ML20235T221
| ML20235T221 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 02/06/1989 |
| From: | Elin J, Johnston G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML20235T192 | List: |
| References | |
| 50-312-OL-88-02, 50-312-OL-88-2, NUDOCS 8903080198 | |
| Download: ML20235T221 (89) | |
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- m 4 Examination; Report,-No.t ,- ! 50-312/0L-88-02~
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<Jacility:
y , 4 4.f - - L .' - 3 DocketTNd;y, iO- y, E' '50-312v a 7 s., , ,, m. u- - . p , ,3. . o - S Exaininations administered.at Rancho Seco Nuclear Power' Plant, Clay, Station, yl 'g
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,3 f[ .-Chief E aminerb .;- /) 3 '
'/5 1 Gary W\/Johnsson, Date/5fgned -
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' Operator Licensing Examiner
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, 0. Elin V Date Signed .
L John Chie [f, Operations Section a w Summary: '
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, Examinations' on December 6-13, 1988 (Report No. 50-312/0L-88-02). Written v .and oral-examinations were administered-to seven Senior Reactor 0perator. ,
~ '
. candidates. i All seven SR0 candidates passed both the writtenTar.d oral ,
C examinations. i
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g EREPORTJDETAILSL
- 1. Examiners: .>
G.Johnston,-RV(ChiefExaminer) "
- 2. Persons Attending the Exit Meeting:
G. Johnston, RV-C..Felton, Rancho Seco q
- 3. Writte'n Examination' and Facility Review: ,
L .. The written examinations were administered to seven SR0 candidates on December 6 1988, i A proadministration review of the written examination was conducted with facility trainingLand operations subject matter experts on November 30, 1988. The reviewers provided the Chief Examiner with-comments and suggested corrections. These comments were duly considered and changes were made prior to administration of the-examination to the candidates. At the conclusion -of the written exam, the facility staff was provided'a - copy of the examination and were instructed to provide written comments.
;The comments made by the staff a N included in the attachment (1). These comments'were' reviewed by the Chief Examiner and appropriate changes.
were made to the examinations prior to grading, p ,
- 4. Operating Examinations.
The Chief Examiner administered all of the operating examinations from December 7 through 13, 1988. No specific generic weaknesses or concerns were identified.
- 5. Referen'ce Material 7
,. d .
The Chief Examiner identified a concern about the quality and completeness ?
.of the reference material provided by the facility'for the preparation of.
the examinations. When the material wasereceived information.on thej ' ' ' ' ( following systems were not provided: + lie " o
+
9 Main Turbine and Generator .
*. - ' s Condensate System l ..
Feedwater System ' ' Circulating Water System ' ., ; q Main Steam System -
> ' Once Through Steam Generators >
Steam Bypass' System . F
- tw 7
Further there were instances of a lack of diagrams for many of the systems descriptions that were provided. The Chief Examiner did convey the lack of the information early on in the process of preparing the examinations and 3 the facility did provide the requested material. The requirements for material to be provided for preparation of examinations is clearly identified in the attachments sent with the 90 day letter scheduling the examinations. The daterial provided for the missing information did not have identified lesson plans or learning objectives. The Chief Examiner requested during the pre-examination review with the facility training staff that they indicate any question they could identify as not meeting any specific requirement. None were identified by the facility staff during the review, and the Chief Examiner noted that these had been accepted by the staff.
- 6. Exit Meeting The Chief Examiner met with the facility representative denoted in Paragraph 2 on December 13, 1988. The examiner discussed the findings to that point and the examination process.
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+ , j RESOLUTION'0F~ FACILITY-COMMENTS'
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4 FacidtfComment: g i4 , 4
'*i_'= ' " ' a' . .. f could' be consiciered a' correct ' answer as well as 'c.') OTSG Tsati; i
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+ and Tc: will? be coupled andzstable." '
4, t., N ', .. 4 [ : Resolution:*( . y.% , .m **
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a' n . 1 . . . v... _ The' Chief Examiner willidelete this; que5 tion', because' of-two possib1'e-correct' answers.ri -
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. Question 6514;;g_ Y jji /
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"No RCPs running or RCS pressu', '
r e]1000lpsig should be accepted as:a
, icorrect' answer." .
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~ ~ The Chief Examiner will Linclude the comment as' a' possible answer. *:s v.
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. Question 6.02~ q
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, , .o Facility, Comment: '
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', ; "For.the 'a' portion the only starts are High Radiation and Manual.
For the 'b' portion the. only answer /shoula be "High ' temperature' in :the :
- NSEB'switchgear room.""-
Resolution: '
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..S ^Part .'a' will be changed, and'part 'b' will be changed to ensure that o
j high temperature is the. answer.. .. t Question 6.04
^ Facility Comment: -
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"'b'=should read " Valves close when demand is.at 20% and decreasing.""
3 Resolution:, ? ,
-The key will be changed to incorporate the comment.
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- Facility Comment:
E "One pump per loop and- three pump ' operation' are two separate' limits.. The minimum load limit is also a correct response." Resolution: The. Chief Examiner will add the responses to the. key..
. Question 7.08'.- ',
Facility' Comment: '
"Sincelhe# question does not state that'the OTSG has been isolated,.
steaming.is'. required bf E.06 until an isolation criteria has been met. The' answer given' assumes that.the generator has been isolated." 4
-e Resolutions L
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ThelChiefExaminer'seesnonbe'dtochangethekey.Thequestiondoesn't-
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clearly) state thatithe OTSG is isolated, but the way the question is phrased that isithe'only possibility!'
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3 Question;7.11 a Facility Comment: 1; ', s1 "The 381 inches level is established to enhance boiler condenser cooling. and mention of this should be correct as well. as the natural circulation answer given on the key.", Resolutions The Chief Examiner will add this comment to the key. Question 7.19 Facility Comment:
"The 40 deg. F to 60 deg. F dT is to promote heat transfer (ensure a heat sink is available)."
' Resolution:
.The Chief Examiner will accept for full credit that the-delta T is to ensure adequate heat transfer from the primary to the secondary.
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. 1 Question 8.14-Facility Comment:
"The vent valves shall also be closed and tagged."
Resolution: i The Chief Examiner agrees and will add this to the key. -4 s v 3 1 1 Y s 4
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- U.S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION Facility: Rancho Seco Reactor Type: pasenet, anri uilenv Date Administered: noremsar A long
' Examiner: Garu u .1nsn e + nn Candidate: ' k', u 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 and a final grade of at least 80%. Examination papers will be picked up six (6) hours after the examination starts.
% of Category % of Candidate's Category Value Total Score Value Category 25 25 5: Theory of Nuclear Power Plant Operation.
Fluids, and Thermodynamics 25 25 6. Plant Systems Design, Control and Instrumentation 25 25 7. Procedures - Normal, Abnormal Emergency, and Radiological Control 25 25 8. Administrative Procedures, Conditions, and Limitations 100 TOTALS Final Grade All. work done on this examination is my own I have neither given nor received aid. , Candidate's Signature
ES-201-1 Enclosure 2 NRC ROLES AND G,UIDELINES FOR LICENSE EXAMINATIONS
..;. e .:e..-
During the administration :. . ; . of.this
.. . . .. examination the,following rules apply:
1. Cheating on the examination means an automatic denial of your. application and could result in more severe penalties. i 2.
' Restroom trips are to be liniitud and only .one__candidata-at-a-tiny-leave. You must avoid all .
room to avoid even the appe.contac'tY ~ aranc'e or possibility with anyone of.outside cheating.--- the-examination _- j
- 3. o Use black in.k.v.r..dar.k pencil only to facilit E legible reproductions.
4.
.3 Print your name in the blank provided on the cover sheet of the examination.
- .:. : n ::: P ce er;sve 1. rr'ce ar.sv e" : : t MM '
5xes Mi-1 sh4he- datr arr t1Tue etner1h'etrof the^ 'eYainihatichi(if necessary).
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6.e t: Ost.only tJar paper;provtidad for anstorst ...=in
; J tre : .- ;s : ve: ;- :" - -- -
- +- -:
7. Print your name in the upper right-hand corner of the first page of each section of the answer sheet. 8._.
.. Consecutively number each answer sheet write "End of_ Category" as
- approprfite, start e_ach category on a n,_ew page, wr_ite only one side of, the paper, and write "Last Page"_on the_last answer sheet.
9. Number each answer as to category and number, for example,1.4, 6.3.
- 10. Skip at least three lines between each answer.
- 11. Separate answer sheets from pad and place finished answer sheets face down on your desk or table. ~
- d. Use abbreviations only if they are commonly used in facility literature.
13. The point value for each question is indicated in parentheses after the qu.stion and can be usetras a guide"fFthe depth of. answer required.
- 14. Show all calculations, methods, or assumptions used to obtain an answer
-to-mathematical problems 3hether indicated in the question or not.
- 15. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND.DgDT, cLEAVE;ANL@SWERBLANK. 3 ,ne- . ,t 16.
If parts of the examination are not clear as to intent, ask questions of the examiner only. -
- 17. You must sign the statement on the cover sheet that indicates that the work is your own and you have not received or'beerr given assistance in completing the examination. This must be done after the examination has been completed.
Examiner Standards
~
- ES-201-1 Enclosure 2 .
18. When you compl. eft your examination',. you' ^sha~1'1:- ~
- a. 1 Assemb.le your examination as follows':t .
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. m;. . . (1b. Eyas questipos;onutop. c z . - - r . .
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, (2.-) resExam aids -' figures, tables, etc.
(3).. Answertpages 1- avc c including. figures.which are'a part of the answer . rb;. Eir a r ; > " - ~ . Turn. . estr 6in your copy;o;;f the exa i
. . . . t.h.e ex. amination questions. m c.
nation and'all "pages used to answer i - r.e ' ' ~ ' ~ c.. . Turn
'not use f.orall scrap.papertand for answering the questions. the balance;of 4the ~ paper that you did
- d. ... . :-c - ; ---
Leave the examination area, as defined by the examiner. If after in progr,essleaving you are found in this area while the examination is stil
, your license may be denied or revoked.
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O! ' -' - c;- ' :. . Examiner Standards l 4 1 (
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1 ! 1 i.cer, yo. n .a r.. your em r.t , c F = ma y=s/t
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Cycle efficiency = ,% g W = mg 2 A=AN s = vot -l- ) at A = A. e- A*
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E = mc2 . ei(y,_ y )/t A = In 2/tg = 0.693/t'g _a .t. - (eg) (e )
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P E .= m gh . w = 6/t I = I. e-E" W = vA P ' m - M b- ' - = r..- I = I. e-#" A E = 931A m .
,, ,._ I = I.10-x/m i
j Q =zhCpI Y ' #Q7:$~5~' h TVL = 1.3/p Q :* UAAT" M'6 p UA'(TnO -- Tsm{~' HVL = 0.693/p Pwr = Wr rh .- SCR = S/(1 - ka) P = P.10sm3) CR, = S/(1 - kax) P = P.e*/* CR1 (1 - kg) = CR2(1 - kg)2 SUR = 26.06/r M = 1/(1 - kg) = CR /CRo i r = 1.44 DT M = (1 - kg)o /(1 - ka)2 SUR = 26 hM ' SDM = (1 -km)/km 7 = (t*/p) + [(4 - p) /Aa p] l' = 1 x 104 seconds r = t*/ (p -g) Aa = 0.1 seconds-1
. r = (4 - p)/Aa p I tdx = I '2 da p = (ke-1)/km = Aka/km ' I2 d2 = 12 d2 p = [t*/rkm) + [S/(1 + Aar)] R/hr = (0.5 CE)/d2 (meters)
P = EpV/(3 x 1028) R/hr = 6 CE/d2 (f et) E=Na WATER MISCELLANEOUS PARAMETERS CONVERSIONS 1 gal = 8.345 lbm 1 Curie = 3.7x1020 dps 1 gal = 3.78 liters 1 kg = 2.21 lbm 1ft3 =- 7.48 gal I hp = 2.54x103 Btu /hr Density = 62.4 lbm/ft* Density = 1 gm/cm8 1 MW = 3.41x108 Btu /hr 1 Btu = 778 ft-lbf Heat of Vaporization = 970 Btu /lbm I inch = 2.54 cm Heat of fusion = 144 Btu /lbm *F = (9/5'C ) + 32 1 Atm = 14.7 psi = 29.9 in. Hg.
*C = 5/9 (*F - 32)
I ft. H 2O = 0.4335 lbf/ina
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Principles of.; Nuclear Power' Plant.
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- Op e'r Et i orr, Thermodynamics. Heat Transfer,
~and' Fluidi F1aw'
+ 0 U E S T 1 0 N ..'5 . 0 1 . (0.'75 )
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- HuiTIPLE'CHD3CE -(Choose the best answer.i -
e.e iechniAej Specification 3.5.2.1,staten.,.that the avai1abin. Shut dpwti. Mar ni n sha) 1 not be J ess than 1% delta'Idk.
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'a. 'lhe Shutdown tsargin a s the reacti vity dif f erence between -
. . criticality and all rods f ully inserted.
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b._ the highest worth rod must be consid red i n the: cor e to calculate the Shutdown Margin. -
- c. t he Snutdown Margin i s the amount the reactoi tan be shut down with the most reactive rod stuci: out.
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- d. Reactivity i s not anfluenced by the position ot the controf rods.when calculating Shutdown Margin.
!* ANSWER-
. c, '
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.*REFEREWCE OD 30'C0506, FIXT-05-OO3, DBil-1, pace 1. , ,
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MUL'IIPLE CHOICE (Lhoose the best answer.) lonor ) tio the- mi nor syst em losses, the heat ti ansf erred f rnm the reactor coolant system to the secondary system is equal. Wnsch of the f oll owino describes why t he primary and secondary mass fJow rates across the O T SG 's d 2 + + et-?
- a. The piping d2ameters are significantly different, thrrrfore to maintain the same velocities the flow rate has to vary,
- b. 'Ihe delta I through t he secoridary side of the OT5G's., i ta smaller than the celta I through the primary side,
- c. Ylie enthalpy change through the secondarv side of tne 015B'r is smaller than the enthalpy change throuch the primary F. i d e .
- d. the secondary side of the OlSG's undergoes a phase chance wh2le the primary side does not undergo e phase chance.
+nNSWER d.
+REFCRENCE OD 30 D 0700 OGJ 1. PG 2 OD 30 D 1400 DEO 1, PG 2 002000i$01 OO2OOuk511 193OO3K108 b
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+ 0LIEST I ON 5.03 (0.75)
MULTIPLE CHOJCE (Choose the best answer.) During a Fenon free reactor startuo, critical data was inadvertent 1v taken two decades below the required Intermediate Range t)R) l evel . Assum2ng RC5 temperatures and boron concentrations were the same: Which o+ tne f011owing describes, the r el att onsh2 p bet ween the critica] rod posi t i on Al THE PHOPER Interniedi at e kanae 1evel ver son t he cri t2 cal rod por_stion taken IWO DECADES BELOW t he proper Intermediate Range level?
- a. the crliltal rod posit 2cn 61 Il-lE PROPLR Inter medi ate Rance level is less than the critical rod position taken TWU DECsDE5 BELOW the proper Intermediate rance level.
- b. 1he critical rod posit i on A1 THE PROPER Intermediate Rance l evel is the same as the critical rod posi ti on t aken ~ LWD DECADES BELOW the proper Intermediate range level.
- c. Thr cr)tical rod position AT 1HE PROPER Intermediate Ranoe level is creater than the critical rod posi tion taken TWO DECADES BELOW t he pr oper Intermedi ate range J evel .
- d. The ci-itical rod pocition AT THE PROPER Int ermeciate Rance l evel cc.nnot be compared to the critical red position teken IWD DECADES BELOW the proper Intermediate range level.
- ANSWER _
h.
+ REFERENCE OD 30 C 0600 OBJ 13 00 30 C 0600 OUTLINE PG l '?-21 192OOt3h 110 1(72OO2K107
*DUEGIIOl1 5.04 (0.75) fiULTIPLE CHOJCE (Lhoose the best answer.)
I n ttin event of a rod elect 2on accident, wh2ch one of t h e-f011owino wi11 be the-f2rst to insert negatsve reactivity? es . firad er at or temperature coeffstient.
- b. Pressure coefficient.
- c. Vo2 d coef ficient.
- d. Doppler Coefficient.
+ ANSWER d.
+ REFERENCE OD 30 C 0400 OBJ 6 OD 30 C 0400 OUlLINE PG 15 J 9 2004):.113 00001El)1B
- DUES 11014 5.05 (O.75)
MULTIPLE CHOICE (Lhoose the best answer.) Which one of t he f ollowing statements best describes the pr oducti on and removal mechanisms 4or Xe-135? A. At low power l evel s , Xenon decay is the major removal mechanium. At hiah power levelt, burnout is the ma.1or removal mechanism.
- b. At ful1 power. steady stat e. about 10% of tne Xenon 2s produced by lodine decay and the other 90h su produced es.a d2 rect f2Esion product.
- c. F oll owi ng a reactor trap from equilibrium condstions. Aenon peaks because delayed neutron precursors continue to decav to Xenon while neutron absorption (burnout) has ceased.
- d. Xenon production and removal increases linearly as power levej increases, i.e., the value of 100% equilibrium Xenon is twice that of 50% equilibrium Xenon.
+ AIJ5WFR 6.
*REFEREl4CE OD 30 C 0500 OBJ 14 OD 30 C 0500 OUTLINE PG 16-17 OO1000K533 192OO6K103 192OO6K104
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MUL11PLE CHOlCE (Choose the best answer.) Whi ch 04 the f ol l owi ng is CORREC1 concerning the conduct of a' secondery calorimetric?
- a. 't he cal ori metri c equation does not take 2 nto account t n e-heat input from.the reactor coolant pumps or loss to the conta2nment, because these o+ f set .
- b. It f es=dwater temperature is read erroneously high the c al cul sit ed r eact or power w211 be 1ower than actual becaust the change in enthalpv w211 be 1ower,
- c. 'Ibe niasc fl ow rate of the secondary system 2s determined bv totaling the average steam flows f rom the two OTSGs.
- d. Thre reEults of a primary calorimetric may De used as the banis for calibration of the Power Range nuclear instrumented 1on but not the Intermediate Range.
+ 416HFR b.
+REFEREi4CE OD 30 D 1400 OBJ 1 OD 30 D 1400 OUTLINE PG 2 193OO7KlO8 h
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+DUEST1DN 5.07 U>.75)
MULTIPLE CHOICE (Choose the best answer.) Reactor power has .i u nt been 2ncreasPc by 30%. Which of the f ol1owing best describes what wi11 happen to Xenon concentrat3on at t er ihe 2nerease 2n power?
- a. Xenon concent rati on will incr eaEe and reach a hiah ir 1.f to 18 hours.
- b. Xenon concenti atiors will 2ncrease end reech a h2ch in 4 to b hours
- c. Xenon contentret 2 on wi 11 di p r eachirin a low an 12 t o 18 hours.
- d. Xenon r. onc ent r at i on wij1 dip reachino a low in 4 to 8 hourE.
*nH5HER d.
+ REFERElJLE Ob 30 C v500 UBJ 16 O D 3 0 (; 0500 OdlLINE PG 17 -
39 192Ove,K 111 l l l l
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MULiIPLE CHOICE (Choose the best answer.)
't he reactor is critical at 10~ amps in the ] intermediate Hanot?
when an DiSG Atmospher2C DLimp vs,1ve +ai1s open. The p1 ant 35 m beginnsng of life (BOL) conditions. the reactor does not trip, and the. rons ere 2n manua.1. tPO4H = Poi nt of Auding Heat /. Which of the f ollnwing best describes the value of Tave ano l niicl ear power + or the res.ulting new steady state condi ti on :'
- a. 6- i n a l Tave less than initial Tave, iinal power at POAh,
- b. F ) n a .! I'a v e less than initial Tave. 4inal power above itHh.
- c. F- i n a l Tave greater than initial Tave. final power above F'OnH .
- d. f' i n el 1 ave greater than initi al 1 ave, 4inal power at PUHH.
+ AIJ5WER b.
- IiEF ET ENCE OL 30 C 070'.s OBJ S.7 OD 30 C v700 ULilLINL 9 - 11 DD 30 C 0700 TRAINEE HANDOUT PG 1 - 4 192OO8h114 e
+0 DEST 3DN S.09 10.75) hijL'lIPLE CHUACE (Choose the best answer.i Wh2ch o+ t.he f ol l owi ng best describes the hesit transfer procrts through the pellet to claa oas gap in a +uel pin?
- a. Radi at i on
- b. Convection
- c. Conduction
- d. Iransmi sui on
- HriSWER c.
+ REFERENCE OD 30 0900 OBJ 2 OD 30 0900 SUBJECT NDYE5 PG 9 - 7 ,
1930071:101 e
+ DUE E l I ON 5.10 (0.75)
MuilIPLF. CHOICE (Choose the best answer.) Whi ch o1 thre ic1]ow2na best des. tribes. the Svetem Head Lort f or a mein +eedwater pump operatino in nnrmel c ondi t i on s"?
- e. l h t.- E ve t eni Stt$ti c Head (UT SG prer E.urc ) plus the Pumo in1ie Head,
- b. Ihr total Pump Head pl us the byrt em Stat 2 c Head (0156 prescurcs,
- c. t he Synt r m Strit 2 c Hend (0156 pressure) sn2 nur, t he Pump Des t e Ht*a d .
- d. 6he Total Pump Head minus the System Static Head (OT56 pressurer.
*s!45WER J.
+ RE F E RElJCE OD 30 D 1300 OBJ 10 OD 30 D 1300 SUUJEC1 NOTE 5 PG 13-14 TO 13-16 1 % O U S K 1 1 ti 3 93004ll:114 4
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*DUESl10N D .' 13 ( O . '7 5 )
MUL1IPLE CHu1CE (Lhoose the best answer.J
~
Corisi d er n nsaa n feenwater punip operatino 2 n normal condi t a nnt.. Which o+ the f ol1ow2 no parameters w211 increase the avai1abJe llet Pnsi t i ve buct i on Heaci f or the niain 4eedwater cump as puma volumetric flow is increased?
- a. The system static pressur e i t, lowered.
[ b. lhe system saturation pressure is raised.
- c. The systrni flui d t etoperature is ratsed.
- d. lhe system fluid temperature in lowered.
+ ANSWETs d.
- REFERENCE 00 30 D 1300 0b.3 13 OD 30 D 1300 OLITLINE PG 3 193OO4K10=
19.1 Ov41'.1 u l
+ QUE S1 ] 014 5.12 (O.75) tiULT IPLE CHOICE (Choose the best answer.)
Raricho Seco i s in a nattiral circitl ation cooldown f ollowino a J os.,s et offsite power. A voia (bubble) has inadvertently been tormed i n i hr head duri ng the cool down. 14 Auni11 ar y bpray is used in the pressurizer, wh1ch of the f of 1 owi ng best des t r i bess what wi .11 happers in the Reartor t.oni ar t Syst em?
- a. The si z e of the void in the head deer enEec because RLS pressure decreases.
- b. The sir e of the void in the head increasec because ci the RCE pressure decrease.
- r. t he voi d in the head increases in size because the pressurizer bubble has decreased in si:c.
- d. ~lhe void in the head remains the same in size, only R E.5 prerzure will decrease.
+ ANSWER c. *RF.FEREhCE NO REFERENCE FOUND IN MAlERIRL FOR REACTOR THEORY. Facility revtewer* accepted.
1930u3t . ) O2 193v03k108
+OUESTION 5.13 (0.75; MULTIPLE LHOICE (Choose the best answer.)
Due t o a tailure of the rod pos2t2on ind2 cat 2cn a control red has been left tully inserted in the core while at full power. The contrn] rod 2e w2thdrawn clowlv over a one hour interval. Wh2th one of the fcllowino best describes the e+fect thas event E has on the Departure 4 rom IJueleate Boll 2 no Hati o ti>l4Dru 2 ri tnP Coro/
- a. It han increated in the #irea where the r od was prima #2 J .' due to the 1ow Xenon concentration.
- b. It has increased in the area where the rod was pr2marijv dbe' to the high Xenon concentration.
- c. It . leas decrerased in the area where the ron was: pri mar 21 y due to the low Aenon concentration.
- d. It l e e s. decr eased i n the area where the rod was pr i mar 2 J v aue to the blah Aenon concentration.
- stJGWiiR c.
+ RE FEREl Jt' t!
OD 30 D 1000 OBJ 1 UD 30 D 1000 DU1LIlJE PG 1 -c OD 3u D 10uO SUBJECT IJOTES 10-2 TO 10-4 001OOOK513 l l s L-l h l l l l l L . w __ _ -- __
1 I
+ OllEST 1 DN 5.1/1 (O.75) 1 MUi11FLE CHu1CE (Choose the best answer.)
LJh3 th of the f ollowing best deccribes what occurs f oll owi no s reactor trip from sustained operation at 100% power?
- a. The power (nt titron f l u;: ) level drops to about 80% anci ' hen decreases with a decay rate that approaches an -1/7 oecede prt manute rete.
- b. The power (netit r on 41 u >: ) )evel drops tn about c,% and then decreases with a rate that apprcachec a -1/3 dr.'cade per noi ritt t e rate.
- c. the power ( rieut r on f l u:: ) level drops to about 4 6*. and then decreases with a decay rate that approaches'an -80 secono decay period.
- d. ihe power (neutron flu :) )evel drops to about 9ed, and then decreases with a decay rat e that approaches a -1/3 decade per minute rate.
*AHSWER
- b. tu.7D)
+ RE FEF.El jCE OD Ju.> C 0600 DN 19 OD 30 C 0600 OUTLINE PG 43 192OO3K108 e
f I
.m_._._
;A b-
*DUESTION D.15 (O.75)
NULT IPLE CHOICE ' (Choose the best answer. )
'Whi ch ' of l t he f oll owi ng describes ' an indication that assi et n i n veri f yi no- netttral circulation in occurring f ollowing' a loss o+ -
04 f si te powse r? w./Li ,
- a. Reactor Coolant System wide. range cold' lea ~ temperature-r- '
st abi e or ' decreasa nti.'sl owl v. '
- b. Reactor-Coolant System' wide rangc= hot'lec' temperature.neer
, caturataon temperature of. Steam Generator. p
- c. Reactor Coolant System wide range-hot leg temperature..stabl e.
or decr easing slowly.
- d. ' React or Coolant System wide .rance hot ') ea temperature more than saturation temperature of. Steam Generator.
- ANSWER
- c. to.75)
- i. ':
- REFERENCE OD:30.D 1400'OBJ~10,l'2 DD 30 D 1400 SUBJECT NOTES 14-1S TO 14-18 193OOGK122' t
%fO l' OL ,
kb_I_I% i/1-Y ,? Y. -
-8
,f.
. - - _ _ . -- ..___----.-n--_u- , _ _ _ . _ _ _ . _ - _ _ . . - - - - - - - _ _ ~ . . . . - -
l 1 -1
)
+ QUEST 1OfJ 5.16 (O.75) ):l l' !
MUi_1 IPLE CHO1CE (Choose the best answer ) 1 Aceun:) ng e11 other Departure from Nucleate Box 1 i ng par amet er s. remain constant, which of the f ollowina will cause the Depar tut e f rom Nucleate boiling Ratio (DNBR) t o decrease? t o. < ; i a.' Reactor thermal p o w er- der.reases
- b. Average React oi- Coolant temperature increareb
- c. Reactor Loclant pressure increases
- d. Rea r.t or Cool ant f1ow increases
- ANSWER
- b. 40.7D
*RE F E FiEliCE Ger:et'ai Physi c s . Rx PWR Li mits p.243 Gi.n s er al Ph y si c.s . Boi1ino Heat Trans+er p.122 DD 3is D 0900 CiBJ 3 1C.008HJUS i
l 9 s i
*DLIE5 TION 5.17 (O.75)
MULTIFLE CHUICE (Choose the best answer.) F or the f oil ow) no questi on assurne that no operator action oc r ur s: . Consider each occurrence independently with steady hiah power ' opera ti on. Whith of the f 01 ) owi no will decrease Net Positive Suct2on Hoad avai1able to the Reactor Cool ant PurnpC W.75)
- a. C,r i d f requency decr eases t o 59. 6 HZ.
- b. Pr essuri n er temperature decreases.
- c. lurbine power increases with rod control i n rnanual .
- d. Pressurizer pressure increases.
- ANSWER
- b. (0.75)
+ REFERENCE OD 30 D 1300 OBJ 3 DD 30 D 1300 OUTLINE PG 3,4 OD 30 D 1300 SUBJEC"1 NO1ES PG 13-2 OO3OOOK110 OO3OOok201 191004K106 l
I l 1 i _ _ _ . _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ . _U
- r. _ _____ ___-__-
l-
+0UEST]DN 5.18 (0.75) 1 MULllPLE CHOICE (Choose the best answer.)
Wnich of the f ollowi no descri bes what happens to the inteoral rod worth at 1007. power as the core age increases? (0.7b)
- a. Increaser due to the fact that the boric-acid concentration in the core is less at EOL.
- b. Iricreases, due to the fact that temperature of the rods are hicher at EOL.
- c. Derreeses, dut - to the f act that the temperature of ttie rods arr' hicher at EOL.
- d. Decreases due ta the f act that the bori c-aci o concentrate ori in the core is less at EOL.
*ANSWFR
- s. (0.75r
- REFERENCE OD 30 C OSOu OBJ '7 OD 30 C 0500 OUTLINE PG 9 OO1000K502 192OO5K105 192OObR106
*DUE5'110N 5.19 (0.75)
MULTIPLE CHOICE (Choose the best answer.) Which one of the f o} } owino best describes the effect that DECREASING RCS Tave from 585 degrees F te 56v degrees F will have on Moderator Temperature Coe4ficient? tu 'D)
- a. It becomes less negative because baron and water molecules are swept i nt o t he core as a result of the outsurce trom t t,e pressurizer resulting 2n more resonance capture.
- b. It becomes l ess negative because the rat e of chance in t he density of water per decree temperature chance 1s'less at 1ower temper at ur e resul ti ng in a lower change of resonance escape probab21ity.
- c. It becomes more negative because thermal uti l i z ati on increases and resonance escape probability decreases.
- d. It becomes more negative because as temperature 2s lowereo, the moderator becomes more dense, increasing the water mol ecul es in the core wi th the neutrons have a greater probability of collidino with a water molecule and 2 nr.reasi ng the negati ve reacti vi ty effect.
+ ANSWER
- b. (0. 7 5)
- REFERENCE OD 30 C 0400 DEtJ 4 OD 30 C 0400 OUTLINE 8 - 9 OO1000K526 192OO4K106 l
l l __- __-_..__________________m
1 l 8 x
- DUE5T I Dl4 5.20 (D.75)
I t1 ULT IPLE CHOICE (Choose the best answer.) ' Wi t h the pl ant operating at 85% power and all systems in a normal / auto configuration, the operator borates 30 ppm. Whi ch one of the f ollowing best describes what happens to the avai 1 able Ehutdown 11argin? (0.75)
- a. Increaee
- b. Increase untij rods n.ove
- c. Decrease
- d. Decrease until rods move
- ANSWER
- a. ( 0. 7 5)
+ REFERENCE
-DD 30.-C. 0800 DB.1 3 DD 30 C 0800 OUTLINE PG 9 - 14 192OO2K114
)
i
- QUEST 1DN 5.21 tO.75)
MULTIPLE CHOICE (Choose the best answer.) When synchronizing the gencrator to the grid, an operator will regulate turbine speed to slowly rotate the synchroscope in the f ast s ci or kwi se) direction. Which choi ce bel ow gi ves the two par ameters . that the synchretcoot-ie indicatino? o.. 75;
- a. Current arid vol t ago di f 4erences
- b. Voltece and frequency differences
- c. F r eques er y and phase differences
- d. Phase end current differences
- ANSWER
- c. (0.7bs
+ REFERENCE OD 30 G 0400 OBJ 20 0620GOA403 1
l i _ _ _ _ - _ _ - _ _ _ _ _ _ _ _ . _ - . _
1
+DUESI1Of4 5.22 (O.75)
MULilFLE CHOICE (Choose the best answer.) Whi ch one of t he f ol1 owing stat ements is CORRECT concernina i he peral1eling of el ectri cal s vst ems'? (v./Si
- a. Hithouah 2t is desirable to havo speed and phase pos2tiori matchea. it is much more important to halve voltages matcheo than to have phases matched.
- b. 1+ voltaaes are not matched at the t2me the synchron2=ing swi tc h is closed, there will be VAR f low f r om the lower to the hiaher voltage.
- c. If the incoming machine is at synchronous speed but out oi phase with the running bus when the breaker is closec. heavy currents will flow to either accelerate or retard the i ncomi ng machi ne.
- d. 14 i he incoming machine is in phase but slight 1y 4 aster than synchronous speed when paralleled, the system will tend to speerj up to synchronous speed.
- AriJSWE h
- c. 10.75)
+ R EFERE NC,E OD 30 G 0400 OBJ 20 062OOVA215
*OUESTIDN 5,25 (O.75)
MUL'lIPLE CHOICE (Choose the best answer.) Rancho beco is operatino at 50*/. power , BOL, when a steam bnaase val ve f ai 1 s 'open. Assume that rod controi is in manual. no oper at or action is taken, and no reactor trip occurs. Which of the f ollowi na describes the rel ationship affectino reactor p ower '.' u) . D )
- a. Reactor power increases due to the negative reactivity added through the Moder ator Temperat ur e Coef f i ci ent .
- b. Reactor power will stabiline at a hiaher l evel after the Doppler Coefficient adds sufficient negative reactivity.
- c. Reactor power wi11 stabi1 ire at a higher 1evel after the Doppler Coefficient adds sufficient positive reactivity.
- d. Reactor power decreases due to the negative reactivity added throuah the Moderator Temperature Coef ficient.
- ANSWER
- b. W. 75)
- REFERENCE DD 30 C 0700 OBJ 6 DD 30 C 0700 OUTLINE PG 10 - 11 192OOOK117 192OOBK121 i
l l 1 t 1 L___________-.-----------
- DUEELI I DN 5.24 (O.75) 11ULTIPLE CHOICE (Choose the best answer.)
What react 2vity addition is requir ed to double the count rat e 2 + Keff ic 0.98? g,, pg
- a. O.Ju15 % delta k/k
- 6. 0.500 % delta I:. / k
- c. 1.015 % delta k / l:
d.' 5.000 % delta k/k
*4NSWER
- c. (0.75)
- REFERENCE OD 30 C 0600 OBJ 7,9 OD 30 C 0600 OUTLINE PG 9 - 17 0040001;507 Oo400011608 l
l l l l
*OUESTION 5.25 (0.75)
MULTIPLE CHOICE (Choose the best answer.) Which one of the f oll owing best describes the purpose of usano soluble boron to control excess reactivity in the Rancho beco reactor core? \ v . '/ 5 )
- a. It increases the effective rod worth bv increasino the Shutdowri Margin.
- b. It result s in a less posi tive Moderat or temperature Coeffic2ent.
- c. It allows a faster loading rate f or power maneuvering at high reactor power.
- d. ]t all ows a more unif or m neutron f l w: distribution in the reactor.
*AW5WER
- d. (0.751
+REFERENEE UD 30 C 0500 OUTLINE PG 10 - 11 OD.30 C 0500 OL4J 9 19200?K105
i
+ QUESTION 5.26. s O. 75) .
MULTIPLE' CHOICE (Choose the best answer.) 0-Which one of the f ollowing. statements concerning the Moderatort
' Temperature Coefficient 1(MFC)-. correctly explains why'the htC becomes mor e negative from BOL to EOL7 w . ~/ S )
I
- a. A decrease-in the fuel to clad cap-over core ace ' resui t s; i n a drcrease an the fuel. temperature.
- b. A decrease in-the bnron concentration-over core ace ~recults in a J orge: chance in the product of the thermal ' utili:'ation iactor and the resonance escape probability.
- c. F'l utoni um bui l di ng over core _ age results in more fissionable material .being .available to compete with boron atoms f or -
- neutrons.
- d. Plutonium. building over core age causes"" hardening" of the-neutron flux which results in more fast neutrons avail able 4 or fast fission and an inerease in the iact fiusion factor.
- ANSWER
- b. (0.75)
+ RE f- ERENCE DD 30 C 0400 DN 4 OD 30 C.0400 OUTLINE PG 9 - 12
? 192004K106-u
. (;
9 L _a---._-._-----._ -.__n_-- _ . . . . - . . .
*DUEST10N 5.27 (O.75)
MULTIPLE CHOICF. (Choose the best answer.'s Which one of the f ollowino statements i s CORhECT concerni no soluble bcron reactivity control? (0.751
- a. As f 2 Esion products bui) d up, differential boron warth (PCM/ ppm) increases.
- b. As boron concentration decr eases, the di+4terent2al boron worth (PCM/ ppm) decreases.
- c. As boron concentration increases, the differential boron-worth (PCM/ ppm) decreases.
- d. As.Tave increaser,the different2al boron worth (PCM/ ppm) increasen.
+ ANSWER C. (0.75)
- REFERENCE OD 30 C 0500 OBJ 10 OD 30 C 0500 OLflLINE PG 11 - 12 192uG4K109 OO1000k528 i
l 1 i I A_________ - - - - - -
*OUESiIUN 5.28 sO.75)
MULTIPLE CHO1CE (Choose the best answer.) Over core life the reactor becomes more responsive to a 02ven reactivity change. Which of the following is the primary cause of this c h an g e':'
- a. Pu 239 increases, decr easi ng the de)aved neutron frection.
- b. Pu-240 increases, aecreasing the delaved neutron tractson.
- c. Pu-239 2ncrerees, increasing Beta ef f ecti ve.
- d. Pu-240 increases, increasing beta effective.
*AN5WER
- a. )
- REFERENCE OD 21 C 0700, OBJ 3.
RANCHO SECO REACTOR THEORY EXAM BANK ! 192OO6K124 l e I t l l l
r i i l l
*DUESTION 5.29 (O.75) l MULTIPLE CHOlCE '; Choose the best answer. )
The r eactor has just been broucht critical during a st ar t u r' . lhe power is increased to 10**-8 amps on the Intermediate Rance instrumentation for critical data. Which of the following describes what happens to the rod helant as a result of this maneuvering'?
- a. It is higher at 10**-8 amps than when it was critical to overcome the Doppler + eedb ac i: .
- b. It is lower at 10**-8 amps than when it was critical to overcome the decreased leakage at the higher power level.
- c. It is higher at 10*+-8 amps than when it was critical due to the increased consumption of neutrons in the contr el rods at the hiaher power.
- d. It is lower at 10*+-B amps than when it was critical because the reactor was actually supercri ti cal when critical was declared.
*AhSWER d.
- REFERENCE OD 30 C 0700 OBJ 5 RANCHO SECO REACTOR THEORY EXAM BANK 192OO8K110 192OOSK111 i
+ >
' +:UUES f1 Of j [5.30' ~
(O.75) MULTIPLE CHOICE (Choose the best' answer.) Whi ch of i the f ollowing best. describes a methodology. f or preventingJ;possible centrifugal pump runout-conditions?
. a.' ihe. pump has a discharge-Valve fully.Open to maintain.tne
. max i mum. f l ow f rom the - pump above.any possible runout r oridi t i on.
- l he" pump. i s- 1'ocated such the the . NP5H i s' mai nt'ai ned as cl os'e.
~
b. as possible to the-saturation pressure such that the' system. 4 head is at its manimum.
- c. ihe.' pump has.a-discharge valve throt'tled to maintain.the maximunt y f.) ow f rom the ' pump bel ow any possible runout condition.:
-'d . i tie .. pump - 1 s l ocated such the the NPSH' is maintained as' high
'as possibl.e belative-to the saturation: pressure.such that
~
the-system head is et its: minimum.
*ANSWEk
-c.
+ REFERENCE GENERAL PHYSICS, SECTION'III, PART B '
OD 30'D 1300 OBJ'3 191004K112 t 9 h__2.m__--_._._2 -m___-____m- _ . _ _ - _ . _ _ _ _ , #
s_.
*DUESTION D.31 (1.25)
In order to maintain a 200 degrees F subcooling margin in the RCS when recur:ing RCS pressure to 1600 psi a , OT5G pressure must be reduced to appro::i mately what pressure? (3.25)
+HNEWER 200 F at 1600 priq 1600 psia sat temp = 604.87 F (+ or - 6) (0.5) subcooled temp = 604.87 - 200 = 404.87 F (0.5)
S/G pressure sat temp = Tc = 404.87 F
= 260 (4 or - 5) (0.25/
- REFERENCE Stearn Tables OD 30 D 0300 OBJ 3,7 193OO3K125
) i
t ,
- i
.l :ll!
*OUESTION .5.32- (1.25) g The reactor is operating at a'therfral power level.of 2500 MW. The mass flow rate through the core is 164.X 10E6 lbm/hr, with a core exit temperature of 610 deg F. C = 1.3.
P What 'i s -the i nlet (Cold Leg) temperature to the core'? (1.2b) (0.-75 concept, u. b f ormul ati on , 0.25 answer)
- ANS'W tik O = mC ptDelta T) s o. D):
Delta T =-O/tmC ): P 2500 MW = (2b00 NW X 3.41 X 106) ,.
= 0.52b X 10 BTU /hr Delta'T G.525 X 109 /(1.64 X 10 ) (81. 3 ) = . 38. 7 &oF
- ( 0. 6 )
610' F- ' 38. 7.- F = 571.3 F. (+ or - 2) (0.25) ,
-
- REFERENCE <
,OD 30 D 0300 OBJ 3 OD 30 D 0300. OUTLINE PG 1 -
13 193007106 End of Section 5 Go on to Section 6
*u*++*************************************************+***+a+++
i .< '. U mm___.I._1_.m_ ___.._.a.-__ _
- - - - = . .
.gc '
~ ?
t >s. .
, Section 6 l Plant' Systems. Design, l Control,'and Instrumentation l
- QUESTION 6.01 (1.O)
Under what conditions would the Margin to Saturation (Subcooling) Meters not. accurately represent the subcooling in the Reactor Coolant System? . (1.0)
- ANSWER ~
The R1D.'s used'in the circuitry could.be sitting.in a voidfor a- stagnant area. -( 1. 0 )
- REFERENCE RANCHO.SECO-FACILITY EXAMINATION BANK No OBJ,' accepted.by facility reviewers.
016DOOK101
's 016000K402-
-h '
uma cpi b y m . Res gee x /a* Ps'j -
s
- r -
t i _ _ _ - . _ - . _ _ . - - - - - - - _ - - - - - - - - - - _ _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ~ - - - - - - - - - - -
- - - - - - - - - - - - ' - - - - - ' - '-- '^ - - - ^ ^^^
r- . y-a
'k
?c: E ' S is
- h.O
.m."
> , y y .. /
g;p s Q
- DUES pl Old 6.02- 4
.s;
-Concerning'Heatino and Ventilating systems:
- 5. ' What ' ccndi tion will start the Control Room HVAC System?
. ( O. b)1
'b.. What tiwo -(2) room conditions in the NSEB will . start the liSEb Essenti al ' HVAC. System? -
-l' *4NSWER c[o:O .. -
- a. +tre rr.;. ri-tb ; n J.; Cr^t ;l Nuvun ' .( O.Si b.< High.: temperature i n NSEB Switchaear rooms. '
(0.5)
*!i g : . Lwupw ate : i - ' C EI' I -~ ~ + = r t n c~ _
.5
- REFERENCE.
RAl#.HU SECD FACILITY , EX AMINATION BANK
.No OBJ.'acepted by facility reviewers.
OOOO60EA102 j 4 S O F ____._____._____m_____._.m.-.-____.m_________._m.__m____._ __.__-.__m_. _._____m _ . - _ _ _ _ _ _ _ _ _ ___m____._.___m
.i
*OUESTION 6.O3 (3.O)
The' Turbine Bypass and Atmospheric Dump systems have cper:atino biases that.are set in to relieve excess steam demand ~when certain ccnditions. exist. What are the : pl anti condi ti ons - onr1 our pone Vor.-' each of the f ollowing t. hat require the.followinn
-steam header biases?
- a. O psi g. ta.ej b.- '50.ps19 31'. 0 )
- c. 1iG psiq. t.1. O r
+ AllSWER
- a. Less than 16 */.-load, control for startup a.ndLshutdown. (1.u/
p ,. b.< Cn u.a m m . . .. 1 R ~L 1 md . p - =n+- li2*4ng s minn sm e l l. M g y=.2cres. . ( 1. O) . Ec. For reactor trip to minimize cooldown of primary system. (1.01 l
- REFERENCE CHAPTER 35'lCS - PG 35-21 TO'35-31 No 0B3, accpeted by 4acilitv. reviewers.
041020K302: 041'020K304 04102OK404~ 041020K40S' I a . jeklcf".\ u_.-- _.._-_E.______..____.__.__.__._____.____.______._._ . _ _ _ . - _ _ . _ _ . _ _ _ . _ . -.___m__.-._m__.I____ __ __ . _ _ _ _ _ . _ _ _ ._-_._I____.__.___________.____.-___..____..____.._._.___ . _ _ . _ _ _ . _ _ _ _ _ _ _ _ _ _ _ . _ . _ . _ _ _ _ _
+ DUE'S i I O!J 6.04 (2. c )
What are the f our (4) control features that the Integrated Control bystem'provides for the Main Feedwater Block valves? (2.O)
*AIJ5WER
- a. Opens the - bl ock valves when the Startup control valves are 80 */. open. - gg,3)
- b. C1 oces the bl och val ves when the Startup contrel valver ao
, ~ ~ 20 % c1osed. Os . 51
- c. Cloce when al1 four RCFs trip. (O.Si
- d. Close when both Main Feed pumps trip. (0.S)
- RE F EREl4CE CHAPTER 35 1CS - FG 35-241 TO 35-243. FIG. 35-77 No 0B0, accepted by facility reviewers.
OS9000U416 4 1 0590001.:1053 - c C
, 9 , , es - $
../!$1
~
) /
q 4 (/- { I' e-T
- 1 L -
g 8
)
)
i I I I
l l *DUESTION 6.05 (2.O What are tho +our (4) parameters / signals that are used to generate the Blu limits in the Integrated Control Systemi ' (2.v?
*MJ5WER
.a. OISG pressure. (v.$j
- b. Thot. t. O .t i
- c. Feedwater temperature, t v. N -
- d. RC's fIow. (O. M
*REFFRENCE CHAI'1 ER 35 ILS - PG 35-46 No DBJ. accepted by f acility reviewers.
016000LA02 016000K403 e
. i
Y
+0UE5110N o.Oe (1.0)
The peggino stratn supply isolation valve can be closed remotely. Why is the valve only able to be opened roariual l y? si.v)
- ANSWER To prevent t he val ve f rom being opened too + ast and causino water hemmer to occur, ti.0)
- REFERENCE RHNCHO SECO FACILITY EXAM BANI; OD 30 1 1300 OBJ 6 04 5050Ke,01 193006l:194
?
e
- - - - _ - - _ _ _ _ _ - - - _ - . . - - _ _ - - _ _ . - - - - - - - - - - - - _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - --------A
.=
+OUESTION 6.07 (2.O)
The Makeup Pump is taking suction frorn the Makeup Tank oniv. What-
-are the four factors in the Makeup and Purification System that will- ai f ect the available Net Positive Suction Head to the Mal eup Pump? (2. O )
+ ANSWER
- 1. Makeup T ank level, w. 51
- 2. Ge.s overpressttre in Makeup Tank. w.5)
- 3. . Temperature of Makeup Tank water. (0.51
- 4. Mal:eup Pump f1owrate. K! . b e
*RFFERENCE RANCH SECO FACILITY EXAM BANK OD 30 1 0600 OBJ 5 1910046::.106 e
u e j f',
*DUF:6 f1 DN' 6'. 0B ' ( 3. '0 5 .
.Recarding the..' Train 'A' Nuclear.5ervices Raw-Water System:
s a- Wnat. i s'. therprimaryfpurpose of NRW-0414-the Spr ay ' B vpas s. -
. Val ve? (1.0L Why . i sL the; Sprav.- Bypass Valve NRW-0414 mechani call y b.
interlocked with NRW-041 the-Mechanical Int er l oc k Vel ve"i ij 0)- { c. Wiiat- is the- pref erred ~ source. of makeup water to the IJ5RW system?' ' W. b) i d. 'What is the other source of' mai.:eup water to thel NSRW system?
- 10. L) '
*AN5WER '
.a. Io pr ov2 de a means of preventing f ree:ing of the Spray Pond i n cold weather conditions.
- b. Io ensure /that neither valve is wide open at the same time causing pump' runout of the.NRW pump.
- c. Ertrvice Water.
- d. Fire:Frot.ection System..
- REFERENCE CHAPTER.22 NSRW PAGE 40.
- OD 30 I';22OO OKI 2
'075000K401 4-4 0
h 4 1 i e _ _ __ _ _ _m _________.___._i_______E_________-___.m.__..__._____ _
V i I I l
- +DUESTION 6.09 (2.5) 1 Bank 4 Pressurl
- er Heater Controls for the ten groups of heaters in the bank are different t'han +or Banks 2 and 3. Assume that the controls for Bann 4 are in automatic:
- a. What will occur when the "ON" pushbuttore is depressed. ered then the " AUTO" pushbutton is depressed? (1.0)
- b. What. indications (" AUTO", "ON", "OFF" bat.l l s cht eo pushbuttons) would you e::pect to see for E heater occupe energized? t J . 5/
- ANSWER
- a. A he+<ter' group will be eriergized then deener a) :ed. -. ( 1. w
- b. AUTO - lit (0. 5 )
OlJ - )it O> bi OFF - lit (u.b>
+ REFERENCE' RANCH SECO FACILITY EXAH BANK No DBJ, accepted by fac211tv reviewers.
010000i607 010000K603 9 e ____________._m_
- OUE5 f l ul4 6.10 (1.5)
The RCP starting circuitry has several interlocks that prevent inadvertent starts from occurring.
- a. Wily must'Heactor power be less than 307. of full power v Lo
- b. Why muct Component Cooling Water flow be greater than iu/
gpm? s v. m
- c. Whv must the Reactor Cool ant System temperature be creater than 500 deg. F.? w. Si
- ANSWER
- a. Pr ecludes possibl e power excursson due to positive reactivity added by the addition of cold water from the i dl e loop. ( 0. b)
- b. Assurez propor cooling water is available to RCP motor ano s eal e. . w. 51 1
- c. Assures D/P across core will not be sufficient to cause
" core lift", i v. 51
+ REFERENCE CH. 2 RFnCTOR COOL ANT SYSTEM PGS. 2--75 TO 2-7 8.
l RANCHO SECO FACIL.1TY EXAll BANK No UR1, accented by facility reviewere. OO3000K404
. OO5000K402
\ 1 J l 1 1 I
*OUESTION 6.11 (j.O)
Why are the Saf ety Groups of control rods moved only with the.use of the au::iliary power supply rather than the normal power supp)y? tJ.o)
- ANSWER The normal suppl y i s a DC "hol d bus". It cannot move t he bat et v Groups. (1.0)
+REFEREIJCE CH. 37 CONTROL ROD' DRIVE MECHANISM RHNCHO SECO FACILITY EXAM BANK No DBJ. accept ed by f acility r evi ewer s.
OO10000A02 OO1000K403 4 l i lj _ _ _ _ - _ _ _ _ _ _ _ _ _ ._. - - _ - _ - __ E
r _ _ _ _ _ _ _ - _ i
'L *OUEST10N 6.12 (2 v)
What are the f our (4) conditions that will create a load 12 ma t in the Integrated Control Sy s t em'? (2. v's
+ ANE,WER
- 1. Los.s of a Reactor Cool ant Pump ( loss of 1 pump or 2 punio r. -
p 1 per loop). ( 0. 5 )
. 2. Lect of ei t her Feedwat er Pump. w. bi
- 3. Asymmetri c Rod + aul t. ( O . S '1 j
- 4. Gr est er than operator set maxi mum /1 oed 3 i mi t. (O. 5)
+ REF EREllCE CH. 35 INIEGRATED CONTROL SYSTEM RANCil SECO FACILITY EXAM BANK No OttJ. accepted by facility reviewers.
0160001:'402 016000K407, _ (> ~') e ' W ' " 's . "
'. 3 v- #
( r
\-
4 l I o
4 - -
,, y u
Ks [
- QUESTION 6.~13~ (2.5) m .
L ~ Ranch >Seco is operattngJin full ICS automatic at 85% unit load
- when a Reactor Coolant Pump
- in'the "B" OT5G loop inadvertent 1v trips. Assuming'a delta-Tc of..:ero.-
a.- What;i c the rati o of .f eedwater f1ow rates between the " 4 -
-and "B" OTSG's at'the end of the transient? ' . ( 1. 0)
- b. What:if. the ' final . delta 'ic at ttie end of the ' tr ansi en t !'
(0.L)
- c. What is the final unit' delta-T after..the transient? (1.0)
+ANbWER
- a. 2.44:1 ( 1,0 ) -
c.- Zero- (O.S) c.- Appr ox i mat el y 50 deo. F 445 to 50 deo. F acceptable) (J.0)
*REFEREf4CE CH. 35 INTEGRATED CONTROL SrSTEM FG 35-309
' RANCH SECO FACILITY EXAM BAllK No DBJ, accepted by ' + acili t y revi ewers.
OOl60VOK402 f l OOi60001:l403 t End of Section 6
.Go on to Section 7
+++++-*++++***++****-+++***+****++***+*++++++++**********++++*+++++
l. L___l___:___.__, _ _ _ _ _ _ _ _ _ _
1 s Section 7 Procedures - Normal, Abnor mal . Emergencv. and Radiological Control
+00E STIOld - 7.01< (1.5)
The Reacter is in Hot Standby. Procedure B. ;; bection S " sp p r o rs c h to Criticality" in being uced.
- a. Whet i s the minimum amount Group 5 must be withdrawn to.
al J ow crit 2 cality ? t o. b)
- b. When in " Criticality" indicated to have occurred durino a Reactor startup? (1.0)
- ANSWER
- a. 2 0. (0.5)
- b. " Criticality" is indicated when Reactor power level (1.0) conti nues a relati ve constant rate aster al] posi t a ve reacti vi ty addi tion has been stopped. (CONCEPT)
+ RE F ERE NCli PROCEDURE D.2 PG 36.
DD 30 J 0100 OBJ 2.3 0010004106 e w__..._ _ _ ..-. .
r
+ DUES 110N 7.02 ( 1. O)
A notc. f or Step 5.2 of procedure B.3 " Normal Operation". Contrel Rod Operation Guidelines' states that there are no restrictions placed on the rate of - movement nr the distance of travel of the AP5R's for the first 310 days of the cycle 7 fuel load. What al1ows the APSR's t a be moved in this; fashion? (1.vi
*4NSWER The APSR's are " Grey" and are designed f or mi ni mum del ta 6:w/ 4 t changes durina rod movement. f,1. 0 )
- REF ERENCE PROCEDURE b.3 PG 13.
DD 30 0 0100 UBJ 2,3 000003G003 e
*DUESTION 7.03 (1.5)
Why does Procedure D.9 " Soluble Boron Concentration Control" tia , e l the operator determine the contracted inass of the Reactor Cool an t S yst em at the temperature the Reactor Coolant Pumps are stepoed rather then at the finel cold RCS temperature? s1.5i
+ 4taSLJCR With the pun'pc_, stopped there i s i nadequate mi >t i rio ( 1.
- 0 , t h i r, presents the hazard of a dilution accident (0.5s.
+REFERENCC PFUCEDURE B.9 FG 5.
Los 39 J 0100 OI4J 2 G0100O'sr 1 (fJ l
') i
+ DUEST I OrJ 7.04 . ( 1. Of Prior to filling the RCS, the OT5G 1evels are required to be at BL*/. on the operatino r ange per procedur e Lt. 2, "Pl ant Heatup and Startup". What i s the basi s f or this requirement? s1.vr
+Hl45WER Asettrec ihet - the Tube to Shel1 differential t emperatur e 2 c 90 t hi n al l owabl e limits ~during the filling and ventina of the RCS. (3.0)
*REFEREl4CE B.2 FG ";
OD 30 J 01v0 OBJ 2 0350101.109 03tiOOOGO10 4 0
.g.
r, .. S ' :p s -
*OUESTION- 7.05 (1.5)
Procedure B.3, " Normal Operations"' states-that'it is' desireable" to. maintai n the contro111ng L group ~ of CRA's from.93 to 97 percent withdrawn. What are three.(3) of the four reasons for this positioning of CRA's?. (1.5)
- ANSWER
' 1. To provide adequate Tave control..
2'. Results in relatively uniform fuel' burnup..
- 3. Even flux di st ributi on - mini mize imbal ance.
- 4. Rods slightly inserted gives a more rapid response lfor.down--
power maneuver (i . e. runbacks). Any 3 9 (0.5) points each
- REFERENCE PROCEDURE B.3 OD 30 J 0100 OBJ 2 OO1000k506
. _ _ _ _ _ . _ _ _ ~ . _ _ _ . _ _ . _ _
Ic'E , { .
.c:
p - m
- OUESTIOk
~
r,. 7.O6 ~ L.('1. 5 ) ' ,
.An. uncomplicated Reactor trip has occurred. The planthis .beino ~I cool ed down .and depressuriz ed. - What three -(3)' condi ti ons. woul d have.Kto verified to allow you - to isolate the. Core Fl ood t eni.:c ?
i i '. M i
- REF EREf1CE ,
1 '. ' Eubcool i ng exists. ' o,. 5 / L e2. ' RCS. depressuri::ation : i s being . " control l ed" . ; ( 0. c.i > - 'l J. RCS pr ensur e. is 'below 700 ps2 q. f - go.p> 1 1
' L *REF Ei!ENCE i PROCEUllRE CP'.104 l OD,30 J'0200'OBJ 2 OG6000K103, t
( f' lb'Y . OUCfYIVl- -j r{ Jo Ccw l S 6 ! a
$8 4 .
1 l I
.i
i l-p-
- QUES 110N 7.07 (1.0) l When responding to Emergency Operating Procedure E.01. en operator is required to throttle letdown flow down to 40 ppm. Whv is this action required rather than isolating the letdown +10w?
ti.v)
*4NSWER Thic reduces the possibility of a letdown cooler tube leat 4 rom thermal cycling of the tubes in the coolers. ( 1. v)
*REFERE!4CE 14$:W Letier 1/1Bi83 RS-83-004 Ob 30 J 0310 OEtJ 1 OOOOO /EK301 l
1 e . _ _ . _ . . _ _ _ . _ . _ _ _ _ - _ _ . _ . _ _ . . . _ _ _ _ _ _ _____________.m _ _ _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ . _ _ _ _ _ _ _ .._.______._________._.______.__.____._.______.._____..._.______m_
r-
+0UESTION 7.08 (1.5)
An OTS5 tube rupture event is in prooress. Emergency Operatana Procedure E.06 "St eans Generator Tube Rupture" has been implemented. What are three (3) of the four instances that woule allow vou t o steam t he at f ected OT5G? (1.51
- ANSWER
- 1. Io mai nt a2 n (fiSG presture be) ow 1000 psio.
- 2. <381 inches in the 015G.
- 3. 'To proainte er establish natural ci rcul at i on.
- 4. Maintain ~ lube to Shell delta T < 100 deg. F.
Any 3 @ to.5) each
- REFERENCE PROCEDURE E.06 OD 30 J 0360 UL4J B OOOO38EKJ.06 I
4
+ 0 U E 5't I O N 7 . O(? (1.0)
One of the criteria of " Excessive Heat Transfer" Erner g enc v Operat ino Procedure E. OD i s a decr ease in Tcc1d of greater tnan or caual to SO deu. F for a transient when lave in less than bbn dco. F. What is the intent'of this critersaY (i . 0)
+nubWEP Thit i c 't o ensur e that excessive heat transfer events that ar e.
Other than "at power" transients are addressed. (1.v)
+REI.ERENCE PROCEl>i. IRE E. OS PO 2.
Ob 30 J 03*'O Obd 7 00004000Ji O O O v 4 0 W ,1 2
'l
[
+DUEEIJON 7.10 (3.o)
Per i od2 cal' l y throuahout all of the Emergency Operating Proteaures gui denr.e i n provided on the information pages regarding the ver i f i c ati orr of natural ci rcul ati on condi ti ons. What are.the thtee verification criteria? G;. . O >
- ANSWER I
- 1. Tcolrl and OlSB Tcwt. approximately equ al , i. J . 0 ,'
d
'. Incore Thermocouple temperature withi n 1v decree,F a+ 'i h o t .
s1.W
- 3. U~lbG oressure decrease causes Thot, Tcold, and incore t hermocoupl e temperat ur e decreases. (1.0)
- REFERENCE PROCEDURE E.05 INFORMATION PG I OD 30 J 0300 OBJ 5 000056G011 000056G012 I
e
I
- QUE511011 7.11 (1.0; Fo]Iowing a loss of Offsite power event it is determinea that natural circulat3on has not been est at>1 i shed. Why'does Fule 4 "OT56 Level Setpoints" require that the level be set to 581 inches on EF3C H2ch Range? (1.u/
*Al45WER f a rai se the cent roid of the heat sink to induce natur al circulation. (Concept) (1.0)
- REFERENCE '
RULE 4, OD 30 J 0380 OBJ 1
- - rj. I [ N " N
[ 000056G012 g gg hg gG2 i O
l *DUEETION 7.12 (1.0) Following an evacuation of the Control Room due to a' fire, the operatore are procedurally required to establish an alternate recirculation path f or the HPI/MU Pump. Why is this path r equi rec , icr t.hi s everit Y ( 2. Of I
*A!JSWER This al1 ows corit A nuous operat2 on of the HP1/MU pump. t i . i..* )
- REFERENCE C.134 & H EVACUAllON OF CONTRUL ROOM DUE'10 FIRE l rat lC.110 SECO ' F AC ILI T Y EXAM BANK '
UD 30 J O200 OBJ 2 OOOO68GU12 OO4000i:.405 i I 9 l i
l I l 1 1 [- i
- QUES I 1014 7.13 ( 1. O) 3 I I Protecture E. 07, "lnadequate Core Cooling" has, been i mpl ementea .
and the plant P/T pc. int has entered reoion-3. Why are all oi the hiah point vent valves opened at this time? tl.O>
- ANE;WE F<
The ventu at e opened to reli eve non-condensib) e cases, f r et.) tr e hot 1eos thet could prevent netural circulation from occtrrino. tj.>>.
- REFERENCE E.07 144ADEDUA1E CORE COOLING OD 30 0 0370 OL4J 7 j OOOO/4G011 "
OOOO74G012 0020001104 I 1 ( 4
.i
, ~ ~ ~ _ - - - - - - - - - - -
*OUESTION 7.14 (1.0)
Why is increased letdown required f ollowino termination of an overc.coli no transi ent during which HPI was initiated? t1.01
- ANSWER Reheatitio of the RCS by decay heat will cause the primary coolant to swell, possibly causing a solid p r essur i::er and/or over pressure eorida ti on. si.u)
- REFERENCE E.05-4 EACESSIVE HEAT 'IRANSFER i R4HCHO SECO FACILITY EXAM B ANF.
OD 3.0 J 0350 OBJ 7.8 OO6050A101-A
I_
+DUESTION 7.15 (1.5) f Conct'rning Procedure b.2, "Startup Procedure':
- a. What -1 s the minimum required overl ap bet ween the Sour ce and Interm**diate Range e>:-core nucl ear instrumentation? (6.5)
- b. What is the maximum transient Etartup rate allowed? ( 0. N
- c. What is the maninium dei ta-T between Main Feedwater t emper atur c+ and 01SG 1ower downtomer temoeratureF *v.Si l
- At JSWER
- s. A mi t ei rnum of one decade overlep. iv.b>
- b. 1. 5 DPt1 0 $. 5)
- c. Maximum delta-T is 350 deg. F. (0.01
- REFERENCE S.2 STARTUP PROCEDLIRE RANCIIO SECO FACILITY EXAM BANK DD 30 J 0100 OBJ 2 015000A102 015000 A10.5 O
t i l i i
*OUESlION 7.16 (2.0)
Rule 1, " Initiate HP1" requires that HPI be inattated whene.'er Subcooling Margin is lost.
')
- a. What ot her- conditi ons ' require that Hi'I be i ni t i at ed ;. (1.0)
- b. Whv is.it necessary to ensure that lWO HP1 pumps are runnino at full capacity when the Subcooling Marcin is lost ~: t).0)
- ANSWER
- a. O~i Sb heat transfer is lost and Feedwater is not. availab)e bef ore RCS pressure reaches the EMOV set point s24SO pu g).
(1.0)
- b. Running two HPI pumps ensures adequate core coolina because the actual RCS inventory is not known. (1.O)
- REF EFEllCE RI.l!. E 1 AIOG PART 11 - VOLUME 1 CHAPTER E RANCHO SECO FACILITY EXAM BANK DD 30 J 0380 OBJ 1 OO6050H102 9
l
- DUEM IDN . 7.17 ( 1. O )
What is the reason for the limitation of 10% per hour power increare between OX and 20% of full power? (1.01
'
- ANSWER lhis assunieb that there are pinholes in the cl6dding of the fuel allowing water into the fuel pin. A fast heatup coul d flash the water to sieam and cause excessive siress and tpobc2bjv a r er:t ur e of t.he pin). '1.vi
+ REFERENCE B.2 NORIisL PLANT OPERATIONS RANChu SECO FACfLIlv EXAM BANK ;
OD 30 0 010v OBJ 2 j 002000M106 OGa.>OOl:.613 O l
I a
+0bESTION 7.18 (1.0) i A loss, of Makeup has just occurred due to a trip of - the Mal: cup l p ump- from an electrical fault. Va've J SFV-23616, " Seal Inject 2on l Isclation Valve" has been closed manually. Why must the special precaut i on of slowly increasing the ilow be usec in the restoration of seal injection? O .'v ) + 4145WER Festote sl owl y to avoi d ther mal shock and'the subveauent camnae of seal parts. (1.01 *REFERENCF C. 9 L ov.s of Reactor C, col ant Makeup / Letdown OD 30 J O200 OBJ 2 0030000001 1
I i I
n
+DUEST10N~7.19 , (1.0)
A' reactor tr'ip.has occurred from a temporary loss.of of f si te power . toffs.1ie power has'been restored)"and indications eksst thatl Primary-to1 Secondary heat: transfer hau been lost ano the Primarp.ic saturated.,;you have entered E.04 " Loss Heat'1rancier*. Why 'must. OT5G saturati on temperature.be 40 to'60 deo. F' lower than' incore Core ExitEThermoccupl e (Incore T herruccoupl e)
'temperatu' re. when L5 umping an RCP to rectore heat: transf rar? ti.ui
+ iil JEWER Pressurizer ~outsurge will occur when the' steam voids in the
; Reactor' Coolant; System collapse. (1.0)
. + REF ERENCE E . O' Loss ~of Heat Transfer PG 10 -
DD-30 J 0340 OBJ 7
-OOOO36 GOO 7-OOOO56GG11 000056G012
-- {.
ggw 1- cm - h
/
4 c ,~, 'j . 3 ,
~
__ ~ 1, ~jg,. ." ~- '
--jy- *" ' '
.) ,n .
,.i j
b End of Section 7 Go on to Section 8
- m m *++++****+ m ****+******************+********+*+-+*****+++* g l
l 8
.-__--_---____--__-_-________-__-:--__-------_----------_-------a .
I i 1 1
- l. i i
Section 8 Administrative Procedures, Conditions, and Limitations
- QUESTION 8.01 (2.0)
Technical Specification 3.1.3, " Minimum T emperat ur e f or Criticality" requires that the reactor remain subtritical by at leant 1 ".. d el t a k/h until a bubble is f ormed in the Pressuri:er.
- a. What range.cf l evel must be present in-the Peensurt er to sati s+ y the LCU? (i . 0)
- b. What is the basis for the requirement to establish a bubble prior to criticality? (1.01
*AIGWER
- a. Between 10 and 316 1nchen. i1.vi
- b. To assure that the RCS w2ll not aosolidhn the event oi a rocwithdrawalaccident), t .i . O )
+ REFERENCE
'i . S . 3.1.3 Ob 30 J 0600 ObJ 3 ,,
vo2OOOK407
. OO2OOOG105 OO2OOOG106 l
1
+ UlliiS T 10!J 8.02 s1.o)
The reactor is at 100% of full power when a regulating roc' hat become mi sa12 gned resulting in a Quadrant Power Tilt of 12*' . Action to reduce reactor power must be taken to bring the L/P t to with2n 4.92%. By how much must rescior power be reduced? iJ.or
- ANSWE.R Priwer must be reduced by 2% for each 1% above 4.92%
(12% ~ 4.92%) X 2= 14.16% (or G5.84% of full powers ( J .Os
- REF EFE14CE 1.S. 3.5.2.4.B UD 30 J 0600 GBJ 3 001000%O0%
001OOOi,006 f I I l
I-
+DUEST10N 8.03- (2.O)
A channel check munt be done on the Containment Area High Ranoe Mon 2 tor at 1 s o s,t once every sha4t (onee.every 12 hours). Eeme e::tensi ons of the basic interval are allowed by the Technical Spetif) cations. Surveljlance records show that these checks were done on: December 7 at 0100 December 7 at 1600 December 8 at 0100 December 8 at 1500 Decembet- 9 at 0600 When i e the _ ne::t channel check survei11ance due to be perior meti AT T HE LAT EST? ---> Show how you derived the time! (2.0)
*ANSWEH Ma >: i nter val ior 3 survei11ances is 36 + 12(O.25) = 39 hourc 12/8 0100 to 12/9 0100 in 24 hours. to preserve 39 hour interval ne::t check muct be done by 0100 + 15 hours ( 1. w lhe answer is 12/9 1000 (i.O's
- REFERENCE T.S. 1.9 and TABLE 4.1-1 OD .30 3 OBJ 1,3,4 072000G010 4
l l h _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ _ _ _ _ _ _ . . - _ 5
~
1
+DUESTION ?.04 (1.5)
You are filling the position of Shift Supervisor during Loid Shutdown.
- e. What ether posi tions ar e requ2 red by the Technicel Specifications to be manned under these conditions? (1.9)
- b. If a et: ember of the required crew complement becomes incapacitated, how much t i ene is a31otted for the cesioneted r epj aceinent to report on si te r 50.57
+ wi ju Wi- H
- e. 2 li censeri RUE (Ass 2 tant CD's) and 1 non-12 c ensed opt-r et.or .
(1.0)
- b. 2 houre. (0.b)
+ RE F EI,:EiKE I.S. 1AEtLE 6.el DD 30 J 015 5 194001A109 1
1 4 i j
+ 0UE 5110lJ S.05 (3.0)
Reoarding Administrative Procedure AP.44, " Safe Clearance Pr or eottr e" :
- e. Who is responsi bl e f or determining i f SFAS Independent Vers 42. cation is required for a clearance? ( J . v .'
- b. If the boundary for a clearance :_ennot be drained or .entr d what action must b e t a k en'i' ', J . u )
- c. Whett two actions must be undertaken f or those clearancer that base been outstanding f or 30 dayt or more? (1.0)
+ nNE.WE R
- a. Sh2ft Supervicor (or desi gnated representative . (1.O>
- b. 4-Caution tag must be hung on the applicable boundary tvelse body, flange, etc.) 13.0)
- c. 1. A review for applicability. (v.S)
- 2. And a physical verification. O> . 5 i
- REFERENCE PROCEDURE AP.4A PAGES 13, 19.
OD 30 J 0800 OBa el 194001K)OJ 194001K102 e e __ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ ---...s---
( j' l l
*OUESTION 8.06 (2.O)
Pr ocedure RSAP-bO7, " Change Notices to Procedures" describes the methodol ogv of' making changes to procedures. In this procedur e there are si:: specified changes that effect the, intent of a pr ocr clur e or procedural step. _ What are f our (4) of the sir: changes t hat could chance the i nt erit of a procedure or procedural step? 12.9)
+ANEWEb
- 1. A ctsantie to the acceptance criter l a
- 2. A change to the li mi t >:., and precautions.
- 3. Del eti on or change of any step w2tn a speci+ied accentente criteria.
- 4. Deleti on or revision of USAR requirement.
- 5. Deletion or revision of 1. S. requirement.
- 6. De1 et i on o- revision steps, subsectson, or sect 2on implementing a commitment document.
Any 4 at (0. 5) each.
+ REFERENCE RSAP-SO7 PAGE 3.
UD 30 J 0800 OBJ 2,4
. 194001A101 O
l i
p1 !- . c 3; d
*QUESTIO!4 8.'07 tl.0)
Special Order #38-11 specifies the operator good practice coricorn2 ng reposi ti oni ng of valves during the performeince o+ clearances and lineups. What is thic good practice? $ 1.v'
*ANEWER The Supervisor choul d give the oper at or speci fi c gu2 dance cri wh e. t to do if a val ve is not in the required poc52 tion. i J . ' ' ;-
+RErEPENCF SPEC) AL ORDER MH8-11.
OD'30 J 0800 OftJ 4 194001 Al%: ) I 4 e
l
+ DUE S T I Di'J 8.OB (2.O)
Spectal Or 6.r #88-37, "Use of HP1 Subsequent to Reactor Tripr'- ditcusses the Actions that were taken for the reactor trip c1 Auaust 6, 1988. During this trip the operators utilized all four HPI i n .i ec t i on no::l es to min 2 mi ne the pr essur i zer l evel d ec r c-a s e. Under AP.28, " Post Trip Transient Investigation. Assessment. end Reportinp" the event was classified as a ~Iype 1I event because of the use of all four no::les.
- a. Whv was the use of all four HPl no::1es not al1 owed 4 or tht>
conditions of an uncomplicated reactor t r i p'r 11.0)
- c. What is t he dif f erence between a tvpe 11 and a Type 1 event ?
(3.0)
- HilbWf; P
- a. It causes unnecessary thermal cycling of the injection no::1es. ( 1. O )
- b. the type II event r equi r es an investi cative t eam to review the event end determine'if corrective atti ons are needed.
For a type I event, a Shif t Supet vi sor can recommend a rectcet without a revi ew. (1.0)
+F F f- FRFijG AF.2d. 1:iF E CI f)L ORDER h88-3) .
OD .f.0 J 0000 OBJ 4 190001A102 S 4 (__. _ . . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ . _ _ _ _m._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .
+uuESTION 8.09 (2.O)
What is the. color of each of the following couipment control 1 t ag n ~P
- a. C l eer e.nt e / Darin er ' O. ..Li
- b. Abnorms) (0.br
- t. T e s.t u.. . L >
d, Cauti on e i s. 5)
+ A145WF.R
- a. Red t0.5)
- b. Blue O> . S )
- c. Green iO.5)
- d. Yellow OJ . S )
- REFERENCE AP.4A,4B,4C DD 30 J 0000 OBJ 2 1940v1K102 4
e
E l
*DUESTION. 8.10 (1.0)
What i s the purpose of the Abnormal tag? ( 3 . .> r
- ANSWER 1he t ea 2 denti fier an abnormal cond2 tion in an operating pjent system without a drawing change.
- 1. W
- +REFERENC.E AP.26 PG 2 OD 30 0 0800 OBJ 4 1940011:102 h
e ___.-__._m_m____._ _ _ _ _ _ _ _ - _ _ . - _ _ _ _ . _ . _ _ _ . - _ _ . _ _ _ . _ _ _
L r
*DUESTION 8.11 (1.5)
. Procedure RP.305-7, " Area Definitions and Posting" defines t n o r,e areas of radiological concern which must be posted and estab1ished.
What ar e the def i ni ng condi ti onr, f or the.fol)owing areas. per R P , 3 0 5 ~/':
- a. Radiattors area o... f. )
b.. High Radiation Area (9.b)
- t. Secured Hiph Radiation Area v.> . 5 ,.
*HNbWER
- a. > 2.5 mrem /hr < 100 mrem /hr (0.51
- b. > 100 mrem /hr < 1000 mrem /hr (v.Si
- c. > 1000 mrem /hr when measured at 18 incher, ( 0. 5 )
REFERENC.E RP . 305--7 OD 30 J 0800 OBJ 4 1 9 4 0 0 1 1-: 1 0 3 9 l--.-- . - _ _ .
t. 9_G
+DUESTION B.12 (2Ari 10CFRSO.72 describes the NRC. reporti no requirements. Generallv there are (3) categories of events. each with a time period within which a report has to be made to the NRC.
- a. What are the two reporting time periods associated w2th there evc+nts? i .v)
- b. When do the reporting time " Clocks" for these periods t t ar t
- 4s
- c. How would you directly inform the NRC? (e.b)
- ANSWER
- e. 1 hour and 4 hours. (1.Of
- b. When facility management "should have known" (i . e. at the t i rne of discovery by the person who discovereo the event or condition). M'
- c. By pickina up the " RED" phone in the Control Room. (0.b)
+REFERENLE 1 O C.F H 5 o . ? 2 JOCFR Lesson Plan Ob.iectsve 194001Alu6 L _ _ _ _ _ _ _ _ _ _ _ _ _
- QUESTION G.13 (1.O)
The plant is in Hot Standby when the following information is turned over to the on-coming Shif t Super vi sor : 1.8 ppm - leakage past check val ves f rom RCS to both Core F3 cod Ianks (O.9 GPM ea.) 1.2 gpm - Primary to secondary leakage (total) with RC5 att i vi t y of 0. 2 uCi /gni of 3-131. 4.8 onm - Iotal RCS leakage 15 (1pm -- Leakage f r om Reactor Coolant Pump Seal s What RCS leakage or other limits have been enceeded? (1.0)
- AIJ5WER Ihe l eakage j i nei t s f or unidentified leet: age of greater than j 6Pn hos been exceeded. (0.5)
Arid the 1. 2 opm pri mar y to secondary i s its excess of 500 aallons per day. (0,5)
+REFEREl4CE Trechrei c a l Speci f i cat i ori 3.1. 6. 1.2.34 OD . 30 J OcaOO OltJ 1.,
OO2020G011 002000G005
, OO2OOOK.405
,. . _ _ _ . _. . _ . . _ _ _ _ . _ - - - _ _ -- - - - - _ . - ' - - ' - ^ ^ ' - ^ - - ~ - - ~ ~
- DLIESl I ON 8.14 (2.O)
The Rancho Seco Technical Specification require that the the Core Flood larets be operable when RCS pree.sur e i s above 800 ost o. What are f our (4) of the five conditions required to be verified to e at i E4 v thi s requi r emerit? VHLUES ARE NO1 REQUIRED, on1y i he parameter need be li sted. (2.vi
+ W JEWER
-' I sol at i on valves open
- Water vol ume
- Bor on cotitentrat2on Cover pressure
- Pr es,sur e instrumentation op er abl e Lany 4. O.5 each]
+ REFERENCE lechnical Speci f i cati on 3. 3. 3 OD 30 0 0609 OBJ 3 vobu2060uS Que,000 GOO 5 (7 h 3 h gc,(g(~.7 C 09 A '
S*}
. _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___--____a__ _- -
m 4:
*OUESTIOld 8.15 - ( 1. O) -
What must be done by a licensed operator to maintain his/her license .in; an " active" status per ;the regul ations of '10 CFR Sb .
" Operators Licenses"? ,
(1;0)
- ANSWER IThe operator shall actively perf orm the f unctions of the appropriately' licensed operator on a' minimum of seven 8-hour shif ts . or. fi.ve 12 hour shi f tu ' (O. 5) - per calendar' quarter tO.51.
- REFERENCE-19 CFR 65.53(e) 10CFR Lesson. Plan Objective
'1'i4001 A103 : -)
.j-i i
l i .- r i I 1 s lx 1 I 1 i End of Section B i End of Examination '
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