poo1 HEFERENCE i I
l PSBR Training Manual, Sections 3.1 i
r> C D R CCP-2, Reactor Thermal Power Calibrat1on".
Thermal-hydraulic Principles and Applications tc the F*rescurtfoc .44ter Reactor, Chapter l l
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- ANSWER H.12 (2.00)
1 Slightly I Slightly I 1 Succettical ! Sapercettical !
g.-___........g......_- ......:
I ! !
Period me t tir . I t0 CHANGE I INCREASE I g..__.........g_..............
I I I Count rate eete I NO CHANGE I INCREASE I g.............g...............g REFERENCE
- PSDR Training Manual, Sections 0.1 I
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I i i l ATTACHMENT r ;
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l TACILITY COMMENTS AND NRC RESPONSE FOR
- SRO SECTION H EXAMINATION ADMINISTERED ON AUGUST 30, 1988 i
guestion H.07a
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Facility Comment: Buildup of crud in the heat exchanger will decrease the j heat transfer and therefore the change in temperature on 6 the su ondary side will decreas l NRC Rtsponse: Comment note The question has been deleted because the >
answer is dependent on the rate of crud buildup and the j length of time ever which the temperature transient is :
, considere }
. i 1 Question H.12 The facility interprets the question to be referring to a !
] constant period startup since a startup is in progress and i'
no rod motion has occurred. Under this condition, in a .
slightly supercritical condition, the pericd meter will j remain steady, t
- NRC Response: The comment is vali Additional review has resulted in ;
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the question being deleted, since source strength is not i addressed, and the term "slightly subcritical" is too vague i l to convey a period of time that will permit subtritical !
- multiplication to cause a steady countrat .
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