IR 05000309/1988013
| ML20154Q535 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 09/23/1988 |
| From: | Eselgroth P, Norris B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20154Q533 | List: |
| References | |
| 50-309-88-13OL, NUDOCS 8810030431 | |
| Download: ML20154Q535 (142) | |
Text
{{#Wiki_filter:_ _ _ _ _ _ _ _ _ _ _ _ _ _ _. _ _ - _ _ _ _ _ ! , i U.S. NUCLEAR REGULATORY COMMISSION. REGION I OPERATOR LICENSING FXAMINATION REPORT , i
EXAMINATION REPORT NO.
50-309/88-13(OL) FACILITY DOCKET NO.
50-309 FACILITY LICENSE NO.
OPR-36
' LICENSEE: Maine Yankee Atomic Power Company l 83 Edison Drive ' Augusta, Maine 04336 FACILITY: Maine Yankee Atomic Power Company EXAMINATION DATES: August 8-11, 1988 [ u CHIEF EXAMINER: . OM l
/S. Norris Date' - Sen r Operations Engineer l i i ,/ \\ APPROVED BY:
. 9-25'-8 i pew r W. Ese Myoth, Chief D' ate PWRSectionfdperationsBranch,DRS ' i
l SUMMARY: Written and operating examinations were administered to two Senior , l Reactor Operator (SRO) and five Reactor Operator (RO) candidates. One of the ' i SR0s failed the simulator portion of the operating examination, all others . passed all portions of the examinations and were issued licenses.
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0810030431 800923 ADOCK0500g9 i DR i .. -_.
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- - - -- , DETAILS TYPE OF EXAMINATIONS: Replacement EXAMINATION RESULTS: E R0 E SR0 l I l PASS / FAIL l PASS / FAIL E E E E Written E 5/0 E 2/0 E I E E E E E E E Operating I 5/0
1/1 E I E E l E E u E OVERALL E 5/0 E 1/1 I I _I E E CHIEF EXAMINER AT SITE: B. S. Norris (NRC) OTHER EXAMINERS: R. B. Eaton (NRC) L. J. Defferding (PNL) R. L. Gruel (PNL) 1.
GENERIC DEFICIENCIES: a.
There were no generic deficiencies noted during the administration of the operating examinations, b.
The following is a summary of generic deficiencies noted from the grading of the written examinations.
This information is being provided to aid the licensee in upgrading license and requalification training programs.
No licensee response is required.
Reactor Operators (1) The ROS were unable to describe how the ability to transfer heat across the rod gas gap would be affected by various changes to the fuel assemblies.
(2) The R05 could not explain how to prevent an uncontrolled cooldown in the event of a loss of all A/C electrical power.
Additionally, the R0s could not list the four actions required to locally start the AFW pump.
(3) Neither the R0s nor the SR0s could list the two actions which need to be taken immediately after reenergizing the instrument busses DP/IAC and DP/ PA _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -. - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ - _ _ _ _ _ _ _ _ _ _ - - - _ _ _ _ _ _ _ _ _ _ _ _ (4) Neither the R0s nor the SR0s knew the emergency radiation limit to repair plant equipment and prevent further plant degradation.
(5) The SR0s could not describe the resultant plant actions if a second pressurizer pressure channel fails high during a plant cooldown.
3.
EXAMINATION REVIEW a.
Written Examinations The written examinations were reviewed by the training staff in two parts.
Prior to the administration of the examination, they were reviewed for technical accuracy, applicability to the Maine Yankee facility, and assurance that the answer key was consistent with the question. On the SRO examination, fifteen of the forty-six questions were changed as a result of this review; on the R0 examination, eleven of forty-seven questions were changed. As can be seen in Attachments 1 and 2 (SR0 and R0 Written Examinations, respectively), most of the changes were minor in nature: terminology, or addition / deletion of a word or phrase for clarification; some questions were rewritten to better reflect the actual responsibilities of the operators at Maine Yankee.
The new questions were retyped and the pages were replaced in the examinations before they were given to the candidates.
The examinations, as attached, were modified to show the original question and the question after being changed.
After the examination was started, the written examination answer keys were reviewed by the training staff to ensure they were technically correct (see Attachment 3 for the facility comments).
The NRC response to the comments is contained in Attachment 4.
b.
Operating Examinations The scenarios for the simulator portion of the operating examinations were also reviewed by the training staff prior to being administered to the candidates. Again, only minor changes had to be made to the scenarios to stay within the capabilities of the simulato,,. _____- 4.
EXIT MEETING: a.
Personnel Present at Exit Meeting: NRC Personnel R. Eaton J. Lanning Facility Personnel M. Evringham M. Schwartz J. Kirsch R. Dee J. Weast b.
Summary of Comments Made at Exit Meeting: (1) The NRC stated that the simulator did not have the ability to override the auto start feature of all of the pumps on the control boards.
(2) The facility expressed appreciation for the opportunity to review the examinations prior to adidnistration.
They felt that the overall examination process was improved.
(3) The facility stated that they noted a significant improvement in the area of open ended and double jeopardy questions; however, they expressed concern that some questions on the examinations are beyond the scope of the Examiner Standards (see Attachment 3 for specific comments).
Attachments: 1.
SRO Written Examination and Answer Key 2.
R0 Written Examination and Answer Key 3.
Facility Comments on Written Examinations 4.
NRC Response to Facility Comments 5.
Simulation Facility Fidelity Report
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3.
irrLEAR n rmu;. ATCFY COMMI5510h
- cNIUh rd. i,L I C R oft.tu4tOh L 1 CENSE EM4IIINA FIUM FACILITY:
_L1Glyg_16dLEE__________ _ FEACTOR TYPE: _ E W B ; G E..._.. _. _ _ _ _,. _ _ _ DATE ADMINISTERED:,5@L@@(gi____,.,____,._____ EXAMINER: _QPUEL1_ Fu _ _ _ _ _ _ _, _ _,,,, _ _ _ CANDIDATE: I _ _ tR I.,.. *r. _ _ _ ,, jf s., _., IN51EuCIlgN3 Ig_c60019eIst Ucs rocarate peorr ice the answert.
Write answere on cno vice univ.
Stapte ouestien sneet en top of tne answer thcets.
Foints tor eacn uuettaen ar e incicatec in parenthetes after the ouestion.
The passino graao recutros .a t lucut 707. in eacn category and a final grace of at luost 507.. En6mination papert will be packed up stu to) hourc after tho enamination starts.
' '. OF l CATEGORY '.. O F CANDIDATE'S CATEGORY l __20LWE_ _I9Ie6 ___EG95E___ _VeLUE__ ______________G6IE99BX_____________
- 92 99-_ _ EEs.90
______ 5.
THEORY OF NUCLEAR FOWER PLANT ~ _ _ _... _ _ CPERATION. FLUIDS. AND THERMODYNAMICS l l _E5 2.@9_ .? E.99 _______e>. FLANT SYSTEMS DESIGN, CONTROL.
_ ____ __ _ AND INSTRUMENTAT101.
_E92.dO_ _EL.9Q 7.
FROCEDURES - NOFMAL. AbNDRMAL.
________ _ _ __ EMERGENCY AND RADIOLOGICAL CONTROL _S$2.09__ EEs.00 a.
ADMINISTRATIVE FROCEDURE5.
. ___ __ _ _ _.. _ _ _ CONDITIONS. AND LIMITATIONS 100s.00__ ____..'/. Totals _ _ _ _ _ _ _. _ _ Ftnel Grace 'All work cone on this enamination is my own.
I have neither given nor enco1ved ato.
_____ __ _ __ _ . __ __________ Candidate's signaturo - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
s n - I d E 0 6 1 _ 9 3 _ U U g L E e B _ E G y E O. E 6 6 H I _ g E S E g I l O b,._ Ei U 1 9 5, _.@ d D PAGE EUEECODIbed1Ch CUESTION 5.01 (2.00/ >v6WF.R TRUE er W< LEE to the f oll owi no: a.
Helving the reactor period will double the 5UR.
(0.5) b.
If reactor power in increaneo from 1% at a stable EUR of 0.3 OFM. pcwer will be at 5% in one minute.
(0.5) c.
It will take the uomt> time io-the reactor to go f rom 2% to M. powar as it will to go trom 25% to 50% power with the same constant EUR.
(0.5) d.
If a posi tive reactivi ty addition to a critical reactor results in a 1.0 DFM posi tive SUR. the same amount at negative reactivity addition will result in a 1.0 DPM negative EUR.
(0.5) 564 ** CATEGOhr OS CQt4TINUED ON NEAT PAGE 6644*)
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .. Te..._IUt0ELDE_UucLEOS_E0k!L'E_ELOUI_0CE601190s_ELU1Dh 000 Ff GL UmE599YUOMIcs OUESTICN D. 02
- '. 50 )
(14 t h r# v ann ee is in hot snutdow w2th a neuteen countrAte ot 400 cos and a coron conc.ntra+ an c4 :200 pom.
.i r e c e. t i v i t., int,rrt1on at l '/. r h o r e s.u * 5 n a shutdown maronn (tDM.
0+ 7,%. c.
CALCULATE the new c n rate.
SHOW your work.
(1.5) b.
STATE WHAT (if a) acti s must be taken immediately.
(1.0) QUESTION 5.02 (2.50) Maine Yankee is in hot standby with a neutron countrate of 400 cps and a boron concentration of 600 ppm.
A reactivity insertion of 11 rho results in a shutdown margin (SDM) of 31.
a.
CALCULATE the new countrate.
SHOW your work.
(1.5) b.
STATE WHAT (if any) actions must be taken imeediately.
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idb b.UUl*1LlBi%LOE UUE5T1CN 5.34 (2.00) For aaen at the factors lantec colow. DOE 5 *hc mocefrotct'
- smner+<ture ecoff1ctent bc.come r;0RE NEGsTIVE. LE55 teEGAT I VE. or REl%IN THE SAME as the paramoter as caanced 2n t he di rect 1 on decer1 t,ca'
ASSUME normal pcwor cenattaons.
a.
cos) int tumperature accreases.
(0.5)
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newer increasea (0.5) t.. caro aces (0.5) o, centrel rods are utthcrawn (0.5) , t64*** CATEGORY 05 CONTINUED ON NEXT PAGE o4*se:
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HXh09DYU0019S Alt.5110N b.de (0.50) ANSWLF. the tollowing vestions regarcing plant response ic! ! cwi no. e cat t er te o atter an r,tenced peger occretton.
4.
R o a r.t o r power immedt toly (witntn one second) crops to a certain value.
1.
To WHAT value does eactor ow-r drop? (0.5) 2.
WHAT determines this o er level? (0.75) c.
Following the immodtate op reactor power cecreases at a cert.itn SUA.
1.
At WHAT SUR does reactor p er subsequently drop? (0.5) 2.
The reactor dower level one h r after a reactor tr:o as en v.. a n.e t e i. I'.. E AFL 'IN t n e e n : e t en e r-ct this r cter power level in 1 ht of voor respons to part b.1.
(0.75) QUESTION 5.06 (2.50) ANSWER the following questions regarding plant response following a reactor trip after an extended power operation, a.
Reactor power immediately (within one second) drops to a certain value.
1.
To WHAT value does reactor power drop? (0.S) 2.
WHAT detereines this power level? (0.75) b.
Following the iemediate drop, reactor power decreases at a certain SUR.
1.
At W!!AT SUR does reactor power subsequently drop? (0.5) 2.
One hour after a normal reactor trip, nuclear instrueentation indicates approximately 100 cps; however, the actual reactor power is approximately it.
EXPLAIN the existance of this reactor power level in (0.75) light of your response to part.. - - _ _ _ - _ _ _ _ _ _ - _ - _ _ _ ____ - - _ __-__ l >
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1
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i JUEETIC?1 S.07 r3.00)
. t a a r.e Y an k..e e r eic t. c r cover as etoaos at ICE-3;. power.
T he> i 1) i nadvertenti v mo ses the C'un llJ vor 45 seconos.
456UME - , a od worth an 0.006*/. delta-rno/wtep.4nd the oficctive celaveo l neutren fr.*ction i c 0. 00s.
AN5WER the followino. assumino.
, , j no urinor cperater ..c t 1 c n '
a.
CALCULATi' the fiUR t ra:nact at vi v AFTER red itottcn etocc.
iKOW al1.our wari.
- ., T AI L a l 1 acuu,.pt ons.
t2.0) f c.
C uma.w oo wi t o cart sc., above. HGW ann 6Hr would tne ,
E';h c c.aric e av it were calculetco just rEFORE rod motion ,
- .t r o p a e a
- Na catculationn are nec e r, tar v. ;
(1.0) l .. f,
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I'FibOQpyNQU}C$ QUEtiT ION S.09 (1.50/ I Fuel rod gao 9 heat transf c ar, be constcoreo essentially conduc ti on tical trenster.
ILL the hoat t e' An s t er across
the gap INC:<FASE DECREAS. or NOT CHANGE for s.et ti ot the following' o.
fuel swelling (8.5) b.
higher reactor ower (0.5) ' c.
gap gas daf uston into the fuel (0.5) -, QUEST 10N 5.09 (1.50) l Fuel rod gas gap heat transfer can be considered essentially f conduction heat transfer.
WILL the ability to transfer heat ~ across the gap INCREASE, DECREASE, or NOT CHANGE for each ' of the following? a.
fuel swelling (0.5) L b.
highs reactor power (0.5) I . c, gap gas pressure decreases (0.5) ! . '
i ' i ! . (ass &6 CATEGORY 05 CONTINUED CN NEAT FAGE totsas , - - - - - - - -., -, - - - - -, -,. ,, w... - - - >, -,, -, =,,., - - -,, .,-r ,,,w.,- --,,...,-,,n-m .,nwe,,,_y,,.,-,n:--------n- --
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- M.E L11.tbe01CS OUEETIGN D.10 ( l. CL1 ) The tuine iani ce reactor i3 4L iCG*. cower.
Ycu note t. n a t Io 13. rf ec P' hacher inan the prevacus cavs value.
FCS tlourate is tne somo. T/G output is the same, and the plant it in eautlicrium.
STATE whether thu f 011 owt nc) parameterrs WQUlc be HIGHER or LOWtiR than t.ne previous dav's vaauen. Ana dIYa O FDACCh tQr naCD Answer, a.
,te en gener4 tor rec e u vr e (O.75) a.
s t e a,n ,1owrara (0.75) l ! ! I I r I i i !- ! i see446 CATEGORY 05 CONTINUED ON NEXT FAGE see**e
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..] HEgby. OE,NUGLF; Ah. POW [F, [tGNT_OF [60T 10N, _ FWJ DS,,QND PAGE !! . 1006:300(NQttIC5 UUESTION 5.11 ( .00, The Masno Yan6tu. reacto a operatang at 100% power.
A l'URV h.A n utott or'ch.
I T E.RM I NE tne appro:: s mate lano t on per at ur r-wris ch t.hrail a nos cated downste can, ce the FORV 1i p e ris sur i : or pr usur as 0005 pstg.
SHOW all work.
STATE all ass ptions (2.8) x QUESTION 5.11 (2.00) The Maine Yankee reactor is operating at 1004 power.
A PORV has stuck open.
DETERMINE the approximate line temperature which should be indicated downstream of the PORV if pressuriser pressure is 2235 psig.
SHOW all work.
STATE all assumptions.
(2.
0) (44444 CATEGORY 05 CONTINUED ON NEAT F AGE 4:44&s
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U.tSHODXNOM1GS JUE51 ION 5.)Q (O.00) One centrifuoal CCW cump is ocorating a a certain dascharon n o.n c iF1i and + .w sO!). A second ce r1+ugal CCW p u.ro inn parallel with the first) as star)cd resultano an o single corr 'K w (P2) and f (02).
For each of the combined dischargo head f ol l owi ng, CHOOSE t ct answer.
a.
The ratto of f i n a to ini al discharge heads (PO/P1) ist (1.0) (1) equal to 1.0.
(2) greater than 1.' but less than 2.0.
(!) equal to 2.0.
tai greater than .0.
b.
The ratio of fi al to in tial flow (02/01) ist (1.0) (1) eaual t 1.0.
i!) greator than 1.0 but l'ss tnan ;.0.
s!) equal o 2.0.
(4) grea er than 1.0.
o QUESTION 5.12 (2.00) One centrifugal CCW pump is operating at a certain discharge head (P1) and flow (Q1).
A second centrifugal CCW pump (in parallel with the first) is started resulting in a combined discharge head (P2) and flow (Q2).
For each of the following, CH005E the single correct answer.
a.
The ratio of final to initial discharge heads (P2/P1) ist (1) equal to 1.0.
(2) greater than 1.0 but less than 2.0.
(3) equal to 2.0.
(4) greater than 4,4,/,e b.
The ratio of final to initial flow (02/Q1) ist (1) equal to 1.0.
(2) greater than 1.0 but less than 2.0.
(3) equal to 2.0.
(4) g r e a t e r th a n JW1F. /.P se.... enu ur LHicuvnv es asssss .
6. MtTN1 pyiij f.0!i.pE5[0th f 09IEQ6_OtiD_lN$16Vd[Ul@llQN PAGE
l v a 3..... n.e; < k,3, ANSWER the followino que tions reoardino the CVCS.
. *. 1.
STATE t h e, two ( ) purpos 5 of tna letcown cray salves (LD-A-9.11), (1.0) 2.
Briefly DESCRIBE O these valves funtion.
(1.8) 6.
The standby charging p,u is started when pressurizer level as 11% less than setpcin Under WHAT condition (s) will . this pump NOT be tr bped hen pressurizer level e::ceeds setpoint b 13%? (0.5) c.
WHAT tvats% d e ts t 'n feature s m i t t, the civr rcr euur e of tne cnarging 1 e downstream of the charging flow c on t r ol valve (CH-F-38)7 .NC UDE its location.
(0.75) QUESTION 6.01 (3.25) ANSWER the following questions regarding the CVCS.
a.
1.
STATE the two (2) purposes of the letdown drag valves (LD-A-9,10).
(1.01 2.
Briefly DESCRIBE HOW these valves funtion.
(1.0) b.
The standby charging pump is started when pressuriser level is 115 less than setpoint.
Under WHAT condition (s) w11.1 this pump NOT be tripped when pressuriser level exceeds setpoint by 1357 (0.5) c.
WHAT system design feature limita the overpressure of the charging line downstreas of the charging flow control valve (CH-F-38)? INCLUDE its location within (0.75) the systee.
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5.157 the two i 2) eutometic act2onti unach ._.c t. u r fol1owano 4 1 r;w ste,am cens2 rat or lovel stonel ( 250':. 11.0) U.
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.A+4*luN o b'. ' s ".. :. 0, ANSWER the fo owing questions reoardino the emergenev diesci e,s'n er a t or v.
- ED6 ).
c.
TRUE or FALSE.
When the engine is muiuallv started. the generator ftet is automatica y flashed and its output breaker is manua y closed.
(0.5) b.
LIST'the normal sou e of cooling water for 1.
DG-1A (0.5) 2.
DG-15 (c.53 c.
The EDG temperatu e is maant ined at 150 degrees F.
HOW is this temp rature conte accomplished? (1.0) d.
LIRT the twe ( ) conditionn wht step the EDG withcut
en a 2. f m a r.u t t11e delay.
61.0s QUESTION 6.03 (3.50) ANSWER the following questions regarding the emergency diesel generators (EDGs), a.
TRUE or FALSE.
When the engine is manually started, the generator field is automatically flashed and its output breaker is manually closed.
(0.5) b.
LIST the normal source of cooling water for 1.
DG-1A (0.5) 2.
DG-1B (0.5) c.
The EDO temperature is maint.ined at 180 degrees F.
HOW is this toeperature control accomplished? (1.0) d.
LIST two (2) conditions which would stop the EDG without an 11.5 minute time delay.
(1,0) 188448 CATEGORf 06 CONTINUED ON NEAT FAGE seasts
- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ ___., EL6NJ Si SJ(M[j,D[QlON _(QNJ6Q(3, @ND_jh516UMEN161100 PAGE 1~ ^- 11 1 +.1, n. M ..',s.
i
ANSWER the followan questions regarding post-LOCA containment
- ectrculatton.
.. edSUME a LOCA hat c4 cur ed followed by a salte RAS.
STATE the flowpath t t) t unasts to return water from the containment sump ba k the RCS assuming no operator action (LIST major compo nts in flowpath order, valves not required).
(1.5) b.
WHAT problem acessitated inst lation of the HSI-331 and HSI-33" vpass valves * gg,gy / QUESTION 6.04 (2.50) ANSWER the following questions regarding post-LOCA containment recirculation.
a.
ASSUME a LOCA has occurred followed by a valid RAS.
STATE the flowpath that exists to recurn water from the containment sump back to the RCS assuming no operator action (LIST major components in flowpath order, valves not required).
(1.5) b.
WHAT problem necessitated installation of the HSI-331 and HSI-332 (A Train and B Train bypass valves)? (1.01 (asssa CATEGORi 06 CONTINUED ON NEXT FAGE as***)
._.. D.
'L ON I.DlE f f dL_ QG 5IIiUx _E 9015DL t _dO2_10ElOb'UEUIO1190 PAGE
OLESTICra 6.00 ( 2. 7' J J AfiSWEf? the following quantions,regercino the Emergency and Atta111ory Fessm+ter 3 ns t r$m. a.
LIST two (2) suction nources for the emergency ano sua111ary focawater system.
STATE which ta the normal r.e ur c e. (1.25) o.
- TATE wnether the emergenev teoewater flow centroi
vaa a e QFW n-101. 201. 301) will FAIL OPEN. FAIL CLU5ED cr FuiL-45-IE cn a lona of instrument atr.
(0.5) W.+4 7 will coune outomatic closure et the emergency
- .
.. , voedwater isolaticn valsos (AFW-A-375, 209 2,4 0 ) ' (0.5) "OU con than itirict i on be t,vpensed an tne event of .. an s naaver tent actuationT to.5) i t , E L P l
, I
l gas *** C AT EGOR r' Co CONTINUED ON NEXT PAGE 6****) ! i __, __ , _ _ _. _ _ _. _ _ _ _ _ _ _. _. _. _
_.
_ - _ _ _ _ _.__ 1. _. 1 8 "N1_.315!1i.N:._El.IU l'1 r. 7-2bO,f' -r _ub@ I'j$3.lAtt!dfjh}f 1903 ' ' *GE I' ' .. + UULSTION 3.6b t'.50/ << s S L ft tr.c RCs 1.
in the procets of t,C a rig Cooled down normell. And a t:Or or, U r t ; r J /,fter 4 reac+cr trio.
1-r r b ;o t t r-r,. r e. r, u r e _ ;, nt.n e l i. hos im A t d ina yo tut f.at c not ccen r t. n e t. F Cs c,rossure t5 at 1400 psig anc 400 *deg F.
F r e ne u r t ;: re r pecucure tafoty Chcnnel D then is t i n hiah.
DE2CPifW IUW4 T 64; 11 cccur a r, ci result of thi'a s i t u.it i o n AND WHY at cccurr.
INCLUDE tettonntc and coincidences a s.
epolic0ble.
(1.5) l 164444 CATEGORr De, CONTINUED ON NEXT FAGE
- )
__.. _.. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -. - - _. _ _ _ _ .-. %OUl_'J!sI6Mh 9E?.Ws _GUIJIE96a.._sND_10kTE(Jd?NI@Ilg[J AAGE .' O I
OUE5110N o.07 C. 03; 4tE WEh the f ollowa rm auestions rooardino pressuri:er pressure and lemi i n s t r u n.e n t a t t e n, Lurtog aonormally-hign containment pressure conditions.
a.
W I t.L the indicated pressuri:cr cressure be EOUAL TO.
AE.ATEh THAN. cr LECS THAN actual-- EXrLfi!N veur reasoning.
(1.5) U.
DW t nq sbnormal)y-nagn conteinment t omperatur:* condi t i ens.
WILL the inatcated p r en t.u r t : ce level be EDUAL TO, GREATER ThAN. cr LESS THAid a - t v a l
- '
EXPLAIN vcur r et a n on i n g. (1.5) sa*64* CATEGORY Oo CONTINUED ON NEXT FAGE
- 66)
_ _ _ _ _. _ t.
.._ u t. 1. ? 1. d. y -.iv d ... .2 ..- ,, c . , -. - c', 7 * 'I ax.- r Ult e :: s. _19, L 1' 9,i...,,,, U.-[U11/.*
- HJt-4
-c uuu_ 'A [I~: QN n.03 1.SCe cor nacn at the pollowino patrL o v' na mul tatinotts RF6 instrument
- .4 : 1cer2 If4DICATE mnetne: r-
- n e-rc-:tcr a hnt.l e TF:! F. *::T TF.f r.
- 5 AF T; I F'. J ui,T I F r your e n s.% r una r. c n *. 1 d o r oa c n ;; c. : r et tatAeret Seoeratelv.
ASSufiE ofant ac at 1007. power, s.
'f h / L F t rid i c at i c r.
t o Cha.nt:1 i, ietlh to 1700 resta stID r iM/LF indacatton ta Channt*1 C taa15 to 2050 outg.
(d.75) L.
Channel b t. < n.m e t r. c c e t *. e t 1atIs tc -0.5 AND ocwor ttvopiv to Chinnr!) o reawer falla.
(0.75) (66*** CATEGORY Oe CONTINUED ON NEXT FAGE : ****)
,_ i-u,N T S e's ],tity _liE31 G.;, _.jjgi$ gL,,__gND_lySTEtit'.EUlGIICN PAGE
,t_ UUEST I Ot.
6.07 ( 2. ' 0)
For each ot the t ol l own r.o radi ati on monitors. STATE the .iu t em a t t : ' unction (9' af anv. per+ormed on an al armed . c or u t t i cn. a.
6M-2605. Steam oenerator blowdown system (0.5) o.
RM-?A01. F r i me.r v component cooling wate+r system (0.5) c.
h el-!iO x. t ri mar y vent utac6 (par t i cul ates (0.5) a.
.M-31029 Cont.aomont.ontslatten toau) (0.5) c.
n M - o l J,'. Spent tuel pool aren (0.5) ! ! I ! l ! I t***** CAIEGORY Ca CONTINUED ON NEXT PAGE t**sa) - - - - - -
0... rl60I. d_' 51 Ebb Id.i?lths _C?llbkL s.. 600_lUklbl.'UEUlOllEU e AE 27-C U E b f l O !J c.10 '2.00) rNSWEli TTsUC cc FALGE tc the tallowing ruatter c o o l dsn t loco
- nterAOct u t s t e me n t.i.
a.
The bypass valve mu r.t be open betere either T-hot or T-cold stop v a l vry s 3n he enut.
(0,5) b.
A T cold s t ort vaive c.s n n o t be opened uniest its u socazited cold iao temper atur u as wttnin 2 0 ateo F ct tne hignent colo lug tempcrature in the otner iocas.
(0.5) c.
The lecL U s p.e.
salve tannot ti e w r.u t unless tnt * s is s o c i e t u d Icup I-hat sno T-cold ztco valsos are, c>en er ttir itssociateo hCr' tt oft, s0.5) a.
- Te MCF ulll trip ;f etther the f-not or T-cold 5tco valve is not fully corn and the associated bypats valve s: not coen.
(0.5) I (46448 END OF LATEGORY 06 **tes)
I....[RQCEQVSES_.0060GL,.OPUgSMA(,,EM6EQEUG),GUD PAGE 4 MP10(00.1 COL CONTROL CUESTION 7.01 (3.00s k ANSWhh the following regaronno Magno v an6 ce oper at i en. momes.
a.
Operations memo 9-B-d advt us operators to manually trtp the reactor instead o+ movt39 the/CEAsduringaplant shutdown with no cooling fa a operational.
WHAT adverse condition is being mitigated (1.0) b.
Operations memo 9-D-3 addres a MDFP recirculation valve operation 21 testing.
It states that during such testing the associateo MDF mu t be isolated anc cepressura:ed.
WHAT adv rue ec dation as betno n'.rtgetud' (1.0; c.
ANSWER the followan TRUE or FAL E.
1.
According to crerations memo 9-6-1 at to par-tstible b '- 5 c n anr.c l for n i n d e t' i n t. c cerace t o t vpas.t #. wnsle awat ing ItC Department eer 6 to commence.
(0.5) 2.
Operation memo 9-H-3 addressing motor operated discon p' cts in 345 KV and 115 K switchyards was e9 ablished as a means to pr vent an t inady4rtent loss of load.
(0.5) CUESTION 7.01 (3.00) ANSWER the following regarding Maine Yankee operations memos.
a.
Operations memo 9-B-6 advises operators to manually trip the reactor instead of moving the CEAs during a plant shutdown with no cooling fans operational.
WHAT adverse condition is being mitigated? (1.0) b.
Operations meno 9-D-3 s.ddresses MDFP recirculation valve operational testing.
It states that during such testing the associated NDFP must be isolated and depressurized.
WHAT adverse condition is being mitigated? (1.0) c.
ANSWER the following TRUE or FALSE.
1.
In accordance with Operations Memo 9-J-3, the SOS is authorized to lend the key ring for access to high radiation areas.
(0.5) 2.
Operation meno 9-H-3 addressing motor operated disconnects in 345 KV and 115 KV switchyards was established as a means to prevent an inadvertent loss of load.
(0.5)
. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ? - E6U(t QtJh r Q _ ;,Ng5 mal g, A[tJgEM A( 3,G M(Fj Q(tjQ Y, AN Q FAGE Ob RA15J OL,00 {Q(f.,GQtQ hQt, l.
OUESTION 7.00 (O. 30) /, AShi)ML that the parect al.
n.
"Less of Instrument Fus Dre!AC" -no "to.s o.
I n u t r uiten t F.s DP/FAC" activato.
a.
It the cuses are ucce sfully repowered per ADF 2-11, STATE the two (2 acti s which must be taken immediately.
(1.0) b.
Under WHAT co ition(s) ust AOP 2-11 be exited and EOP E-0 be eftered? (1.0) s QUESTION 7.02 (2.00) ASSUME that the panel alarms, ' Loss of Instrument Bus DP/IAC* and "Loss of Instrument Bus DP/ PAC' activate.
. a.
If the buses are successfully repowered per AOP 2-11, STATE the two (2) actions which must be taken immediately.
(1.0) b.
State TWO conditions when AOP 2-11 aust be exited and the EOPs entered? (1.0) l l ' (44a44 CATEGORY 07 CONTINUED ON NEXT FAGE aatso, .
- . _ -. . _. __ ___ _ _ - _ _ _. _ . _. _ . _ _ _ _ _ _ _ _ _ _ _ _. _ _ _ _. 7,t. 26i9565%O!55_ 02bOUks. dSd960662.5DE.EGENgy,60Q PAtsE Oc 5:.i R I W 4 0 L C. % G 9 0 ! 6 0, OUESTIOtt J. 03 ! 1. 7'! ) M a a r.t-ienl ee 3L cL.or a t i r.Q #i t 1 DD*; Ocwur whon a urcCr,cd r oc occurs.
ii. IDENTIFY the action (s) that must t; u t a k tin during the f 1 r t; t nour aiter identifitation ci the prod 1em. a t.S u mi n g tho red cennot t o al 1 ont'd W1than 15 minutes.
t1.0) u.
uMAT accitsonal actients) .T.u r t oc taken ;f a secono it'A rneuld drer..et!c the tartt CEA se tully incerted i ri the cere? (0.75) s***66 CATEGORY 07 C,0NTINUED ON NEXT FAGE 46444)
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ , ?r..A50GEDU6ES,, ;,NQBMGi, t_QPf,jghMQ(,g,[MF6Q[NCLetJD FAGE
69019690lG06.GQN160( QUESTION 7.04 (0.00) Ma n tie v an6 ce is op eatang at 5 0 *< p o w r$r. Lctdown ano ehargang elows becomo erratt RCP sua water ovopiv and return flows . become erratic, and b feed low tz lost.
a.
WHAT is the most ely cause of this plant response? (3.5) b.
WHAT initial a ton ) should be taken within the farat minute (1.5) ' QUESTION 7.04 (2.00) Maine Yankee is operating at 50% power.
Letdown and charging flows become erratic, RCP seal water supply and return flows become erratic, and SG main feed flow is lost, s.
WHAT is the most likely cause of this plant response? (0.5) b.
WHAT initial action (s) should be taken within the first minute? (1.5) l ! I r - , b (*e aa CATEGORY 07 CONTINUED ON NEXT PAGE ***as) - - - - - - -
, .__ _ -. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ______ _______ E. _ECOE[.0USEs. _UGB% ?Uubuf42..it!EBGEUO etJR %GE n % 916 W Ji:.b _ 9 tile L OUEBTION 7.05 44.00) A re..cter trto has occurred due to a s t rit 1 o n DJeckout.
E.C A-0. 0.
'Lc,s ci al1 4 t cwer. 1s entereo.
a.
STATE WHi the EFCVs are immediately closed, t1.0) u.
All out ene at the potentiel RC5 loanage sources are tecleted as part of tree immediate actions.
IDENTIFY thw rne (1) remainsng l e a i. a a e source and tne b a s t y.
f or net manually 1:clating it ou part at the t m.me a t s : e act1ons.
s1.0) c.
-ert et the a rt.me o t at e r es p on te to this event includes .erieicotton ct nFW pump start.
It AFW pumo F-25b J r., c t.-
- ot tt. ort trcm the centrol r ectn. LIET the four s.1 )
acttens an cocratcr munt car.c l et e locally before attempting to locally start AFW oump P-258.
(2.0) , (***** CATEGORY 07 CONTINUED ON NEXT FAGE
- )
F .
Z.t__E5DIEDL'8EE_ _U9BOOLt_OEUQdb6bz_ENE5GENGX_0ND FAGE
is0196921G66 6901696 0UESTION 7. L% ( 2. ' 0) J F OT-E-3.
' Steam Generater Tube Rupture" (SGTR) providec gui darice ver responcing to a SGTE.
a.
LIST three (0) uecendary indice.tiens used in E-3 to identify a rupturoc SG.
(1.5) P.
Ctcp 17 i n te t r uc t s the e.ocrator to cooldown the hCS to a touctfied toinpereture cosed on euptured SG pressure.
WHAT is the basis for the soectfled core temperaturo? (1.0) (***** CATEGORY 07 CONTINUED ON NEAT FAGE
- J
- .2_._ SEDER 6E55_:_UR5t h BENE 006Ls_dudEE5dGl_6NQ-m6 E
ce!!1CLual;66_ suldb6 0UESTION 7.0< ./S) + Tne heat sinr G t S t u re Tr* ? e F.". T montters three aecenaars p.ar dimet er t :. c assure that the heat e t n :, er1tacal i.a t e t v 5un7t1on ts uatasiaed, t.15T thosce throu (3) parameter *s.
(O.75) (***** CATEGORY 07 CONTINUED ON NEXT FAGE
- )
_ - _ _ _ _ _ _ _ _ _ _ _ _ Et__t60?sDVEE5,r_OGEU6Lt_e[UOEUGLt_hdEE0%U?1_6UD FAGE
d6DIGL00lG6L_GGUIE0w OUESTION 7.08 (2.50) Dur i rio c empl et1 on of EDF EE-0.2.
"Natural Circulation Coolocun," an HC5 barntton to eolo snutdcwn ccncentrat1cn sper luchnical Data Book 1.1.2) is required ti at least ono RCP cannot be startec.
2.
STATE WHY over-boration ie necewaarv.
INCLUDE a description of why thin Situation exists.
(1.5) 6.
WHY 13 cvor-beration unnecestarv tt an RuF can be started? (1.0) l ,
l l l s***** CATEGORY 07 CONTINUED ON NEXT FAGE
- )
3.*_ .l l O G E2E L'b E E _ ; U O O O bies,_ O M JO F.U O ba... M E O E U C L.U U p 'AbE
. . 66kl.C6001s06_G.001E' 6 J C UE ST I C:N 7.09 <..0) Hign ;cn t a i r.mr-n t ci r:a r n e c. c t i v i t y occurecd while ficccang
- h e r e t' U ts 'A A f10 d d V i t '. I r) p r 9. 0 3 r* a t 10 n for thO r a r ti t tCW
. 6otuolinos.
STATE ino t.wo-etage process used to mitagate this prcbicm.
(2.0) t6444* CATEGORY 07 CONTINUED ON NEXT PAGE e6***)
It__E60GEQUBEg_ _UDEUGLx_GQUQEtGL,_EdESQEUGX_sND CAGE
t09106901Geb_?ONISO_, QUE3 TION 7.10 (2.00) NRC nc 1iacAt1cn as requirco vie t h e Err.er g c nc v Nottiicotaon svutem TEN ) tmmodtatelv (within one hcur) if certain limits are met or w>:c eeded por 10CFR20.400.
IDENTIFY the applicable limits for eacn of the f oll owi no.
n.
Fereonnel e:tposure (three i3) limits requirea) (1.5) u.
Rac2auctive material celease tone (1) limit requirod) (0.5) ! i l < s**6** CATEGORY 07 CONTINUED ON NEXT FAGE
- )
as-i60C[9W8EE 2_UObOObr..ebbOBdb6t EUEEEbOE)._GUD FAGE
6.0D.IOLG01;e6_GQNIEQs OUESTION 7.11 (2.50s Curino a tr>racus plant ett+ r o r n c v. necreters mav ou called vocn la oest ut in eoaren sna recovery operations an the olant.
a.
In such cases. WHAT wnole body cowe is an operetor permstta to recesve:
to bring en inj ur ed wor 6 er to 76totv? tD.5) 2.
- o repcair plant equipment ano prevent further
. ^ 1 Mit COgrLOation' 10.b) o.
Wh?) muut authortJe this voluntary radiaticn c::cosure up to the cmcrgency limits? (0.5) c.
WHAT are the consible otiects ci reeviving radiation e::pt cure of the levels of 50 rem? INCLUDE thort-term and long-term offects.
(1.0)
, st**** END OF CATEGORY 07 464**) - -. - _ - __ -- __ _
Os.QQMjNISJR911S[ [60G{QQhhQ3,QQUpillgNF, QgQ,LlMlIOllgN} FAGE . .. ut. i 1 ;.n o..; ; .. N. ' e ANSWER the f oll o ing Questions regarding e reQua rements of Fence' dure 1-Oo-S.
's 1+t Manntng and Ove t me hequi r ements. " r. r. 41 M.i t no r,.n6e+ Te ri ical Spec 1iacatt .c.
a.
1.
WHAT ts the at amum number of fire brtgeoe memberg needed on-stte t all ti es? (0,5) O.
WHAT Qualtftcation et the replacement f or the Fare Brigade Team L der possess assuming a replacement is nee e by incapacatation? (0.75) !.. WHAT time I s ma t, coply o this replacement' (0.L; D.
During refueling erations th SOS becomes all.
The FSS suspends ref eling operatio s, and dispatches the refueling super /tsor to the cor tr 1 room as a replacement for the all 509.
An AO a s di scatc.ed to the refueling pletto r.
ta aost mi t sn re t.te; t ng a er a t t er. t. r+VE T e c h n i t, ~. E c:2 4 tcations even met ~ t:FLAIN.
( 1. U.)
QUESTION 0.01 (3.00) ANSWER the following questions rogarding the requirements of Procedure 1-26-5, ' Shift Manning and Overtime Requirements," and Maine Yankee Technical Specifications, a.
1.
WHAT is the minimum number cf fire brigade members needed on-site at all times? (0.5) 2.
If the Fire Brigade Team Leader becomes incapacitated, may a Reactor Operator assume the responsibilities as ' the Fire Brigade Team Leader? Justify your answer.
(0.75) 3.
WHAT time limits apply to thAs replacement? (0.5) b.
During refueling operations the SOS becomes ill.
The PSS suspends refueling operations, and dispatches the refueling supervisor to the control room as a replacement for the ill SOS.
An RO is dispatched to the refueling platform to reestablish refueling operations.
HAVE Technical Specifications been met? EXPLAIN.
(1.25) Lassas URIEUUhY 08 CONTINUED ON NEXT PAGE 4***4)
____ UA-UDdl01215sIIEt_f.00C[E!!$GEt s9Ui;111996_gSD1{b]I6TIQUS e nc,E
- '.o
Oh2STION G.or 11,00) tibT tne two (2) boots wotr.n must be rovacwed and intt1aled
o.
onth tnu en-cming PSG and 3C5 dur ing stil f t turnovc;. (1.0) ! l t i > , , (4**** CATEGORY 08 CONTIt4UED CN NEXT F AGE
- )
.
p~~-tr,
-nGd ', 7 L I M I T /; T I o*n......r r. t 1 I N..I.q T P J.T WE.. F A OG !.' U 33.0- - t L C. Dh D..1 T 7 ',J.,L-n n.
-- -- - -- OUEST!ON 3. C '. (2.50i ,,NEWEt; T R Ut' cr i~nL5E to the *ol1ewtng quest 1ons on Froceoure J-14-). "Whtte T-oqstia Frccadure'. a.
A eingle Itcensea operator tunually the F55/505) can valtdate that a tagging order util perform itu 1otendsa t urm t a t n.
iU.5) a.
ii Lagytng ordor-rih a l l not ce crunged without fir?t c:st at n ar..j permi nt on t r oai ogi noldw., n d the PE,s/203.
(0.L) c.
Inueooriaent arieicat. ten er eggana and 'awste ni n g tn c.outrcu en.i l 1 eufetv C 1 c. t. L J cu t pmcent, t0.Se d.
T a m p ar a r '..uodtinc6ttans wnten J rv t iu t i n t er l oc h ts ano setery +raturet.r.av t e wn s t e t a g g ea p r o. t d ea t ra a t 355/ 5GS approval is racesved anc all Technica S pec t t i c t i c,n t, riave been met.
60.5) - e.
T.gyru equipment .m ni v be operatec uncer emer gency c u lo t t i nr.w only at tne dis.cretton of the F55/ SOS.
to.5) s6s:** CATEGORY CB CONTINUED CN NEXT F AGE 444**s . _ _ _ _ _ _ _ _ _ _
S A u2Oll'lf2Ihsllh'!i 65.GLEf:WEEx t!.ONDI T T ONn. AND_61bil8IlQL@ F AC,E
, i JUE.5T1ON 5.04
50i Tno lant thret-compl ert s on oatus +or the performance of a semi-2nentel wvevetA'. m.o test weres
- 1 Feb 87 (day 52). 24 Auo 87 (day 206). 28 Feu 88 (day 59)
a.
WhnT t.; the normal 1y seneduled aue dato (or day numberi tor t h e n em t peric.rmance of t h i ::, test' 5HOW your worL.
( 1. 0 ) s.:. Dv lechntcal Specitications. WHAT 15 the last cay tor d u nurf.bre) tB1e tert can t: 0 1egelIv perfcemed before the tvuter/cceconent must be classiftad inocerable? (1.5) 'd H UW sour wor v. l
. t < \\ l s***** CATEGORY 08 CONTINUED ON NEAT FAGE
- 8)
! I
- - - - _ _ _ - _ _ _ _ _ _ _ _ i.i._ 00010.15IRQI! yE,.ERQCGEt.f.G3.,,G 3(JQ I T,J ONs3. fyQ,(1011QT I,Qy,5
- nGE
- UEETION B.05 ( 1.50)
WHAT three t!) plant p rer sonn el choulo tirut be 2nvolved
- r.
c.
Techn1 col Corct i 2catacn t nt v.r pr at at t on cocts1on re,r .-rcceauro 1 - l. c - 2.. "Tc.cnnicat. spec t e t c at i en Interorotation-s1.5) ' < l I
. ! I f i ) , I
1 L*6A** CATEGORY 08 CONTINUED ON NEXT PAGE
- )
_ _ _ _ _ _ _ _ _ _ _ _ _ L-A QU 1015I 56I 1Y E.160 C E n u S E ;53. _ g O N D lI l O d 5 t _ @ U D. 61d l I 6119 b h PAGE
OUESTION S.06 (1.23/ STATE the casts for Technical Soccatication 3.1 wnten limits core oower to 90*/. unnn over the v:cera nvmmetric o ttet protecticn uvstem has not Deon calibratoo within s the arevacun 70 dayn.
DISCUSS reasons associated with both the coro and the detector.
(1.25) , l I i I (6*e44 CATEGORY 06 CONTINUED ON NEXT FAGE *es6*) - - .
. -. . . _ _ _ _ _ _ _ __ . _ _ _ _ _ _ _ _ _ _ t.is 000101 SIB 011h'E tbOELUUSth CWUQ11190l22.000,.L,101101.1905 PAGE
l vvt_a e l t st.
t:. 0.' s l. shu - WHAT two (2) remedtal cct) ns must be taken if the RCS o r t.*s sur e / t emp er a t ur e 1 ts at Tecnnical Spectfacetton 3.4.
"t.4nu t n ed Hemsuc. C00 wn and Fresaure-t emper atur.s L a mt t e t t ons,. " ar e er eec c? (1.0) , l N ,
. QUESTION 6.07 (1.00) j WHAT IMMEDIATE remedial action must be taken if the DCS pressure / temperature limits of Technical Specification 3.4, "Combined Heatup. Cooldown and Pressure-Temperature Limitations,' are exceeded? Do not censider LTOP in your I (1.0) a ris w e r.
J (4s444 CATEGORY 03 CCNTINUED ON NF. AT F AGE 444a )
_ < h __ SLO !31sIEd'IIEt.1E%s k'ihi:iit '-;00DI T.IM51_eNO Lib 1I6IlpM fnGE 4: CUE 5 TION 6.Oh ( 1..'. 0 ) The e t= ac c or 15 et 00*/. o cwer, equi l i br i um c orro t t l or.s.
Heat tE* e c i n o in l ost, to all ti c r c'n injecticn naths.
WHfT two (2)
- nareru l e t. e it.iittaintait appl. tu reactor cperations.
(1.0) s:**a CAldGOR'r OS CONTINUED ON r4 EXT FAGE ses* )
_ _ _ _ _ _ FAGE
dt e001012IGOIIYt.:_E50sEEUEE31_GQUDIIIOU5t_bND_LIdlI6IlOU3 DUESTION 6.09 (~.00) ANSWER the tollowing outstions regarcing the satuty injection tanim (SITS).
o.
HOW MANY SITS must be hetup for automatic inttnatton when in Condition 7 per Mainu Yankee Technical Scoctfications? (0.75 c.
ETATE the reoutrements that must be met for on SIT to Le constccred operable (notocints not recutred), ti.5) c.
HOW lon; may cn SIT be isolated? (0.75 t . P I l ,
l ! l l
, is64se CATEGCh/ OE CONTINUED ON NEXT PAGE 444**)
I l l i i
- - _ _ _ _ _ _ _ _ _. _ _ 4.t _.60 dlUl'63 E bII'. 'E L.E CG DUE h k z _ L ?UOlllC U: t _OU Q_ L idlIOIICUf IId'E
?.'U E S T I C N 5.10 1.CD) - l 57 ATE the basis fcr Technical Foncification ~J.. e. Secticn b.
wnsen recutrer. that two HERI o uit o n t, *)
- ry err a b l e wnenever the ACS boron c en c e nt r c.i t or. it lest than tnet ronut rea f or Hot Shutr10wn.
(1.5) " Concit t i en ; - , ss 4:* CATEGORY 08 CONTINUED ON NEXT FAGE *****> _ _ - - _ _ _ _ _ _ _ _
-- _ .-. ~ FAGE
S t _ _ dOOldj 5I5 ell'iE _:f EOCE pUFE S t _GOUD1I190), _6UQ_L J U LIGII QU :i OUESTION 3.11 (1.50i tecnntcel Soocification 3.10 addresses. in part, CEA eterattenal Itmits.
2 TATE *.no enroe (3) Ortteria usec to o s t i n e, e CEA mtualtgnment conottacn por Matno Yanteo Tecnnical (1.5) Specifications.
. t e s t s * CATEGORY OS CONTINUED ON NEXT F AGE 66664)
Os-_0RululBIE011YG_tSQGGQWSEft GQUd1I1Gues_000.6101IGIlgus Fact 4o Ol)LJ!luN a.1J (*.00s N ANSWER the following Questions on the Maine Yentee Emergency Flan.
a.
LIST the three (3) potent.a1 urces used in the elease rates and related emergency plan to ogtermanej proj ected of f site d e rates.
(1.5) / b.
Under WHAT emergency ynditions will the EOF, TSC and OSC (0.5) require activation an'd 4taf fing? / c.
LIST tv o (2) acttons wh1 must De accompitshed within 15 minutes of th'e di scover that an emergency action (1.04 ' level has oeen' reached.
' i / QUESTION 0.12 (3.00) l ANSWER the following questions on the Maine Yankee Emergency Plan.
l a.
LIST the three (3) potential sources used in the emergency plan to detereine release rates and related (1.5) projectee offsite dose rates.
b.
Under WHAT energency condition levels will the EOF, TSC and OSC require activation and staffing? (0.5) c.
LIST two (2) actions which must be accomplished within 15 minutes of the discovery that an energency action level has been reached.
(1.0) (tsass CATEGORY 09 CONTINUED ON NEXT FAGE assas) .. _.
...__..n.
. ~ _. -- - - - O*..ODM.!UlgIEAT j y(_[,6QgpyE[gg,y@,f pl1J OUy, OND,,(,) dilt?!19WS l 4GC
tiuh51 I Uf.
u.;. t.. ; 's ANSWER the f ollowino ou stions rea ret ng 10CFA"C. "Oceraterd' Ltconsos.' a.
STATE the ouer t e+r l y c,1 + ronuirements to maintain eri activo license.
(0.75) D.
WHAT two (2) condt) ons ust be met to allow control room ocutoment ahtpulatt n bv an uniscensed individual * (1.5) \\ QUESTION 8.13 (2.25) ANSWER the following questiens regarding 10CFR55, ' Operators' Licenses.' a.
You have been off-shift for two months and have just been i requested to go back on shift.
Are you allowed to assume the shift? Justify your answer.
(1.00) l b.
The primary Auxiliary Operator needs to perform a surveillance on P-14A charging pump.
He requests paretsmion to put the pump in pull-to-lock.
Will you allow him to manipulate the controls? Justify your answer.
(1.25) staatt END OF CATEGCRY C8
- 6)
(assoasstessae END OF EXAMINATION seases64eeesa6s's _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _1
_ _ - _ _ _ _ _ _ _ _ _ _. __ __ _ l t i ! ............................................................................ EQUATION SHEET , ............................................................................ t . .
Where og = m2 (density)3(velocity)g(area)g = (density)2(velocity)2(area)2 ! '
............................................................................ t t !
KE=h PE = mgh PE + KE +P Y where V = specific l ' g g = PE +KE +P Y22
2 volume g
P = Pressure r { ............................................................................ q , t (h.h) I 0* C (Tout. Tin) Q = UA (T,y,.Tstm) Q= t 2 p t \\ ] ............................................................................ i ! P = P 10(SUR)(t) p, p,t/T 3gg, 26.06 T = (B.p)t
o o I p [ . ! l ............................................................................ l J deltaK=(K,ff.1) CRg(1-Kef f1) = CR (I*Keff2) CR=S/(1.K,ff)
, < i (1-K,ffg) (1.K,f f) x 100% l SDM = I M = @keff2I "eff
, ............................................................................
g=Ae.(decayconstant)x(t) { decay constant = In (2) = 0.693 A
- 1/2
- 1/2
r ............................................................................ Vater Parameters Miscellaneous Conversions 1 gallon = 8.345 lbs 1 Curie = 3.7 x 10 3p, j
1 gallon = 3.78 liters 1 kg = 2.21 lbs j f
1 ft3 = 7.48 gallons I hp = 2.54 x 10 Stu/hr , Density =62.4lbg/ft 1 W = 3.41 x 10 8tu/hr [
6 Density = 1 gs/cm 1 8tu = 778 ft.lbf l , I . Heat of Vaporization = 970 8tu/lbe Degrees F = (1.8 x Degrees C) + 32 Heat of Fusion = 144 Btu /lba 1 inch = 2.54 centimeters 2 1 Ata = 14.7 psia = 29.9 in Hg g = 32.174 ft.lba/lbf-sec s i ............................................................................ l ! l l i f i
- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ , D.... lW O!d. 0L Nll[t 1.0L f,0W[h,[,tfgi,yghQl,1yN,, F,l U l yy g,Ogp FEE
IUt_Egggygen gs ANWERS -- M.41NL YAN)t.E-BD/08/09-GRLEL. 6 ANSWER 5.01 (0.00) 0, true C+0.53 b.
f alse (powur will be 3 *. ) C+0.53 c., trup (+0.53 d.
faise (11mt ted by faseton preduct occay roten) I+0.53 REFERENCE 1.
Manne Yanten: Lisson Plan. RO-L-1.10 pp. O through 6.
CLO
- CRC-0101-60.
19:000) 106 192003),109 ... ( 6:A'S) ANSWER 5.02 (0.50) a.
SDM = L2 - 1.
so 6 2 = 1 - 0*/ or 0.97 C+0.53 i 6:2 - delta rho. so El = 0.97 - 0.01 = 0.96 C+0.53 ' K1 = 400 (0.04)/(0.00) >0) >:1 ) / (1 CAO = CR(1 = - - CR2 = 53: cps (5:5 to 535 cps: will gave full credit 1+ l approx mat 1on ta not usco) C+0.53 b.
borate immectately to increase and matntain SCM > 0. *. r n o Mat.Aee.st4 w.o w a44g,/'p.gf tur4'J'. C+1.03 s
REFERENCE 1.
Maine Yannen: Lesson Flan, RO-L-1.10, pp.
I and 5.
TLO
- CRC-0101.
O.
Manne Yann00: Lesson Plan. RO-L-1.10, p.
O.
ELO
- CRC-0101-50.
3.
Maine Yankee Techntcal Specifacat1ons, 3.10.D.1.
0040006519 ...O.A'S) i _ _ _ _ _ _ -
_ b.... M OhV LK. NUf L I "' 6.l)Wlb.) l..QCD 0Mb9110Na _[k Ullt t O!;.J FGM
16.4 6 50tq.0 0 H W ANf Wi h s -- MAINL Y AND LL-tiO / 0 8 / 0 9 - ($4 Uf. L. R.
ANCWER 5.03 (0.00) -- CR(o)/CR(t) (+0.53 1/M(t) = 50/50 = 1.00 1/M(1) = 0.6 L+0.63 LO/o; 1/Mt ) = = 50/105 = 0.4 [*0.53 1/M(3) = ) This can be plotted to show that criticality (1/M=0) is predacted et 30 (29 to 31) a s t> emb l i c s. l+0.53 OR __ .. Since the last 5 ensemblics halved the 1/M v41ue (+1.03.
Another 5 should ma6e the reactor critical C+1.03.
REFERENCE 1.
Maine Yankee: Lessen Flan, RO-L-1.13. pp. 7 and G.
TLO #CRO-0102.
19000GL106 ...(LA*S) ANSWER 5.04 (0.00) a.
less negat t ve C+0.L3 b.
more negative C+0.53 c.
acre negative (+0.53 d.
less negattve (+0.53 REFERENCE 1.
Manne YanLce Lesson Flan. RO-L-1.11, pp. 27 through 09, ELO # CRC-0101-31.
-79, and-80.
O.
Maine Yankee TDb. Fngures 0.0.1.1, 0.0.1.0, and 0.0.1.0.
19:004E103 190004K106 ...(FA'S) -- __ ___ _____ _
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ b., f M (t).Of. NUCL[Qh,.F,'QW[B,%ONLQEMQ1]QS, [LW}Qb a,,,Q'Ji) F * AGE
. . W t.b N D E N Q U K $ AtGM h5 -- MAINC YANtEE-00 / 0D / 0 9-GRUt' L. h.
ANSWER 5.05 (1.00) Xenon production after a reactor trip tu due solely to the decay of todtne [+0.51 and there is more nodino in the core at 10M.
power than at t,0*/ power C + 0. 5 3.
FEFERENCE I 1.
Meine Yan6 ues Lessen Flan. RO-L-1.10 pp. O ano 9 ELO # CRC-0101-90.
19?ccet 107 ...(6A'S) ! ! ' ANSWER 5.06 (0.50) a.
1.
6% (5% to 7%) (+0.53 2.
This level 15 due to the subcr1tacal multtp11 cation of delayed neutrons.
( + 0. 7f,3 b.
1.
-1/5 dem (+0.53 ! O.
(A ~1/3 dpm SUR over a one-hour perted would produce a 20-decado crop in reactor power.)
Reactor power decreases to onl y 1% (instead of much l ower ) due to the presence of decav heat.
(+0.753 REFERENCE 1.
Maine Yannee Lwsson Plan. RO-L-1.9. pp. O through 6.
ELO
- CRC-0101-54 and -55.
' 0000076:104 000007N105 1900006: 1 2 ',, 19200BL107 ...(LA*S) , , i
- - -
_ _ _ _ _. _ _ _.
s i D t.. 1 Hf 0SL 000Vct. [ % 2WE5.tL 901. 0EM91100. _ELV I Dh _0ut! FAGF L1 , ' lufkMgtjyueMics ANSWF.RS -- MAINE Y ANL EE-09/09/09-GOUEL.
R.
i ( ! ' ANSWER 5.07 (3.00) [ do T= (beta - rho)/ rho x lambda (given on equation sheet) lambda = 0.00 sec-1 (9tven on equation shent) ' beta = 0.006 (given in questnon) (+0.253 l rod speed is 40 steps / min C+0.253
rho = (45 sec)(1 mi n/60 sec ) (-0. 008'/. del ta-rho / step) (40 st eps/mi n) I = -0.04'4 (+1.03 ( w A M y. 2 % A M - M) . after rod motion stops
SUR = 06/T (given on equation sheet) = 06 (lambda w rho)/(beta - rho) [
26 (0.034-?.4E-3))/(6E-3 - (-0.4E-3)) [ I = = 26 (-1.90E-4)/(8.4E-2)
= -0.6 dpm (-0.6* to -0.56 dpm) (+1.03 ! I k.
m w & Co.s] H % ^*$ 1 tAmy *$ & *'N1 f'd[*' K] l REFERENCh j ! 1.
Manne Yankee Lesson Flan, RO-L-1.10, pp. 6 and 7.
r ELO # CRC-0101-63.
! J 190000K104 ...(KA'S) !
1 I
[ > ANSWER 5,03 (3.00)
1.
reactor power C+0.053 (decrease will) RA!SE DNbR (+c.53 l } ) 2.
reactor coolant f low rate (+0.;53 ! (decrease will) LOWER DNER (+0.53 l f 3.
reactor cool ant anlet temperature (+0.053 (decrease will) RAISE DNBR (+0.53 j i l 4.
pressurtrer pressure C+0.053
(decrease will) LOWER DNER (+0.53 j l REFERENCE ( i 1.
Manne Yankee Lesson Plan. RO-L-7.3, pp.
14 and 15 ELO ) j
- FFM-0103-10.
t 002000A101 00 000A103 002000K501 193008M105 ...(KA*S) ! I ' i
I i ! ! i ,
_ _ _ _ _ _ _ _ p,. 1 HL olW. Or_ NUCl.,EQR,7 OWf R_(( ANT. O((.FjAllON,,(WI f6_QGQ FAGE L2 IUrbM00!NQMjph ANSWLhs -- MAINE VANtEE-08/09/0Y-GhuEL.
k.
ANSWER 5.09 (1.50) o, increase C+0.53 b.
nncreene [+0.53 c.
decrease (+0.53 REFERENCE 1.
Maine Yan6cca Lesson Flan, AO-L-7.3, pp.
O, 0, and 7 ELO #FFM-0103-0, ~4 and -04.
190000L116 .. 0: A' S) ANSWER 5.10 (1.50) c.
higher C+0.53, due to higher RCS T-avg and same power level C+0.053 b.
higher (+0.53, due to lower enthalpy steam, more flow is needed to keep power constant C+0.053 ACTERENCE 1.
Maine Yankee Lesson Flan. AO-L-7.3, pp. O and 9 ELO
- FFM-0103-4 19:000L101
... (L A * S )
I l l
-__ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ t.. lHiUki Of., NUUllOr< (OW[fi,,IJ ON) Oll,ROIJ 0% _(t.l.l.! DS _ WD FAGE 0 ?- , IUIMUDINOMiW icNSWEFsG -- Mri!NE YnN6 EE-00/09/04-GRUEL.
R.
ANSWEk 5.11 (0.00) 1.
assume tsenthalptc expanston (constant enthalphy) (+0.53 2.
from steam tatiles 1110 liTU/l bm - dog F (sat. steam at 0000 pala) (+0.53 h1 = 5.
assume Inne pressure of O peig C+0.53 (1.o.. quench tan 6 pressure)
Trom Mol l i er d1agram move heri:entally ior constant enthalpy expanston to 17 psta lin!.. Temperature is read as i ' approntmately 000 deg F (can also use saturated steam pressure tabic) C+0.53.
REFERENCE 1.
Manne Yannee: Lesson Flan. RO-L-7.1, p.
00.
ELO WPF M-0101-10 and -0100-18.
00000F6:101 0000066700 010000L500 190004L115 ...(6.A*S) ANSWER 5.10 (0.00s a.
(4) C+1.03 b.
(0) (*1.03 REFERENCE 1.
Manne Yankee Lesson Flan. RO-L-7.4, p.
16, ELO
- FFM-0104-15.
191004L109 191004L114 ...(LA'S) _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ____ __ _ _ - _ _ - - _ - - _ _ _ - -
_ _ _ _ _ _ _ _ _ _ _ - _ _ _ _.
S... F L ANJ MO 1(MG,,D[Q [(i% _(QUlfiOL 3, A(JD, } fj7.,1 hUtGNigi ! 09 F' A D E 5S ANSWCh ai -- MaltW YANIEE-G a / 0G / 0's -GRUEL. E, t__ - ANSWEA 6.03 (3.50) l_ _.= . false (field reust be manual 1y f1 ashed) C+0.5) _ a.
.. b.
1.
FCC water (+0.5) 2.
SCC water C+0.53 c.
A temperature regulating valve directs water througn t he heat enchanger or through the bypase line.
(*1.0) l __ _ d.
1.
cverspeed - -- O, M [ A @ O.30 AMA] . manual 1y posationing ivel e a t 6. s to "no fuel" postt1on L-?.F3 J.
L 4 J/ M Q A m EGn*O e s A S Y & d. W Y '( & s*> q REFERENCE 1.
Manne Yan6eet Svetem Desertption AS-12. pp.
2.
7,
17.. and 14: ELO #DG-0101-2-3 and -0100-8.
064000A406 064000h102 064000r400 ...(LA'5) ANSWER e.04 (0.50) 4.
1.
c?ntainment s p r s. v prepts) (+0.L] 2.
Rh6 Heat ex changer (s) C+0.5) +. ne si pump (s) (+0 53 b.
The rectrcuiation val vos (CH-A-30, 73 CH-F-70 and CH-85) were inaccessible in an accident situation.
C+1.03 REFERENCE 1.
Manne Nantee Gystem Desceiption NS-5 pp. 7 and 0: ELO
- ECCS-0101-0.
006000A304 006000L403 ...(KA'S) -- - _ _ _ _ _ _ _ _ _ __ _ _ _ _ _.
6. _ _tLONJ. W YUIEMS _ph Q1GN,,_ GON16QL,, _@NQ _lNSl@yM[NI@llON PAGE S4 ANSWERS -- MAINE YANFEE-88/0G/07-GRUEL.
R.
ANSWER 6.01 (3.25) a.
1.
letdown flowrate control C+0.53 letdown pressure reduction C+0.53 2.
These valves use a stacked disk assembly C+5,53 which consists of a sor t >;s of slotted discs which direct the letdown flow through a tortuous path C+0.53.
td.14lalso &&f=- f 5 A 6 Vbl y f eMnd*W.
b.
if SI AS i s present C+0.53 c.
spring loaded check valve C+0.53 which bypasses CH-M-44 (l oop 2 charging isolation valve) C+0.253 REFERENCE 1.
Maine Yankee System Description NS-4, pp. 22, 46 and 73; ' ELO #CVCS-0103-2.
004000A207 004000K603 006000K108 011000K602 ...(KA*S) ANSWER 6.02 (2.50)
- N, feedwater pumps start C+0.53 a.
motor driven r-ir reactor (and turbine) trip C+0.53 s b.
1.
all main feed pumps trip C+0.253 all condensate pumps trip C+0.253 all heater drain pumps trip C+0.253 2.
assures SG with steam line break is not fed C+0.75) REFERENCE 1.
Maine Yankee System Description PGS-15, pp. 11 and 12: ELO
- SG-0101-2. ELO #MFW-0101-5, ELO WAFW-0101-5.
( 059000K416 061000K402 ...(MA'S) , i l _- _ _ - _ ___ _.._,
y.
6.. 0L9tJI SYS16MS_!mg.1gN, _CO(J1EL _@ND_]NSIGy(1EN161109 PAGE
ANSWERS -- MAINE YANI:EE-88/08/09-GRUEL.
R.
ANSWER 6.05 (2.75) a.
1.
DWST C+0.52 2.
PWST C+0.53 DWST is the nv.maa source C+0.25] b.
fail open C+0.53 c.
1.
low SG pressure (on the associated SG) C+0.5] 2.
by placing each 3-position control switch in "open" position C+0 5) ,, g g g g,,gy '
' REFERENCE 20o^5 1.
Maine Yankee System E'scription PGS-13. pp.
1, 9, 10. and 13; ELO #AFW-0101-2 and -14.
061000A207 061000K401 061000K414 ...(KA'5) ANSWER 6.06 (1.50) Automatic unblocking of SIAS occurs when 2 of 4 pressure channels C+0.253 sense pressure greater than 1685 psig C+0.253.
Since 2 of 4 pressure channels C+0.253 senso pressure less than 1585 psig C+0.253, SIAS will occur C+0.53.
. % f fbrA'V h Qd jsrs.[0.J.7 REFERENCE 1.
Maine Yankee System Description NS-5, p.
37; ELO
- ESF-0101-1 and-4.
013000K412 013000K501 ...(KA'S)
! s br._.2LON1_Sy$1EMO_QCSlGNt_QQNI6Q6t_GNQ,1GSI6gMGNIGilgN PAGE
ANSWERG -- MAINE YANLEE-88/08/09-GRUEL.
R.
ANSWER 6.07 (3.00) a.
Indicated pressure will be LESS THAN the actual pressure C+0.53.
Pressurt:er pressure instruments read relative.to
containment pressure C+0.53.
Therefore, as containment pressure increases, the indicated pressuriner pressure decreabes C+0.53.
b.
The indicated 1cvel will be GREATER THAN the actual level C+0.53.
The reference leg fluid would be less dense from the higher temperature C+0.53, resulting in lower delta P and thus greater indicated level C+0.53.
REFERENCE 1.
Maine Yankee: TDB Figure 1.3.13 ELO #PLC-0101-5.
191002K108 191dO2K111 ...(NA'S) ANSWER 6.08 (1.50) a.
should not trip C+0.25], only one failure exceeds pressurt:er pressure C+0.53 6.
should trip C+0.253, trip signal produced by power supply failure, second trip from low symmetric offset failure C+0.53 REFERENCE 1.
Maine Yankee System Description NS-12, pp. 20, 21, 24 and 25, Table NS-12-1 (p. 34); ELO NRPS-0101-2.
C12000K402 ...(KA'S)
. bz.!:LON.1,F1SIEUS_p[Q1QN _[QUlBOL3,9ND.[NQlBUdENISIlOU 'PAGE
3 ANSWERS -- MAINE YANKEE-88/08/09-GRUEL.
R.
ANSWER 6.09 (2.50) a.
no action C+0.53 b.
shuts surge tank vent C+0.53 c.
traps Fan-2 C+0.53 . d.
stops containment purge (in the ref ueling mode) C+0.53 o.
stops now fuel elevator upward motion C+0.53 REFERENCE 1.
Maine Yankee System Description AS-18, Table AS-18-1, p.
34: ELO #RMS-0101-7.
034000K602 073000K401 ...(KA's) ANSWER 6.10 (2.00) a.
true C+0.53 b.
true C+0.53 c.
true C+0.53 d.
true (CAF normally closed during power ops) C+0.53 REFERENCE e J Y) 1.
Maine Yankee System Description NS-2, pp. 4 and 5: ELO
- RCS-0101-6.
O.
Maine Yankee Operations Procedure OP-1-10-7, Section 1.0, p.
1.
003000K411 ...(KA'S) .
_ 21__UjQCF.Dy50,$,r_N0000L _GDNQ6dGL x_EME6QGUgY_GUD PAGE
t , 600196091GOL_G9NIGOL ANSWERS -- MAINE YANLEE-88/08/09-GRUEL.
R.
ANSWER 7.01 (3.00) e a.
the potential for CEA coil damage (caused by coil energi:ation under high coil temperature conditions) C+1.03 b.
the potential for water hammer when the valve is opened C+1.03 c.
1.
faise ' ~ ? - ! - > t r-dei y c: ' d; . " 'v--
.: cr d: '- C+0.53 2.
true C+0.53 REFERENCE 1.
Maine Yankees Operations memo 9-H-3.
9-B-6, and 9-D-3 ELO WSNO-0302-9.
001000A201 012000A403 062000A402 193006K104 ...(KA'S) ANSWER 7.00 (2.00) a.
1.
normali:e charging and letdown C+0.53 2.
normali:e condensate pumps C+0.53
b.
If 4160 V bus 5 or 6 is cause of instrument bus power loss C+0.53 and emergency diesel for bus affected cannot be brought on line C+0.53.
s 1. q m c ~m.t e e r"] '. REFERENCE g,3f gj .>. 4 o40et s U A/C 1.
Maine YankcoV Procedure No. AOP 2-11; ELO #EAS-0150-5.
000057A219 000057K301 ...(KA*S) ANSWER 7.03 (1.75) . a.
reduce thernal power by 10% in 1/2 hour C+0.53 and reduce thermal power by 20% in 1 hour C+0.53 [ .W b.
trip the reactor C+0.,53 a,d t -him: sand enter E-0) l^?.251 REFERENCE 1.
Maine Yankeo: AOP 2-21, pp. 2 through 5; ELO #EAS-0150-5.
001000A203 ...(KA'S) _ -. _ - - - -... - _ - - . - -.. _ -. - _ _ -. _ -. _.
-_ - _..
. - - . . 2s.__EbOCLRQbE@ C.NOBdb(s_90006OOL,_(DEh0[UgY_69Q PAGE
600196991GOL_GOUI696 ' ANSWURS -- MAINE YANKEE-88/08/09-GRdEL, R.
ANSWER 7.04 (2.00) a.
loss of control air C+0.53 , .?f b.
1.
trip reactor C+0.p] :-d tr-b: r C-9 25' O.
trip the reactor coolant pumps (within 45 seconds) C+0.753 REFERENCE 1.
Maine Yankee AOP 2-28, pp. 1 through 3; ELO dEAS-0150-2 and-5.
000065A206 000065K308 ...(KA'S)
< ANSWER 7.05 (4.00) a.
to prevent an uncontrolled cooldown of the RCS C+0.53 since a turbine trip cannot be verified in the control room after a loss of AC power C+0.53 i b.
RCP seals not isolated C+0.53 to protect them from damage during coastdown C+0.53 a c.
1.
check if steam supply open (MS-T-163) C+0.53 ! 2.
check if AFW overspeed trip is reset C+0.53 3.
vent AFW pump (to eliminate steam binding) C+0.53
! i 4.
ensure a SG steam supply header isolation valve is l open C+0.53 -
t REFERENCE { 1.
Maine Yankeet ECA-0.0, Steps 3, 4, and 5 and Background f < Document; ELO #EAS-0101-6 and-7.
2.
Maine Yankee Reactor Coolant System (NS-2).
p.
56.
, 200055K302 ...(KA'S) I .
r
i r h i ! ,-m .,,. ~ _., , _ _.,. _ _ _ _ _ _ _. _,. _, _ -, _ _ _, _ _...,, _ _ _ _ _, _ _ _ _ _. _ _ _. _ _ _ _ _ _ _ _ _ _, _, _ _ _ _ _ _ _ _ _ _ __
- - _ _ _ _ _ _ _ _ _ Z s _ _ CBOf.:EOU6E5_..NQ6MQLs_ODUQ6dGLt_EDE60EUCy_@ND PAGE
B001960gtgeL_GON160L ANSWERS -- MAINE YANI.F.E-88/09/09-GRUEL.
R.
ANSWER 7.06 (2.50) c.
1.
NR level rising unexpectedly 2.
high SG sample activity 3.
high radiation from ony steam line 4.
high radiation from SG blowdown 5.
high steam / feed flow mismatch Any three (3) C+0.53 each, +1.5 maximum.
b.
it ensures adequate subcooling (20 deg F) C+0.53 upon subsequent RCS depressurization C+0.53 REFERENCE 1.
Maine Yankee EOP, E-3, Steps 2, 17, and 20; ELO
- EAS-0101-7.
000038A203 000038K301 ...(KA'S) ANSWER 7.07 (./5) C & si no ' ' sS$y & 1.
2 ' 3 ; : z ; ;- ^
- C.;3J J/6 p4J LA
- 2.
3/3 le.cl C ? 25 3 ' .f d 74 M f. a G 3.
J flem " ;0.;3; ,"e. * *S[ h p C. r d REFERENCE 1.
Maine Yankee: Heat Sink Status Tree F-0.3p ELO MEAS-0101-1.
035000G015 ...(LA'S) . h ANSWER 7.08 (2.50) I a.
To prevent a loss of shutdown margin [+0.53 that could result l from the insurge of relatively diluted (boron concentrated) pressuri:er water C+0.53 caused by an RCS temperature drop and volume shrinkage C+0.53.
b.
An RCP start provides an adequate means of loop and pressuri:er mixing C+0.53 by use of RCP-driven pressurizer spray C+0.53.
REFERENCE 1.
Maine Yankee EOP ES-0.2. Step 2 and Background Document;
7..f6pp DL!$F5 _ r, NQBd@L.3,,GhNQ6UGL,,.,Et1E6G[,NGy_QND PAGE
S0R196QQ[C0l,_CQNIhgL ANSWERS -- MAINE YANKEE-88/08/09-GRUEL.
R.
ELO #EAS-0101-7.
000017K101 ...(NA'S) ANSWER 7.09 (2.00) 1.
fill upender pit by gravity from the RWST C+1.03 2.
after upender pit is full, remainder of cavity may be flooded (by normal means) by throttling open the RWST suction valves for the operating RHR pump.
C+[.p] A !Eet u% g Q & WM 4 e'";* f ' M.
REFERENCE 1.
Maine Yankee: Procedure No.
1-17-2, p.
1.
034000A102 ...(KA'S) ANSWER 7.10 (2.00) a.
(Personnel exposures) 1.
25 rems (or more) whole body C+0.53 2.
150 rems (or more) to skin C+0.53 3.
375 rems (or more) to extremities C+0.53 b.
(Material releases) release which if averaged over 24 hours would encoed 5000 times limits C+0.53 REFERENCE 1.
Maine Yankee Procedure No.
1-26-1, p.
12; ELO MSNO-0302-5.
194001K103 ...(KA'S)
- , 2t_ f OOL'EDUbf.S_!_N9bdel t _ ObN9bOOls _f_'UEbGE,NCY _QUD FAGE 67.
60010 LOC:1 COL _QQNJbg6 ANSWERB -- MAINE YANLEE-89/08/09-GRUEL.
R.
ANSWER 7.11 (2.50) 6.
1.
75 rem whole body C+0.53 2.
12.5 rom whole body [+0.53 b.
plant manager (or designee) C+0.53 c.
Long-terms increased likelihood of cancer, particularly leutemsa [+0.5J Short-terms none (blood changes) [+0.53 REFERENCE 1.
Maine Yankee Procedure No. 2.50.14, pp.
1 and 11; ELO #AD-0103-2.
194001K103 ...(KA'S)
_ _ _ _ - - - _ _ Q.__ODMJNI,SlyO][yG_th0C[QUS[5,_COND1110NS _QUD_6]MilQllGNS FAGE
3 ANSWERS ~~ MAINE YANKEE-88/08/09-GRUEL.
R.
ANSWER 8.01 (3.00) a.
1.
five C+0.53 2.
"O !-0_:r2. 9tO t^? 252 r-epi. !cnt pl-t _2'rty- _ g t _.. t n e m ! m -< g m y,. m.,a n, m m+n s car rn.em ann n.
_ o n 2.
. A.5.].cf At.h =re M M b 72 C o.Se] 3.
2 hours C+0.53 I b.
no C+0.53, refueling supervisor must be an SRO C+0.753 REFERENCE 1.
Maine Yankee Procedure No.
1-26-5, "Shift Manning and Overtime Requirements," pp.
1 through 5.
2.
Maine Yankee Technical Specifications 5.2: ELO #AD-0104-11.
194001A103 ...(KA'S) ANSWER 8.02 (1.00) 1.
crew document review book C'?.53 [ 4 $ e.S~.rW 2.
shift information book C : 7. -) .3.
cvi!Cd h REFERENCE 1.
Maine Yankee Procedure No.
1-26-3, pp. 2 and 3; ELO
- 5NO-0301-2.
194001A106 ...(KA*S) ANSWER 8.03 (2.50) a.
false (a second licensed operator is required) C+0.53 b.
true C+0.53 c.
false (PSS/ SOS may waive if high radiation involved) C+0.53 d.
false (may not defeat interlocks or safety features) C+0.53 c.
falso (may not operate under any circumstances) C+0.53 REFERENCE 1.
Maine Yankee: 0-14-1, Sections 4.5, 4.8.
4.10 5.1.7, and 5.1.15, pp. 3 through 6; ELO HM-0302-7, -8, and -10.
194001K102 ...(KA'S)
. . Et-BDUINih15611ME_EhgCEQUSESg_G9NDillQN92_QND_Lidil6I19NS PAGE
ANSWERS -- MAINE YANKEE-88/08/09-GRUEL.
R.
ANSWER 8.04 (2.50) a.
28 Feb 88 (day 59) + 184 days = 30 Aug 88 (day 243) C+1.03 D 88-t$4 $W F#J) b.
21 Feb 87 (day 52) [+0.53 + (3.25 x 184) C+0.53 = 11 Oct 88 (day 284) C+0.53 REFERENCE 1.
Maine Yankee: Technical Specification, Definitions, pp. 5 and 7, Section 4.0; ELO WSURV-0301-1.
194001A106 ...(KA'S) ANSWER 8.05 (1.50)
~ 1.
PSS C+0.53
2.
NSS C+0.53 3.
SOS C+0.53 REFERENCE
1.
Maine Ycnkee Procedure No.
1-26-2, p.
2.
194001A103 ...(KA'S) i
ANSWER O.06 (1.25) i i Excore detectors can have errors (of up to 10%) if not ! calibrated monthly C +0. 753 due to instrumentati on dri f t C+0.253 or core changes resulting from fuel depletion C+0.253.
REFERENCE 1.
Maine Yankee Technical Specification 3.1, pp. 3.1-1 and 3.1-2; ELO #SNO-0303-12.
015000A103 ...(KA'S) I k . i
h _Ql)tij N] Sib 0lJ.yE,_FJOCF,DL)FKS.,C(JN! IlJ ONS, _ AN!)_l.lM11 ATlO!)S F'AGC
3 ! ANSWERS -- MAINE YANLEE-08/08/09-GRtJEL. R.' ANSWER 8.07 (1.00) /. e k ptJ J e* Leo [*. r]
bring reactor subcritical C+0.53 9.
- -!=
- - =ngi- :-tm;
==='y=- p- - ': p=.--
- z t = :' -~
- 0 C3 REFERENCE 1.
Maine Yankee: Technical Specification 3.4, p.
3.4-1; ELO
- SNO-0303-10.
000027A204 000040K101 193010K107 ...(KA*S)
ANSWER 8.08 (1.00) 1.
any positive change in reactivity is not allowed C+0.53 2.
commence a reactor shutdown within one hour C+0.53 REFERENCE 1.
Maine Yankee: Technical Specifications 3.0.A.1.
3.5.B.
and 0.5.C.
pp. 3.0-1 and 3.5-1; ELO HSNO-0303-10.
004000G005 006000A207 ...(KA'S) ANSWER 8.09 (3.00) a.
C+0.753 b.
adequate water volume (10700 to 11700 ge11ons) C+0.53 adequate boron concentration (at least 1720 ppm boron) C+0.53 adequate nitrogen pressure (205 to 140 psig) C+0.53 open isolation valve (not required for full credit) c.
(A closed isolation valve must be opened within) 1 hour.
C+0.753 , REFERENCE 1.
Maine Yankee Technical Specification 3.6, pp. 3.6-1 and 3.6-2p ELO NSNO-0303-10.
006000G005 ...(KA'S)
.- . _.
. . f M. 0QMINJOT80lly[_PROGEDUEESs..GQND[IlONS _GND_LIMITDI!QNS PAGE
1 ANSWERS -- MAINE YANLEE-08/CD/09-GRUEL.
R.
, ANSWER 8.10 (1.50) Ensures that a sufficient quantity of baron can be injected to , ' maintain the core suberitical C+0.753 following an MSLB C+0.253 i concurrent with highest worth CEA stuck out C+0.253 and failure l of one ECCS train to function C+0.253.
REFERENCE 1.
Maino Yanl:ee Technical Specification 3.6.
p.
0.6-31 ELO
- 5NO-0303-12.
000040G004 006000G006' ...(KA*S) ANSWER 8.11 (1.50) L 1.
CEA in Group A, B, C, 1, 2, 3.
or 4 out of position by more . than 10 steps trom others in group.
C+0.53 2.
CEA in Subgroup 5A or SB out of position from others in , subgroup by more than 10 steps.
C+0.53 3.
Indicated subgroup position of 5A and 5B differ by more
than 15 steps.
C+0.53 { REFERENCE j
1.
Maine Yankee: Technical Specification 3.10, p. 3.10-11 ELO I
- SNO-0303-10.
i , I 014000K406 ...(MA'S)
' L b !
h I L ,
l t s !
' . l
8.. _00tl1NIS160lli,[;6QGEQUBEh,QQUQll1Q[JSg,,0NL(jg11GI!ONS PAGE 6H ANSWERS -- MAINE YANhEE-88 / 08 / 09-GRtJEL. R.
ANSWER 8.12 (3.00) a.
1.
primary vent stack C+0.51 2.
uncollected containment leakage [+0.53 3.
main uteam lines C+0.53 b.
at the ALERT level and above [+0.53 c.
1.
classify (and declare) the emergency C+0.53 2.
notify offsite authorities C+0.53 REFERENCE 1.
Maine Yankee: Emergency Plan, Section 6.3.0, p.
6.14.
2.
Maine Yankee Emergency Plan, Section 7.1, p.
7.1.
3.
Maine Yankee: Emergency Plan, Procedure No. 2.50.17, p.
1: TLO #SEO-0301.
194001A116 194001K103 ...(KA'S) ANSWER 8.13 (2.25) 4, r a,, s +.. s m 1, - s i r3 rm e + _ i g g _ s 7 _.
s_.irtry ;~ 7_ y t e - s C'2.752-b.
!- u ': d e - di ect rspr-"!cic^ r ! ! c e":t :-d ^;- ete-C-2.'"2
2.
e-clied i-itcente t 2t-t g p cgr - C-2.'52 REFERENCE 1.
Maine Yankees 10CFR55, Subparts 13 and 53.
199001A103 ...(KA'S) 42.. [.to fv. 5p.,7 ag3 w wa=:u_qap4 a m y c:. w c..sa [** &._..../ r m th.ar-A--) 3 m -.
b.
U* - a i wwA4 n-pe.? c a.se 7 s
/ U.
3.
NUCLEAR REGULATORY COMMISSIGN REACTOR OPERATOR LICENSE EXAMINATION FACILITY: _ljAINg_yANEEg____________ REACTOR TYPE: _PWR-qq__________________ DATE ADMINISTERED _@@Lg@Lg2________________ EXAMINER: _QRUg6t_6t_______________ CANDIDATE: _ Ic_ _ [g _ _ INSIEUgligNS_lg_g@NQ1Q81gt U30 separate paper for the answers.
Write answers on one side only.
Stcple quention sheet on top of the answer sheets.
Points for each qu2stion are indicateo in parentheses after the question.
The passing grade recuires at least 70% in each category and a final grade of at 1cest 80%. E:: ami n at i on papers will be picked up si :: (e) hours after tho examination utarts.
% OF CATEGORY % OF CANDIDATE'S CATEGORY __Y86YE_ _I9IG6 ___5G9EE___ _M669E__ ______________G8IE998X_____________ _EEt99__ _2Et90 ________ 1.
PRINCIPLES OF NUCLEAR POWER ___________ FLANT OPERATION. THERMODYNAMICS.
HEAT TRANSFER AND FLUID FLOW _EEt99__ _ set 99 ________ O.
PLANT DESIGN INCLUDING SAFETY ___________ AND EMERGENCY SYSTEMS _ __ _EE s.99 ________ 3.
INSTRUMENTS AND CONTROLS _ _ _ _ _ _ _ _ _.. _2Et99__ _;Etgg ________ 4.
PROCEDURES - NORMAL. ABNORMAL.
___________ EMERGENCY AND RADIOLOGICAL CONTROL 199t99__ ________% Totals ___________ Final Grade All work done on thi s e:: amination is my own.
I have neither given nor received aid.
___________________________________ Candidate's Signature r 't -
r-ic__EBlWGIE60s_0E_UuGLE68_EQUE5_E66SI_OEEE6IlOUr PAGE IUE5090'IU60 lG e t _UE 6I_IS e BSEE6_ @ U Q _E6U lp _E6 QE QUESTION 1.01 (2.00s ANSWER TRUE or FALSE to the following ' a.
Halving the reactor oeriod will double the SUR.
(0.5) 6.
If rea-+ne power is increased from 1 *'. at a stable SUR of 0.5 DFM, power will be at 5% in one minute.
(0.5) c.
It will take the same time for the reactor to go from C . to C. power as it will to go from 25*,. to 30% power with the same const>nt SUR.
(0.5) d.
If a positive reactivity addition to a critical r eactor results in a 1.0 DFM positive SUR. the same amount of negative reactivity addition will result in a 1.0 DFM negative SUR.
(0.5) (s**** CATEGORY 01 CONTINUED ON NEXT PAGE
- )
r- . 1o FR1NG][( Q,,O[_Gy(((GB_[QWgB_[(@N1_O[E69IlQU3 F' AGE ?. UW6M0tNNAM]QF:_HE01 ISBU!iEEE_099_ELUID_EL9'd i / a' / OUESTION 1.02 ( 1. 50 ), / Maine v a n t r:e i t-in h t, shutdown with a neutron countrate of 400 coa onc a boron c ' centration of 600 ppm.
A tcactivity ansortton of 1 *'. r h c et, il ts a n a shtitcown margin (ELMJ of 3 */.. CALCULATE the ne countra SHOW your work.
(1.5) . QUESTION 1.02 (1.50) Maine Yankee is in hot standby with a neutron countrate of 400 eps and a boron concentration of 600 ppm.
A reactivity insertion of 1% rho results in a shutdown margin (SDM) of 3%. CALCULATE the new countrate.
SHOW your work.
(1.5) . <4aa44 CATEGORY 01 CONTINUED ON NEXT PAGE *s **) . . . . - . - - - -.. . - ... - - ... -
it..._E810GitLEs_9E_UuG6EGB_E99E5_E6@UI_OE[b8IlQUt PAGE
IHEEdQQ10@UlCst_UE@l_16@UEEEB_6UQ_ELyl@_E(QW OUESTION 1.03 (2.00's The data given below was taken auring fuel loading into the core.
WHAT is tite predicted number at assemolios to obtain criticality? SHOW your work.
(2.0) Number of Assemnlies Loaded Neutron Countrato (cps)
50
63
125 (asass CATEGORY 01 CONTINUED ON NEXT PAGE sse44) - - -
Ic__EE1001ELEE_0E_UWGLE65_E9WES_ELsUI_0EEB6Il001 FAGE
IbEEb99106DIGEz bE6I_IE805EsS_60p_E6UJp_ELQU OUESTION 1.04 (2.00) For each at tne facters listed celow. DOE 5 the moderator temperr.ture cecificient become MORE tEGATIVE, LESS NEGATIVE. or REMAIN THE SAME es the caramuter is changed in the direction doctrined? A55UME normal acwcr condatiens.
a.
icriant temperaturte decreabes (0.5) (0.5) c.
- usr increaten (0,5)
c.
- ore oges a.
centrol rods are witharawn (0.5) (s**** CATEGORY 01 CONTINUED ON NEXT FAGE sesa:) . - ..
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ i._ _2 IM.ilE!.d5 E _GF._djs6E 6ti _EO'd ?@ _ (6 @ ff _(F,E R @ llOij L FAgg , J H_ E..F_M_ O_ i_W N A_;*l _I. C. 5. m.. E. A__ T__ _T_ R..._,N.. S.F_ E_ R_ _ A__ N_. D._ _F_ L_ U_ I_ D_ _ F_L. G_ W - ... _ - . _ CUE 5 TION !.05 (1.50) ' PLAIN WHY the ts n or, ped which o c c u r s-a t t. or a reactor *rlp , . fecm 100% cower lequilibrium nenon) is greater t h /* n the p ec. for r, trip frc>m CZ'. tower (ettualibrium :enons.
(1,5) i (44444 CATEGORY 01 CONTINUED ON NEXT FAGE a4***s
. - - .
Ir__h81NG{{([5_Q[_hg[([@$_&QWEB_E(@NI_QEE6@IlOG3 FAGE
.TUEBd99XN901GS _dEGI_IBONSE[$_QND_E(glD_E(QH
QUESTION 1.
(3.00) l ANSWER the folio ng questions regar.tng plant resocnse tollowing a reactor trip atter an r.t2nded power operatton.
c.
Reactor power imm ately ( thin one secondi drops to a certain value.
1.
"To WHAT value does eactor power drops (0.5) 2.
WHAT determines t is wer level? (1.0) b.
Following the immedi te drop.
eactor power decreases et a certain 3UR.
, , 1.
At WHAT SUR oes reactor powe subsequent 1v drop? (0.5) 2.
The react. power level one hour 4ter a reacter teto as apr o::1 matel y 1%. ExFLAIN he e:.1stence of this eactor power level in light f your respon e to part b.1.
(1.0) QUESTION 1.06 (3.00) ANSWER the following questions regarding plant response following a reactor trip after an oxtended power operation.
a.
Reactor power immediately (within one second) drops to a certain value.
I To WHAT value does reactor power drop? (0.5) I 1.
2.
WHAT detereines this power level? (1.0) - b.
Following the imeediate drop, reactor power decreases , at a certain SUR.
l 1.
At WHAT SUR does reacter power subsequently drop? (0.5) 2.
One hour after a normal reactor trip, nuclear instrueentation indicates approxieately 100 cps)
however, the actual reactor power level is approxiestely it.
EXPLAIN the existence of this reactor power level in light of your response to part b.1.
(1.0) < J ! (assas CATEGORY 01. CONTINUED ON NEXT PAGE sassa) - _ _ _ _ _ - _ _ - _ _. _ _ _ - -. _ _ _ _,. _ _ _ _ _ __
i.___.LE10.IE'.b.E_.YE_UWGb506_50 WEE _ELOUI_9EEEOIl90t FAGE a IdEEDODINedIcez_cE0I_IEOU5E56_6uG_ELY1D_ELOW CUELT I QJ 1.O' (2.50) M A t :iu v ani:c e r e..c t or p ow *e r is Stesov et IDE-:!. power.
ihe FC i nac e.er erativ cnoves the CEAs Ill for 45 ocends.
A35UME cod worth is 0.00St. aelt+-rho / step etio the ef f et ti ve cini ayed neutton froction t, 0.006.
CALCULATE the SUR i mmedi e t t+1 v ,V T E R e :o me t i cri stopt.. nHOW all.our wort.
iiTATE all s.s u u mp t i on s. s2.5) s& est CATEGORY 01 CONTINUED ON NEAT FAGE easae)
r 1.__tS.IUGIELE5_0E_UVOLE65_EOUE5_E6eUI_0EEEGIl00t PAGE
ISEEM0010601G3t_bEGI_IEedEEEE_900_E6ulp_EggW OUESTION 1.tB '4.00) ' i.15r four (4) p a r o n.et er s ori the prin arv plant attectino DNE uhtch can Do controlled by the roacter operator.
For eacn p a r e,tirr t e r IDENTIFY whether a DECIiEASE in cach will FsAISE.
NOT AFFECT. ce LOWER t he DNER.
(4.0) saaes* CATEGORY 01 CONTINUED ON NEXT FAGE eae66)
- _________________ _ __ _ . _ - _ _ _ _ . 1.
FRjNGlELES_QE_NgGLEQS_tQWES_E(GNI_QEQ6911gN PAGE
g IUE SUODYNQd},G$3,0(Gl 16QGS[[G,QUQ_E(y,1,Q,E(QW OUESTION 1.09 (1.501 s + ttel rod cac gap h6at transfer can be considered essentially ~ ..cnduction heat transfer.
WILL the heat transfer across the gep INCAEASE. DECREAEE, or NOT CHANGE for each of the tollowing? - ' c.
fuel. swelling (8.5) h.
higher reactor power (9.5) e.
gap gas diffu ' ton into the fuel (0.5) N l l l l QUESTION 1.09 (1.50) l l Fuel rod gas gap heat transfer can be considered essentially ' conduction heat transfer.
W!'.L the ability to transf er heat across the gap IN'REASE, DECREASE, or NOT CHANGE for each of the following? a.
fuel swelling (0.5) b.
higher reactor power (0.5) c.
gap gas pressure decreases (0.5) . (esses CATEGORY 01 CONTINUED ON NEXT PAGE sasas) - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _.
1.1_ _ E t i b ?. I E L E 5_0E _ bVC L G 05_ E 9 W E E _ E 669I_ ? E E E 0Il 00 F +4GE
it4hPJ90106di?st_UESI_IE894EES.ebp_ELUlp,ELQW QUECTIDN j.10 (1.50) The Meir,c ranteo reacter 1, in e naturas L:rculation couldcwn with +n RCS prresnuro of 1150 putg snd a T-ccid that in 75 deg F subcooles.
CALCUL ATE t he copro::i o. <t o s t eani generator steam prosauro at thtu condition.
(1.5) isteae CATEGORY 01 CONTINUED ON NEXT PAGE ee4*6)
it__EEI.UC ELEE_9E_UdELE66_EObs6_EL$dI_CEEE01190t FAGE 1 *J idEEd9910001 Git _UEGI_16GN@EE8_@UD_E(UlD_ELQlj UUESTION 1.11 (2.00) Tr.e Maino v'a n 6 o p reacter is operating at 100% power.
A FORV haa stuc6, open.
DETERMINE the apor o:: t mato lino temccrature which should be indicater dcwns.tream o+ the FORV tf c r o s sur 1 :: er pressure tu. ~5 put9 EHO6J alI wort, STATE 011 ascunptions.
(2.0) (attst CATEGORY 01 CONTINUED ON NEXT FAGE o8844)
.et__EElb;IELEi 9E_UWCLE68_E9WE6_E600I_0EEbOI1992 PAGE
HEF'UDXUeU1Gh. M OI_IB6UhEEB_eU!>_ELUID_ELow OUESTION 1.10 (1.50) A variable speed centrifugal pump operatos at 4S0 rom and craws 3 VW of power.
The initial flowrate is 100 gpn at a pecusure differential of 50 pst.
If pump speed in i n c r e t.s ed to 900 rpm.
WHAT will be the news (SHOW all war > ) o.
ticwrote? (0.5) b.
ocuer recuirements/ (0.5) c.
os efernnttal prousure.
50.5) (esses END CF CATEGORY 01 saass) . -
_ _ _ _. _ _ _ _ _ _ _ _ _ - _ _ __- Ez__ClOUI_DESlQU_INGLUDIUO_EOLEll_OUD_EUEBO6UCy_gygTCUD PAGE
- i. t a.. ! I t. ~. ..di t1.15) ANSWER the follows q questic regarding the CVCS.
a.
STATE t h re two ( ') pu post >s o+ the letdown (J r c y .alvos (LD-A-9.1 ) (1.0) b.
WHAT system des)'gn esture limits the overpressure of thes charging 1Yne d notream of the charging flow control valve,(CH-F- )? INCLUDE its location.
(0.75) QUESTION 2.01 (1.75) ANSWER the following questions regarding the CVCS.
a.
STATE the two (2) purposes of the letdown drag valvos (LD-A-9,10).
(1.0) b.
WHAT systes design feature limits the overpressure of the charging line downstreas of the charging flow control valve ICH-F-38)? INCLUDE its location within the systen.
(0.75) (4assa CATEGORY 02 CONTINUEL CN NEXT FAGE oseats
- Ri _ _ E L 6 !il _ C L E.I Q U _ I U G L U O100_ E 6 E E Il _900_ E d E S Q [ UGl_315IE U S FAGE
?LESTION 2.02 t2.00) Five metnods are evatlable to adenuatelv vent tno FCS cena rcmove the reautrement ter L T OP p r ot ec t i on. 412.-! a -1: M.
- c: c '. ;;;;. LIST four (4) of these aiuthods.
(2.0) c/tcw)rfdA+y J/m t***** CATEGORY C2 CONTINUED ON NEXT F AGE 44***)
.. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ Et._ELOUI_DE5190_10CLUD100_SGEEIY_000 EUESQEUGX_SYSIE05 PAGE le ihJLS i l uN ,. 0 :. s.. ;,0, ANSWER the follow no questions regardin the emergency diese! .;erme a t or S (EDGss.
TRUE or FAL.5E.
When the engan to manually started. the generator fauld w automatica ly flashed and its output breaker is manua y closed.
(8.5) b.
LIST'the normal so' rce o cooling water for 1.
DG-1A <g,53 ~. DG-1B ce,5) c.
The EDG temperat e is aantained at 180 degrees F.
HOW is this tem rature entrol accomplished? (1.0) d.
LIST the two .) condition which stco the EDG without 11.5..i-.pa time dela.. (1.0) en QUESTION 2.03 (3.50) ANSWER the following questions regarding the emergency diesel generators (EDGs).
a.
TRUE or FALSE.
When the engine is manually started. the generator field is automatically flashed and its output breaker is manually closed.
(0.5) b.
LIST the normal source of cooling water for 1.
DG-1A (0.5) 2.
DG-1B (0.5) c.
The EDG temperature is maintained at 180 degrees F.
HOW is this temperature control accomplished? (1.0) d.
LIST two (2) conditions which wou3d stop the EDG without an 11.5 minute time delay.
(1.0) (44486 CATEGORY 02 CONTINUED ON NEXT FAGE 6 sst)
- _ _ _ _ _ _ _ _ 's._ O 6dl. ME15d 1dGk W lU2.56E61Y.eND,,lidE6GEdi,4 jX~sIE!jE PAGE
OUEST10i: ~. 0 4 (1.MO> WibLME o LOCA non occurreo tollcwoo bv a vallo RAS.
STATE tho flowcath that estets no r ot urri uater f r oen the contatnnent t.uo p n s.; 6 to the RCS annumang no cperatcr action u. I S T rnajor ccmponenta in flowpatn creer. vslvaw not requirod).
(1.5) i s4:464 CATEGORf 00 CONTINUED ON NEXT FAGE 46e46)
L.__Lkebl..iEE100_luctug160_geEEIy_eug_EtE5gguci_iXQIgd5 FAGE
JUESTION 2.05 (2.00) ANSWER the following questions regardino the Emergency ano ou> I1 t arv Fuecwater system.
a.
LIST two (2) huction sources tur the emergency and auntltary feedwater a v s t o rn. (1.0) 2.
ETATE whether the emergency fenawater flow control valvos (EFW-A-101. 201. 301) will FAIL OFEtJ. FAIL LLD5ED or FAIL-AE-IS on e loss of instrument air.
(0,5) c.
WHAT will cause automatic closure of the nmergencv toeowater teclation v+1ves (AFW-A-026. 339 040)' (0.5) (***** CATEGORY 02 CONTINUED ON NEXT PAGE
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,- - - - - - - - - - - - - -. - - - - - - - - - - - 2.t.
?.669I_[6sigy_INCLypiUG_f,6Egli_60p_EME,5QEggi_diGIhdS FAr2C
OUES T I Ott . 06 (2.50) ANLidf( +he tallowing cuestions en the Fire Protection system, . s.
DESCRIEE the automatic resocnse to decreasing water pressure i ri t he f i r e p r ot tec t i or, c ys t err.. INCLUDE setcosnts.
(1.0) n.
LIST all of the locationn.4 hero the f ir e pumps can be .n a n v a l l '. started and uncopod.
(0.75) '>Hy are the two tiro pumor rophrated by a concrett* c.
e cncicsure7 (0.75) 544488 CATEGORf 02 CONTINUED ON NEXT FAGE
- 60s)
. - _
is..f!: OUI _RE319.U lbG4.99100_36EEIX._600_60E50EUGY. 3XFIEi.15 PAGE
. L'uti5 T I ON 2.07 C.00) LIST r,1 :* (6) o t' the seven automatic responsen which occur in the CVC5 system when en SIAs signal is generated.
C. 0) fl (***** CATEGORY 02 CONTINUED ON NEXT FACE
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- _ _ _ - - _ _ _ _ _ 'se.... F.kOUI_EE5100 ISE Wi!1d3_50E61I 6UD_liUE50ggy J1gTEUS PAGE
CUESTIQiJ 2.03 s1.001 ANSWER tho followsng Quettions on the Electeical Dit.tribut1en 5 v s t eir. a.
WH4T is the normal Supply ice 450 V but. 7" (0.5) b.
14 480 V bus G uupolv breater e031 +411u open. HOW would power be re-nupplied tf br ea k es r 6081 cculd i not be closod? (0,5)
1
l
(l**** CATEGORY 02 CONTINUED ON NEXT F AGE 6****) _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
sa__U 00f_GE5!QU 10G6UDibO_56EEIX_000_EdEEQENQY_515IEMS PAGE
OUESTION 2.09 (2,50) ANSWER the f ollowa nc questi ons on the RHR system.
a.
STATE the three (3) methods employed to itnsure the RhR flow control valvo (LSI-F-59) remtsins cpcn during normal clant operatton.
(1.5) b.
STATE tno two '2) reasons for recirculating the RHR . system before RHR cperation.
(1.0) (***** CATEGORY 02 CONTINUED ON NEXT PAGE
- s*)
E -_cL6dl_kE'5100_ LUG 6UQ1Gj_fedGly_eUQ_Gb5E@@UGX_SiSIEdg FAGE
- .
- QUESTION 2.10 (0.00) -NSWEh the f ollowing quer,tions on the rccctor coolant pumph (RCPs).
,4. WHAT is the purpobe of the flywheel? (0.7S) b.
WHY 15 the oil lift pump run timo limited to 5 minutes pesor to starting an ECF? (0.75) c.
Uncer 4. HAT three tM conditient tu cperation of an RCF permitted with two at the lower three coal staaet falleo? (1.5) , I e l (s**** CATEGORN 01 CONTINUED ON NEXT PAGE
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02_ _ L LGUT _ [[s 1 Q U_ J UC 6 W DIU d_ E 6E EIy _ sb[>_ E DE h Q E U Cy _ Sy yIE US FAGE
- 4 OUE3 TION 2.11 (2.25)
Fcr each of tne noted approximate seal cavity prosnuro c er.cl t 1 o n t, STATF whac5 reactor cool arit nunp (RCF) L e a l t t- ). to any, have tatled.
A55UMK the follewana indicatud p a r a me t or t+ : Fen Colcr Fressure Tap Locotton
..---
, -------------------
reo petween lower and nat adl e seels c l ut? between.ni adl e ano uncer sesla green cotween upper anc vapor semln men - 200 psis blue 1:C0 psis groen - 75 pat (0.75) - .. 75 putt blue - 75 psis green - 75 pr.1 (0.75) e.
hed -
- .
Fed - 250 pass blue - 250 pst: green ~ 250 ont (0.75)
! ! i , s46 46 END OF CATEGORY 02 66866)
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ - _ - _ _ _ ~' t.
. l u ? I E' lf3 O l 3 _t*U Q _ G g u l d O L.3 FAGE JS
V OUEST 10tJ ,u1 (t,3g) 40W will the CVCS system lotdown and charging responc when the in-ser.t.:o )ovel transnttter in the crossur1 ur 1evel control vvetem fetit HI" INCLUDE tocctiic pump and/or vol ve r espontoos, nSSUME system tu in auto.
(1.5) t***** CATEGORY 03 CONTINUED ON NEXT F AGE s**4 )
e I __itiSIEU97]I5.60D G90160LE FAGE
. OUESTIOlJ 2. 02 (~.50) i AN5WER the follcwing cuestions regarotno automatte ections based on tho stoam cenarator avstum caramteters.
ao LIST the two (2) cutomatic actions wn ch occur followsng a lou cteam generater level utgnal s ',5% ). (1.0) bo !f an blA5 occurs concurrent wath en sG pressure Itss than 400 coto,
- .
_IET t h c: tecencery sybttm p u n.p s wntch tric.
(0.75)
- .
ETATE WH1' these aumns are tripped.
(0.75) l l l , P
l (**664 CATEGORY 03 CONTINUED ON NEXT FAGE
- e*)
3 r... _lV 315 Ui_1I5N T 5.ON Q _LQ U T 5QL p RAGE
UUE 51 I Ul4 3.03 (2.50) LIST tne three (3) conditions which will ctiuse a CEA withdrewal prentbs-( C'w? ) to t>o igenerateo.
Alao STATE the condition when thew c a rt:ui t s can ce uvrussed or c i s asb l ed. 52.5)
1 l l l l l t l (s**se CATEGORY 03 CONTINUED ON NEXT PAGE
- )
_ _ _ _ _ _ _ _ _ _ _ E._.!U516UCEUIE_009 COUTCO65 FAGE
OUESTION 3.04 (;.50) ila r rio v'an tee i s at 100% o=wur.
A 1oss of voltace occurs on ihus c anc DG-15 recorvos an emergency start utgnal.
6.
WHAT bus connection /inteette breA6er traps cpen automaticallv" (0.5) L.
LIST three (3) c on ponent s s.n a c h Arc immectetely loaded (1.e.. breakers Y htst ) ' WH1CH of r h e e_ o componentu is v.ub s c ouen t i v thed trom the bue? ( 0. 0 ) l l i l l l
l t l l l
l
l l l (asses CATEGORY 00 CONTINUED ON NEXT FAGE **sts)
! -
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~ OUE tit I U.7 3.05 t2.00) ANEWEh TRUE cr FALSE for the + ol l owi no que.sti ons reaardi no st eam dumo ano turbine bvpear. control.
t.. The steam dump c orit r ol ubek a diffurence between the ste.nne herder pressure ano a ornusure uutpoint to coturmino the riumour at valvec to opten.
(0.5) o.
.Itthor ene of two interlocLs will prevent any turcino t.pav n or steam dump valvec from coening - low conoonstr .e. um cr steam nascer cressure icw.
(0.S) c'. '. :. t > ovpats Gwitch on the MCh c;.n tvpast tne . . .aw cenaenner. z.c u u m i nt erl oci.. (0,5) c.
Trm c on.o n n at i cri ot t hc t urt:1 no ovpast ono steam cumo 4 stem can hancle acout 75% of full load steam.
t0.5)
I (a4*** CATEGORY 03 CONTINUED ON NEXT PAGE 444s*) > - - .
7.r.__!USlEUU6U13 OUR 90blE % E PAGE
QUESTICf1 3.06 C. $0) A55tiMC the RCS is in the procesn et ttrano cooled down normaj1y and dupresnurinod o f t eer ce rescter trip.
Rreraurtror pressure Chennel A hat t a a l c+tj htch tut t.a s nct coon rosot.
RCS penssure 12 at 1400 ;;st g and 400 deg F.
Fressuri:er pressure safety Channel D then f.s t i s high.
DESCRIEE WHitT will occur as a rnsult at th!o 4ttuttion AND WHf 1t occurs.
INCLUDC setpotntt and coinctuences as applicabic.
(0.5) f i st **a CATEGORY 03 CONTINUED CN NEXT PAGE aaa*a) - - -
. _ _ - _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ h_._.10aliWEUT.5_t U!! G.CUIEM PAGE
CuESTICN l,. 0 7 (;.U01
- R5WER the tollowino questicns regarosna prenturt ce p r e s s ur r=
4nd level instrumentation.
a.
Luc ng 4,bnormalIv~htgh centatnment pretsure condstaons.
WILL the indscated p r e s s u r t.: e r pressure be EQUAL TG.
9mEATF.R THAN. or LEEL THAN ectual' EXFLAIN your reasoning.
(1.5) ti.
During annermally-high c o n t a i n e er.t temper 3turo condittent., WILL t h cs indicated preysurt:er level ec EDUAL TO. GREATER iHAla. er t.E55 Tr% N actuai ~ E A i-L n I N scur roecentnc.
si.C) (4***s CATEGORY 03 CONTINUED CN NEXT FAGE 446s8)
J u__D!315 YDb t!I.3_600_G OUIh04-- PAGE
OUCSTICN .cs <g,ggj For each at the followino pair e ut simu:toneous hF5 Instrument f.* 1 a ur u s. INIrlCM E i<nocner the reac*,cr rnould TFIF. NOT TRIF. or F RET RIF'. JUSTIFY. c,ur a n t.wo r end c ont.a der usch pair of feilures s e p ar ret e l y. A33UME clant 'n at 100% cower.
a.
T 1/ LF. r.d s c a t i c n tu Channel A iMis to 1700 pstg /4ND IM/LP indicatten to Channel C f alls to !!50 ostg.
(1,;5) L.
Chwnel b v v mn.vtri c otiwet f :i t l w to -0.5 (4ND oomer s u p p l '.- .c Chennal A orew+r f. t i,;. s l..- r ) . s (***** CATEGGRY 03 CONTINUED ON NEXT FAGE osees) i
_ _ _ _ _ _ _ _ _ _ _ -______ 71__e.% ifl i-Ul? l ui J 24IEUbR t' HEE 'J' ! -- OVESTIUN '. 09 t:. 50> Fcr ca:r' ci the folloutnq radiation monitort. 5 TATE tna L automatic fonettents), if env. per+ormeo en en clarmco eendtt&03.
a.
h M-L'c 01. Stean generater blowdown svatem (0,5) b.
.11-7401. Framary ecmoonent cooling water 1r.v v. r o m (0.5) e.
F, M - 7 9 0 : A.
Pe t rusr v + ont utoc6 spartscul0tes t0.L) .i.
i, m - - I c 2,. Containment sont: 3erten sgasi 50.Si , .;.
- N - e l '.' 7 Epent fue ct>ol
.tr e e (0.5) l t
! , l ! ! l l i ! $ , . I t ie6 tot CATEGORv 00 CONTINUED GN NEXT FAGE 66a64i
- 1s__IUDIEUUtVI4_su2 60bibOLt N.GE
OUEST1DrJ 3.10 +.00) AMEnER TAUE or FALSE t o the f olicwa reg reactor toolant 1000 tnterlcc6 statement 4.
a.
Thw ovpass valve eiust bo open before either T-hot or T-cold etco valvas can be shut.
(0.5) o.
A T-cold stop valvo cannot be coenco unless its associated cold leg temperature is within 20 deg F of the* haghost c010 1 eg t e.mper et ur e? 1 ri the ather incos.
(0.5)
- .
The 1 cop b vpate.
Al<e cannot be shut o ril e n c t h o . associatea loop T-not and T-colo + ten valves are ecen or the assoc 14tt.o RCP te ott.
(0,5) d.
The ACP wtll trip 14 either tno T-hot or T-cold stco valve 1s not iul1y open and tne Assoc 1eted bypat,h val ve* 19 not open.
(0.5) (66sta CATEGORY 03 CONTINUED ON NEAT FAGE ett44)
y.. _ _ _ _ _ _ l , ' ! 7 t... l d S I h V D E U 1 5 6 S D. 0 0 0 1 6 9 b h FAGE
l l
a.1 i t 1..t. ..i.
t.
a.
ANSWER TRUE or FA SE to the folio ng questn ons regarot ng , nuclear instrument tion.
[ L e.
The wndw range ogarttt ac channelu rerceive g i u;: l ev t.)
[ si gnal s from in e +t ston chambers.
(0.5) b.
The reactor power A s indicated in % above less-3 power on the wid ange logarithmic channels.
(0.5) i ! c.
The zero power mode bypass (Level 1) bistable automaticall disabl e the low coolant flow and ' TM/LF trnp, below O* ower.
L0.L) l i , ! ! WUESTION 3.11 +4v&O4 l ' t.sn3 , ANSWER TRUE or FALSE to the following questions regard 1* nuclear instrumentation.
, t a.- Durs power operations, the wide range logarithmte [ c nels receive flux level signals froe three ks g ge/ (0.5) saton chaebers.
! b.
The reactor power is indicated in 1 above 10**-8 (0.5) l power on the wide range logaritheic channels.
l c.
The zero power mode bypass (Level 1) bistable l autoestically disables the low coolant flow and l (0.5) l TM/LP trtpa below 21 power.
t f f ) ! l
l ! l t (seoss END OF CATEGORY 0; sesse,
I - - - - . . . - .
_ - _ _ _ l is.
CEEE dlUb.O. 2 I!E.$U.ibl s. tJL!$2 ".'OLs 5 dEE.EENC'f ' 'N E) E fiGE Jo ' e l "'bl.I.bieQGACbb l.E>ilITyk l l OUL57 ION 4.01 tL.OD) l AN;iWtiR t h t- +olloWino reaardirig M,mine r a n k t;e c p e r tit t e n t monoc.
l l 3.
Ocurat1ons memo 9-E-n aavi ses cpterator s to inanudl 1 y trin the r eactor insteac cit movino thr+ CEAs during a g> 1 c n t enutacwn uttn no .:',01 tim t a n tt coorattonal.
LMnT adverne c e n u t t. i c h t s b u t t io m i t 1 g es t o d.' $0.5) b.
Oper a t t enta meimo 1 + :. addresses MLFF rwctrculstten vol ve-enrrettnnel t e r_ t t ri o. It statne that durnha much
- t* = t t o g t h e a s t o r. t a t e o M DF F'.ttu n t ce scolated and
. c e,. r r e. e.u r 1,* c ti. tA.C d '. te r t t-ccnottton 1n Drino c.ttigated.
(1.0) i , ! , t
I . l , L
' , , (a664a CATEGorn c4 CONTINUEL GN NEXT F AGE ea4a4) . .
.___. _ _ ___ ____ ______ ___ ____ _ - - -
, i.... sigeguhE;t. y,NQh5%. AhyOQM%,F0($GGNQX, QUD F f.GE .7 . b@lt%VQMOL GONJRUh ' t f
f umaiiuN 4.o t.. t ci )
j t .M.UMF t h 44 t the pan 61 ler is, " L. c s s a t Instrumt.>nt 14us DP/ LAC" l .i n,t " t u * t. of (nntrum n' l.i., LI 'I AC" actsvato.
a.
.' 4 t he t;usos er o utcc+eiv!!v repowered per AOP 2-!!. 51 ATE the two (d cttons whtch must be taken tamediately.
(1.5) / b.
Under WHAT corydt tion (s) must AOP ? 11 be ex1ted and EOP E-0 be e tered? \\ (1.5)
\\ \\ ! l i ' I
, QUESTION 4.02 (3.00) \\ ASSUME that the panel alarms. ' Loss of Instrument Bus OP/ TAC *
and * Loss of Instrument Bus DP/ PAC' activate.
' ' t a.
If the buses are successfully repowered per AOP 2-11.
' STATI the two (2) actions which must be taken tenediately.
(1.5) i , b.
Under what THREE conditions must AOP 2-11 be exited and the E0Ps entered? (1.5) ! ,
} \\
, L i I ! i !
! ! l { ' ! tesets CATEGORY 04 CONTINUED ON NE AT F AGE 4464*) l . - -
. . _ _ _ _ _ _ _ _ _ _ _ _ _ st .EGGEkUEES :_bOdd66 UEUE0d'.b.SUEbEUUGY @NQ PAGE 's e6Pl.%90 lGeL _G00I50L-VUESTION 4.00 ( 75, M n t rit; <0n6 cc r, c u e r 0.t i n o et 100'; poner when e croppvo etu a c c.a r s. WHAT.ction(s) must oc t a 6 tf n ti e necend CC6 should crop while the first C E A i t.
fullv insterted i ts the corc' (0.75) l l l , (eeeae CATEGOM 04 CONTINUED ON NEXT FAGE oeaa6) . . _
_ _ _. _ _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ $'.- E60GEDWEE.5 :.UQ5MeL 01.<UO550L.rMg60ENCY,,99Q FAGE
! 0019LQQ1G06 GQUT,696 t Jtil(fION 4.04 (P.IL) Matnc Yan6et-is eqeratano e '50% power.
Letdown end c tier a a no flews uncomti errat c.
ACF wal water supp1v eno r.r urre tiows . ! occome erratic. en SG eco + low su lost.
o.
WHAT tu the mo Itkely cause of thts plant response? (0.75) ,
b.
WHAT initta) acti n(s) should be taken within the fieat minute? (1.5)
. , QUESTION 4.04 (2.25)
Maine Yankee is operating at SOE power.
Letdown and charging
flows become erratic. RCP seal water supply and return flows i become erratice and SG main feed flow is lost.
a.
WHAT is the oost likely cause of this plant responee? (0.75) b.
WHAT initial action (s) should be taken within the
first minute? (1.5) i , ' . l i f t ' \\ ' I ! l i ! (seasa CATEGOR( 04 CONTINUED ON NEXT FAGF 6eeoe) l
i ' . . .. . -, _ _ _ _ _ _ _ _. _ __
_ _ - _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _- .. _ _ __ _ _ - _. _ _ _ _ _ _ _ _ _ _ _ , 4o 069CFDVI.46_T,09b0%a.OI'UQ6d b _Ed66960GY. 609 PAGE
hett!.9t,90lG06 6001604,
r P i (Nti n1 10t4 4.Os . t '.. N s j / rem Fower i or Safety Inject 4on." has I E-0.
"Emergency Sh tdown neon an t er ces. ASSU !NG hst one AC omr*rgency bus tu energized.
i pot.s t p l e t r ant.: t a oren t three EOrs entst wi t hi n the i mmect s at e ! setten + t em u of E-0.
t.!ST these t h r it e (3) EOPs AND the l condatton uncer wha h ransition to each is made.
(3.8) L > . I \\ , t L I F ! l ( I QUESTION 4.05 (3.00) E-0, ' Emergency Shutdown from Power or Safety Injection.' has been entered.
ASSUM!NG that one AC emergency bus is energized,
possible transitions to three E0Ps/FRPs exist within the samediate ! action steps of E 0.
LIST these three (3) E0Ps/FRPs AND the l condition under ehich transition to each is made.
(3.0) f i i r i i l ! , I
I r r ! i ! , f ' t I i < sea 66 CATEGCRY 04 CONTINUED ON NEXT FAGE oaeaa) ( l i - - . -.- t _
_ _ _ _ _ - - _ _ _ _ _ _ - _ - - _ _ _ _ _ I:
3 x _. l F.D d i V5 0_.'.'.fiQ E fj 6 ta s._OFf Ji!bMOL s.
I t1Ch0RdQ f U'.JP P A(d.'
E @ l?6091 gob _EQLJI69L DUESTION 4. 0 e.
(0.00) , A rrector tric hat, o c c u r r a.'d cJ u o to a etetton vlec60ur.
f i. A- 0. u. "Louis c-M1 AC Fow.tr."
14 enturoc.
l i a.
r10W ts en uncontrollec cooldown p r avv en t eo * it.0) , ! ts. F ar t of the ammediato rosnonse to thia event ancnodes at 1 t 1 ca+ 1 ors of AF6J putop * t 4.r t. le .',FW pump F - i?.is ocws not it t. a r t t rom the cont r 01 ecom. LIST t ris. tour s4) r r. r t en t, an one ret re e.ur t r es pi r t e-Iccally tw e r.r e- . t. : 4 m a t a n ; to Io: ally start AFW oumo F-255, 12.Os , t I s , l a l t ? > < I L i + I ! i l ! i ! t ! !
, f ! i !
I k ie6aa6 CATEGORY 04 CCNT1hWED ON NEXT FAGE o66st) l , l ' , -... - - - - - - . - -. - - . - - - - - -.
- d..._ibCEiW6EE..UO60SLt_UU.UdiUUlt_CdE69EdGl_00P FWGE
deD10LWOICOL_GGulEUt OUE.sTICN 4.07 si.'0s a
FDF F-~. "Stram benerator T u ti er hutit ur e" tSGTR; provadon yundanco for reponatng to,4n F.GT6 LlhT throp th s oc c;n oc r y a nni c at i c.nw used t ri E-2. t o t aun t s, y a ruptureo EG.
(1.0) , t , ! ! i , I L , f , , . M i [ [ . , t t b (seles CATEGORY 04 CONTINUED GN NEXT FAGE sate 6) , i i ( l -
' _ f 9*.-_EbgCEDklBES _NQ6d@L _9hNQ5d@Lt J:d[60[N[1_9ND FAGE
i 690.196gGIq9L_CQNIhQL OULSTION 4.08 ( 1. '.'D ) ANSWER the followint questions reg d i rig the fire ortgade r equir ements spect+4 d an Froced c 1-2e-5.
"Sta t i t Ib rin i ng .i n d Overtime Requirem ts."
ani Maine rantee Tachnical Spec 1 f t cat i cris.
> c.
WHAT is the minimum mber of fire brigade members needed on-site at a times? (0.5)
b.
WHAT qualificati s mu t the replacement for the Fire E Brigade Team Le der pos ess assuming a replacement tu needed by anca acttatto ? (0.75) QUESTION 4.08 (1.25)
ANSWER the following questions regarding the f. ire brigade requirements specified in Precedure 1-26-5, "Shift Manning and Overcime Requirements," and Maina Yankee Technical , Specifications.
a.
WHAT is the minimue number of fira brigade menbera needed on-site at all times? (0.5) b.
If the Fire Brigade Team Leader becomes incapacitated, may a Reactor Operator assume the responsibility as thu Fire Brigade Team Lotdur? Justify your answer.
(0.75) , l l l
! s i (4 4 4 4 a CATEGOR/ 04 CONTINUED ON NEXT F AGE *****) . _----. . - _.. . . _ _ _
S:. E.EGI:EOU6EE_2 UO60$l-bEUCEdbbt EdEOBEUC'J. dWD Pf4GE
$60196001C66 GOUIEOL.
QUESTIOil 4.09 (1.00) LIST the two (2) books which must be reviewed and initialed bv tne on-coming control room operator durtno s,nift turnover.
(1,0) i I
t6saa* CATEGOR'r 04 CONTINUED ON NEXT P(4GE oa
- )
2 __tBQCEQUEEs_ _UQEU66x_6@UDEd@Lt_sd5E@EUGy_@UQ FAGE
E69196001C66_G90IE06 OUESTION 4.10 (1.50) ANSWER TRUE or FALSE to the following quettions on Fracedure 0-14-1.
"Whtte Tagging Froceaure".
c.
A vingle Itcensed operator (usually the PSS/ SOS) can validate that a tagoing order will perform its antenced f unc ti ori.
(0.5) b.
A taoging order $snall not be enanged without first obt ai ni ng pernia nt on trom all h ol cis and thn FSS/ SOS.
(0.5) c.
Tagged equipment may be operated uncer emergency conditions only at tne d2scretion et the FSS/ SOS.
(0.5) (***** CATEGORY 04 CONTINUED ON NEXT PAGE
- 4)
4:_ E.tl1GEDUBEQ_;_UOh00t, _6hyO600L, _[dEBO[NGy_@ND PAGE
fl6L).I 9bl2G I Cf*L. CON ) ht]L utjt.5 T I ON 4.1i s i.. "L s ANSWER the following uestions rigarding 10CFR55. "Operators' L t e ein s e s. " a.
ST ATF the quar ter l y st ft requirements to maintain an active license.
(0.75) WHAT two (2) cond ion must be met to allow control b.
room equipment m )napula ion by an unlicensed individual? (1.5) , QUESTION 4.11 (2.25) ANSWER the following questions regarding 10CFR55, "Operators' Licenses."
a.
You have been off-shift for two months and have just been requested tc go back on shift.
Are you allowed to assume the shift? Justify your answer.
(1.00) b.
The primary Auxiliary Operator needs to peerfore a surveillance on P-14A charging pump.
He requests permission to put the pump in pull-to-lock.
Will you allow him to manipu3 ate the controls? Justify your answer.
(1.25) (stats CATEGORY 04 CONTINUED ON NEXT PAGE **** )
d s _ _d62C60b'EE h _ z_UObO06 t _6 e UOEMBL t_ MUE E@ s UGi_gN D PAGE
BesiL4001C66_COUIE0e OUESTIGr1 4.12 (1.50s The Maine Yankee Radiaticn Protection Manual estaollsnes ilve rad >ation control areas (RCAsi classifications.
STATE rne minimum exposure 11mitu associated with the dettnation of each of the followtng areas.
1.
Rantation area (1.0) Htgn raatation area.
(0.5) _.
(64444 CATEGORY 04 CONTINUED ON NEXT PAGE
- 4)
Ss__tsgGEpU6dE_;_UQEd@6t_UBU9EdObt_EdE6050Gi_6U9 FAGE
b6010!-90lC6s_G90IE96 OUESTION 4.13 (2.00) Detr3 n e a sericus plant emergency, operators may be called upon to assist in <aearch and recovery operations in tne clant.
c.
In such cases. WHAT whole body dose 1s an operator permitted to recunvet 1.
to orino an Injured w o r s e>r to safetv? (0.5) ' '. to repair plant e qu i o meen i. n n el crevent further plant aegradation? (0.5) b.
WHAT are the possible of f etcts at receiving radiation em eesur e of the level s of SD rem? INCLUDE short-term and l on g -r. er m effects.
(1.0) (**4** END GF CATEGORY 04 es*ss) (************* END OF EXAMINATION
- )
. _ _ _ _ _ _ - _ _ _ _ _ _ ................____............................................___........ EQUATION SHEET ..........._______..____......._____............_______... __.....__.._____ . . , Where mi = m2 (density)i(velocity)1(area)1 = (density)2(velocity)2(area)2 .......___......__...._____.........____....____...._________............. KE="{2 where V = specific PE = mgh PE + KE +P V 3 1 = PE +KE +P Y22
2
7 volume P = Pressure ............................................................................ , Q = mc (T-Tin) Q = VA (T-Tstm) Q = rn(h -h ) p out ave t 2 ...........__.........._____.......__.........__....................____.. P = P 10(SUR)(t) P = P e /T SUR = 26.06 T = (B-p)t t o o T p .................................................................... _..... CR (1-Keff1) = CR (I'Eeff2) CR=S/(1-X,ff) delta K = (K,ff-1)
2 (1.K,ffg) (1-K,ff) x 100% SDM = M = (1-Keff2) K,ff ..........................__..............................___....._____. __ 1 = A e (aecay conttant)x(t) (2)_, 0.693 A - decay constant = t
1/2 1/2 .,..........................................................................
l Water Parameters Miscellaneous Conversions
1 gallon = 8.345 lbs 1 Curie = 3.7 x 10 dps 1 gallon = 3.78 liters 1 kg = 2.21 lbs
1 ft3 = 7.48 gallons 1 hp = 2.54 x 10 Btu /hr
6 Density =62.4lbg/ft 1 MW = 3.41 x 10. Btu /hr Density = 1 gm/cm 1 Stu = 778 ft-lbf , ' Heat of Vaporization = 970 Btu /lbm Degrees F = (1.8 x Degrees C) + 32 Heat of Fusion = 144 Btu /lbm 1 inch = 2.54 centimeters 2 1 Atm = 14.7 psia = 29.9 in Hg g = 32.174 ft-lbm/lbf-sec ...__......___....................__...............................__...... , P . , ! .. . _, _. - - _ -. - _ -
-- - -.,.. -, - _.
_ _. - _ - - - -
. . .. . ,a r b FWI NG,(LLil,OL NUU([QB_[QW[b.,[LGUI_OCE;h&llgN PAGE
3 I U E 6091tY NQU [ p S y _ b G Q] _169N S E E 8_ @yD_ E ( Ul p,[(QW ANSWERS ~~ MAINE YANUEE-88/08/09-GRUEL., R.
i I
, ANSWER 1.01 (2.00) I a.
true C+0.53 b.
false (power will be 3%) C+0.53 c.
true C+0.53 d.
false (limited by fission product decay rat.es) C+0.53 ! t REFERENCE [ 1.
Maine Yankee: Lesson Plan, RO-L-1.10, pp. 2 through 6, ELO
- CRC-0101-60.
l
192003K106 192003K109 ...(KA'S) '
' ANSWER 1.02 (1.50) l f SDM = K2 - 1, so K2 = 1 3% or 0.97 C+0.53 - , K1 = K2 - delta rho, so K1 = 0.97 - 0.01 = 0.96 C+0.53 '
CR2 = CR(1 - K1)/(1 - K2) = 400 (0.04)/(0.03) [ i CR2 = 533 cps (525 to 5.35 cps will give full credit if
approximation is not used) C+0.53 ! REFERENCE ! ' ! l 1.
tlaine Ya n i.ee : Lesson Plan, RO-L-1.13, pp. 1 and 5, TLO
- CRC-0101.
i,. ! -
2.
Maine Yantce: Lesson Plan, RO-L-1.10.
p.
2, ELO "
- CRC-0101-58.
- 204000K519
...(KA'S) i
! I i l ! i i e b ! , t . - - -,. -..,,.. - -, -. ..-w- -. -
.--.-------.-c
-- ~.
J.1_. L UI ngl LL E S _ gE,yuG L( 86_ COWE h _ E(Oy l _ OEE 691100 t f' AGE GO 10tbMODYN601GS _UEOl_I69NSEEh_OUQ_E(ylp_E(gy
ANSWhRS -- MAINF VANi;EE-88/08/09-GRUEL.
R.
ANSWER 1.03 (2.00) 1/M (i ) CR(c)/CR(i) [+0.53 = 1/M(1) = 50/50 = 1.00 1/M(2) 50/63 = 0.8 C+0.53 = 1/M(3) 50/125 = 0.4 C+0.53 = This can be plotted to show that criticality (1/M=0) is predicted at 30 (29 to 31) assemblies.
C+0.53 -- OR -- Since the last 5 assemblies halved the 1/M value C+1.03, another 5 should make the reactor critical C+1.03.
REFERENCE 1.
Maine Yankee Lesson Plan, RO-L-1.13, pp. 7 and 8, TLO # CRC-0102, 192008K106 ...(KA'S) ANSWER 1.04 (2.00) a.
less negative C+0.53 i b.
more negative C+0.52 , c.
more negativo C+0.53 d.
less negative C+0.53 ,
, , REFERENCE , i 1.
Maine Yankee: Lesson Plan, RO-L-1.11, pp. 27 through 29, t ELO # CRC-0101-31, -79, and -80.
' 2.
M,2ine Yankee: TDB, Figures 2.2.1.1, 2.2.1.2, and 2.2.1.3.
l , 192004K103 192004K106 ...(KA'S) , .
I ! ? . i . l s I j l , ,
_ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ .__ __-__________________ _____ _ ______________________.___ _ _. _-_ - ______ - _ - __ _ ____-_________-. Az__EBINCjlL(5_QE_NQGLE@$_tQWEh_[L8NI_OEE891]QN PAGE
t IUESNOQXNOMJC@t_UE91_Ih9NSEE8_eNQ [LU{D_E(QW ANSWERS -- MAINE YANREE-88 / 08 / 09-GF<UE L. R.
ANSWER 1.05 (1.50) Xenon production after a reactor trip is due solely to the decay of iodine C+0.753 and ther e is more todane in the core at 100% power than at 50% power C+0.753.
REFERENCE 1.
Maine Yankee Lesson Plan, RO-L-1.12, pp. O and 9, ELO # CRC-0101-90.
192006K107 ...(KA'S) ANSWER 1.06 (3.00) a.
1.
6% (5% to 7%) C+0.53 2.
This level i s due to (the sv.beri tical multiplicationof) delayed neutrons.
C+1.0J b.
1.
-1/3 dpm C+0.53 2.
(A -1/3 dpm SUR over a one-hour period would produce a 20-decade drop in reactor power.)
Reactor power decreases to only 1% (inntead of mur.h lower) due to the presence of decay heat.
C+1.03 REFERENCE 1.
Maine Yankee Lesson Plan, RO-L-1.9, pp. 3 through 6.
ELO
- CRC-0101-54 and -55.
200007K104 000007K105 192008K123 192009M127 ...(KA'S)
_ 1.___E6J NQJ El,ES.pE. (4UCLEOS,.COWEB. FSONT,0CEGGllpN,. PAGE
IUEbdQDyN60J QS,,UEGI_IgeNSEEB_9ND_ELylD_ELQW ANSWERS -- MAINE YANLEE-88/08/09-GRUEL, R.
ANSWER 1.07 (2.50) rho)/ rho x lambda (Qiven on equation sheet) T= (beta - lambda = 0.08 sec-1 (given on equation sheet) beta = 0.006 (given in question) C+0.253 rod speed is 40 steps / min C+0.253 rho = (45 sec)(1 min /60 sec) (-0.000% del ta-rho / step) (40 steps / min) (Q 4 ;.fpA A swd) = -0.24% C+1.03 _ after rod motion stops: SUR = 26/T (given on equation shoot) = 26 (tambda x rho)/(beta - cho) = 26 (0.09(-2.4E-0)}/(6E-3 - (-2.4E-0)> = 26 (-1.92E-4)/(8.4E-3) = -0.6 dpm (-0.63 to -0.56 dpm) C+1.03 REFERENCE 1.
Maino Yankee Leswon Plan. RO-L-1.10, pp. 6 and 7, ELO # CRC-0101-63.
19200BK124 ...(KA'S) ANSWER 1.00 (4.00) 1.
reactor power C+0.53 (docreaso will) RAISE DNBR C+0.53 2.
reactor cool ant flow rate C+0.53 (decrease will) LOWER DNBR C+0.53 3.
reactor coolant inlet temperature C+0.53 (docrease will) RAISE DNDR C+0.53 4.
pressurt:er pressure C+0.53 (decrease will) LOWER DNDR C+0.53 REFERENCE 1.
Maine Yankee Lesson Plan. RO-L-7.3, pp. 14 and 15, ELO
- PPM-0103-10.
002000A101 002000A103 003000h501 193008K105 ...(kA'S)
It__EblG91 ELLS.0E_NUGLE96_EOWGB_EL901_gEEE@IlQU1 PAGE
IUEB000YUOMICha _UGOI_ lBOUFFEh_QUQ,E(ylp, F(OW ANSWERS -- MAINE YANLEE-88/08/09-GRUEL.
R.
ANSWER 1.09 (1.50) a.
increase C+0.53 b.
i n c r e a r,e [+0.53 c.
decreaue C+0.53 REFERENCE 1.
Maine Yankee Lesson Plan, RO-L-7.3. pp.
2, 3, and 7 ELO #FFM-0103-2.
-4 and-24.
193008K116 ...(KA'S) ANSWER 1.10 (1.50) From Steam Tabl es 565 deg F.
C+0.53 Tsat = For 75 deg F subcooling. T-cold = 565 - 75 = 490 deg F C+0.5] 490 dog F) = 625 psia C+0.53 Psteam = Psat (for T = (4/8-6 So) REFERENCE 1.
Maine Yankee Lesson Plan. RO-L-7.1, p p.- 14 through 17, ELO
- PPM-0101-18.
193000K125 ...(kA*S)
. _ _ _ _ - _ _ _ _ _ _ _ _ - , .l z __LU I NGICLE5_QE_NWQLh8b_EQWhB,[(QNI_QEE60llgN PAGE S4 , IUtB000!NQDJgSg_dE91_lh0NQEE6_@ND_E(Uly_E(QW , ANSWERS -- MAINE YANt.EE-89/08/09-GRUEL.
R.
t L
ANSWER 1.11 (2.00) . 1.
a s s u n.e isenthalpic expansson (constant enthalphy) C+0.53 j 2.
from steam tables , , i 1118 BTU /lbm - deg F (sat. steam at 2250 psia) f+0.53 h1 = ! 3.
assume line pressure of 2 psig C+0.53 (i.e., quench tant pressure) , j i i 4.
From Mollier diagram move horizontally for constant j
l enthalpy expansion to 17 psis line.
Temperature is read as approximately 220 deg F (can also use saturated steam ' i pressure table) C+0.53.
I f REFERENCE ) 1.
Maine Yankee Lesson Plan. RD-L-7.1.
p.
20, [ i ELO #PFM-0101-18 and -0103-18.
200008K101 000008K302 010000U502 193004U115 ...(KA'S) i i ! ! ! ANSWER 1.12 (1.50) I a.
(100 gpm) (900 rpm /450 rpm) = 200 gpm C+0.53 I' b.
(3 kW) (900 rpm /450 rpm)*43 = 24 kW C+0.53 i c.
(50 psi) (900 rpm /450 rpm)*s2 = 200 psi [+0.53 i , j REFERENCE , I l
ELO 1.
Maine Yankee: Lesson Plan, RO-L-7.4, p.
,
' l
- PPM-0104-16.
i 191004K105 ...(KA'S)
i !
i s
, !
! ' s , I
t I ? ' - - - -
L
i E.
PLANI pyj l O(J,1NGLt_lDING_ S AEE T Y _ AND_E ME RGENGY_Sf hlEMS PAGE
ANSWERS -- MAINE YANLEE-80/08/09-6RUEL.
R.
ANSWER 2.01 (1.75) a.
letdown flowrate control C+0.53 letdown pressure reduction C+0.53
I b.
a sprang loaded check valve C+0.53 which bypasses ! CH-M-44 (loop 2 charging isolation valve) C+0.253
REFERENCE l t 1.
Maine Yankee System Description NS-4, pp. 22, 46 and 73: ' ELO #CVCS-0103-2.
004000A207 004000K603 006000K108 ...(KA'S) ANSWER 2.02 (2.00) < 1.
the reactor head off [ f 2.
the pressuri:er manway off 3.
one pressuri:ce safety valve removed 4.
one PORV removed and its isolation valve 015ABLED in the open position j r 5.
both FORV centrol switches in "Open" and their isolation ! valves open ( Any four (4) C+0.53 each, +2.0 mansmum.
i REFERENCE [ } 1.
Maine Yankees OP 1-1, p.
4; ELO #RCS-0101-8.
l OO2000K410 ...(KA'S) i I . i i i !
h
-. . Ez _LLON1 DE51gN_JNCL,yD,lOQ_h8Ehlf_QUD.[DKhGENGi_SySIEUs PAGE L6 ANSWE RS -- MAINE YANL EE-08/08/09-GRUEL.
R.
ANSWER 2.03 (3.50) a.
false (field must be manually flashed) C+0.53 b.
1.
FCC water C+0.53 2.
SCC water C+0.53 c.
A temperature regulating valve directs water through the heat exchanger or through the bypass line.
C+1.03 d.
1.
overspeed i 0.53 C A @ e,f jgj 2.
manually positioning fuel racks to "no fuel" position I-2.52 REFERENCE 1.
Maine Yankee System Description AS-12. pp.
2.
7, 9, 13, and 14; ELO #DG-0101-2, -3 and -0102-8.
064000A406 064000K102 064000K402 ...(KA*S) ANSWER 2.04 (1.50) 1.
containment spray pump (s) C+0.53 2.
PHR heat exchanger (s) C+0.53 3.
HFS! pump (s) C+0.5J REFERENCE 1.
Maine Yankee System Description NS-5.
p.
7; ELO
- ECCS-0101-2.
006020A304 006020K403 ...(KA*S) l l l l ANSWER 2.05 (2.00) - l a.
1.
DWST C+0.53 2.
PWST C+4.53 b.
fall open C+0.53 c.
low SG pressure (en the associated SG) C+0.53 REFERENCE 1.
Maine Yann:eet System Description PGS-13, pp.
1.
9,
and
.-. . U.__ELGN1_ PES]GU,lNGLUDJNG.56FEly_9ND EME6GENQy_SySIEM5 FAGE
ANSWERS -- MAINE YANUEE-88/08/09-GRUEL.
R.
13: ELO #ArW-0101-2 and -14.
061000A207 061000K401 061000K414 ...(KA'S) r ANSWER 2,06 (2.50) I a.
The motor driven pump starts C+0.25] when yard loop i pressure decreases to 90 psig C+0.253 and the diesel driven pump starts C+0.25] when pressure has decreased to 80 pang C+0.053.
i b.
started locally C+0.23 or from the CR C+0.153 , stopped locally C+0.23 or at the breaker (f or MD pump) C+0.2J l i c.
The concrete wall is a fire enclosure C+0.53 in case of a fire due to the diesel fuel oil system C+0.253.
.
REFERENCE ]
s l 1.
Maine Yankee AS-8, pp. 15, 39, and 62; ELO #FF-0101-4, j-5, and-7.
086000<201 096000K402 ...(KA'S) , i , ' ANSWER 2.07 (3.00) e ! 1.
stancby charging pump starts !
2.
charging pump suction swaps to RWS7 from VCT ! 3.
letdown flow i sol a t es ! ! 4.
normal charging path isolates j 5.
fill header valve (CH-F-70) closes . I 6.
RCP seal water supply ('.oses l 7.
charging pump discharge goes to HFS1 headers l 'n y s W M3 .00 maximum.
, REFERENCE I 1.
Maine Yankeet NS-4 p.
97; ELO #ECCS-0101-2.
! 006000K100 006000K405 006000A304 ...(KA'S) t . -- . . _ - -.-. .- - - -
- -
,-. - _-__ .., _
- ,
n Et__ELOU1_DEE10N,1N[(yQly@_@6[[ly_@ND EDEBQENCY_QX@l[D3 PAGE
ANSWERS -- MAINE YANLEE-88/08/09-GRUEL, R.
ANSWER 2.08 (1.00) a.
4160 V bus 5 (thru uformer 507) C+0.53 b.
close tie breaker from 400 V bus 7 (7TO) C+0.53 REFEF.ENCE 1.
Maino Yankec Figure PGG-18-1; ELO #AC-0101-9.
262000A205 062000K407 ...(KA'S) ANSWER 2.09 (2.50) a.
1.
The control switch (FIC-306) is placed in the LOCKED OPEN position (which interrupts the output signal).
C+0.53 2.
LSI-F-59 is mechanically blocked open (with a valve stem collar).
C+0.53 3.
The air supply i s isolated from the valve diaphragm.
C+0.53 b.
1.
to ensure boron concentration is above that required C:0.5 O.
to verify operability of system check valves (LSI-50 and -51) +M
.t u = &r% L y s.g:,,<as [s,if A T 4.sv 4 & J REFERENCE - r 1.
Maine Yankee NS-6, p.
13: ELD #RHR-0101-10 and -11.
2.
Maine Yankee Procedure 1-13-1, p.
9.
005000K402 006C00K410 ...(MA'S)
, Ut__ELBUl_RESjpN,1NC(UplNg_$@[EIY_8Up_EMEBQENCY_SYSIEMS PAGE
ANSWERS -- MAINE YANLEE-88/08/09-GRUEL.
R.
ANSWER .10 (3.00) a.
Ensures minimum heat removal, needed to prevent immediate core damage, is provided (provide coastdown RCS flow) C+0.753 b.
prevent oil foaming and loss of pressure C+0.753 c.
1.
acceptable seal cavity tamperature (< 200 dog F) C+0.53 2.
acceptable seal water return temperature (< 200 deg F) C+0.53 3.
CVCS can handle neal return flow C+0.53 REFERENCE 1.
Maine Yankce: NS-2.
p.
27; ELO ERCP-0101-6, -8, and -16.
2.
Maine Yankee: Procedure 1-10-7, Caution prior to Step 6.2.2. Step 6.4.3 and 6.4.4, pp. 5 and 8.
OW3000K410 003000K602 003000K603 ...(KA'S) ANSWER 2.11 (2.05) a.
lower seal (has failed) C+0.753 b.
middle and upper seals (have failedi C+0.753 c.
asl three seals (have failed) C+0.75,7 REFERENCE Maine Yankeen Figure NE--2-14; ELO #RCP-0101-00.
000000A001 ...(tA'S) _
. _ _ _ _ _ ._ . ._ .-. __ - , , ~, _.F.J0lbUttt NIS,0ND_C991 hQL6 F' AGE
ANSWERS -- MAINE YANKEE-88/09/09-GRUEL, R.-
'
ANSWER 3.01 (1.50) l 1.
letdown drag valve (LD-A-9 or LD-A-10 or both if selected) opens C+0.53 , 2.
charging flow control valve (CH-F-08) closes C+0.53 l 3.
standby charging pump stops if running C+0.53
i REFERENCE 1.
Maine Yankees NS-4, pp. 72, 73, and 74: ELO #CVCS-0102-10.
' i-103-2.
l 011000A210 ...(KA'S)
i ! ANSWER 3.02 (2.50)
a.
motor driven auxiliary feedwater pumps start C+0.53
reactor (and turbine) trip C+0.53 I l i b.
1.
all main feed pumps trip C+0.253 i i all condensate pumps trip C+0.253 v j-all heater drain pumps trip C+0.253 2.
assures CG with steam line break is not fed C+0.753 i REFERENCF.
t 1.
Maine Yankee System Description PGS-15, pp. 11 and 123 ELO
- SG-Ht01-2, ELO #MFW-0101-5, ELO #AFW-0101-5.
059000K416 061000K402 ...(KA'S) ANSWER 3.03 (2.50) 1.
high startup rate pretrip (1.5 dpm) C+0.53, disabled below 1048-4*/. power C+0.53 2.
variable overpower protrip C+0.53 3.
TM/LP protrip (variable) C+0.53, disabled below 1048-4'/. power C+0.53 REFERENCE 1.
Maine Yankec MS-9 p.
4Di' ELO #CEDS-0101-.. - , e 2t,_INQlRUMENTS,AND_GON1ROLb FAGE
ANSWERS -- MAINE YANKEE-88/08/09-GRUEL.
R.
, 001000K407 ...(KA'S) ! l
- '
ANSWER 3.04 (2.50) ! a.
4T6 C+0.53 k ? b.
1.
P-14D charging pump (or P-145 charging pump if aligned I ao a "B") C+0.53 L r 2.
P-29B SW pump C+0.53 i 3.
P-29D SW pump C+0.53 I one service water pump will trip back open C+0.53 , , REFERENCE , 1.
Maine Yankee: System Description AS-12, pp. 58 and 59: ELO
- AC-0101-14 and #DG-0102-2.
[ 064000A307 064030K101 ...(KA'S)
!
ANSWER 3.05 (2.006 i
{ a.
falso (uses T-avg) C+0.53 i b.
true C+0.53 l c.
false (low stea.nlino press) (+0.53 i ' ! d.
f alse (50%) C+0.51 t REFERENCE 1.
Maine Yankee P35-14, pp.
1, 2, and 31 ELO #SD-0101-4 and-5.
241020K407 041020K411 041020K4io ...(KA*S) ANSWER 3.06 (2.50) Automatic unblocking of SIAS occurs when 2 of 4 pressure channels C +0.53 sense pressure greater than 1685 psig C+0.53.
Since 2 of 4 pressure channels C+0.53 mense pressure less than 1585 psig C+0.53. SIAS will occur C+0.53.
V ^= N : f / M V $s N.44 Wd f [/. o] REFERENCE 1.
Maine Yankee System Description NS-5, p.
371 ELO
- ESF-0101-1 and-4.
012000K412 010000K501 ...(KA'S)
. _ st__1NS1hydENIS_ONp_GQN1BQL@ PAGE
ANSWERS -- MAINE YANLEE-88/08/09-GRUEL, R.
ANSWER 3.07 (3.00) a.
Indicated pressure will be LESS THAN the actual pressure C+0.53.
Pressurt er pressure instruments read relative to containment pressure C+0.53.
Therefore, as conta1nment pressure increasus, the indicated pressurizer pressure decreases C+0.53.
b.
The indicated l evel will be GREATER THAN the actual icvel C+0.53 The reference leg fluid would be less dense from the higher temperature C+0.53, resulting in lower delta P and thus greater indicated level C+0.53.
REFERENCE 1.
Maine Yankeet TDB Figure 1.3.13 ELO #PLC-0101-5.
191002K108 191002K111 ...(MA*S) . ANSWER 3.08 (2.50) 4.
should not trip C+0.53, only one failure exceeds pressurizer pressure C+0.753 b.
should tei? C+0.53, trip signa) produced by power supply failues, second trip f r om low symmetrar. offset failure C+Z.753 < REFERENCL f 1.
Maine Yanseet Sestum Description NS-12, pp. 20. 21, 24, and
Table NS-12-1 (p. 34): ELO #RPS-0101-2.
i $ I 012000X402 ...(KA'S) l i e . , i k h t ! i . - - - -. . . -
- _ _ _ _ _ _ _ _ _ _ _. 2 __I.NSI.hyMENIG_ONQ, CONTROLS FACE 67.
. ANGWERS -- MAINE YANLEE-88/09/09-GRUEL.
R.
ANSWER 3.09 (2.50) a.
no aCtlen C+0.53 b.
shuts nurge t a n i: vent C+0.53 c.
trips Fan-2 C+0.53 d.
stops containment purge (in the ref ueling mode) (+0.53 e.
stops new fuel elevator upward a.otion C+0.53 REFERENCE 1.
Mai.ne Yankee System Description AS-18, Table AS-18-1, p.
34: ELO #RMS-0101-7.
034000F600 073000K401 ... ( F. A ' S ) ANSWER 3.10 (0.00) a.
true C+0.53 b, true C+0.53 c.
true C+0.53 d.
t r i.i e (CAF I no.*melly closvd during power ops) C+0.53 REr'EFENCE 1.
Ma4ae Yanice System Dectription NS-2. pp. 4 and 5 ELO
- RCS-0101-5.
t 2.
Maine Yanteet Operations F-ocedure 09-1-10-7, Section 1.0.
p.
1.
303000E411 ...(KA'S) ANSWIR 3.11 > !. E ' r[/. c ) o 52 Dele U /N - s - ~, ean b.
falso (1084-7) C+0.53 c.
false (allows manual bypass) C+0.53 REFERENCE 1.
Maine Yankeus NS-10, pp. O and 10 ELO #N!-0101-1.
-3 and-6.
015000A400 015000M406 015000V603 ...(KA'S) .
_ _ _ - _ _ _ _ _ _ _ _ - _ _ --__ _ _. _ _ _ _ _ _ _ _ _ __ _ _ ___________ _ _ _ _ _ _ _ _ _ - _ __ _ _ _ l 4t__Eb!)CEDUBLW_:_UOh006t_0bu9BD662_EdhbOEUGl_009 PAGE
50D196091G06.G9UIb96 ANSWERS -- MAINE YANKEE-89/08/0Y-GRUEL.
R.
ANSWER 4.01 (2.00) , a.
the potential for CEA coil damago (caused by coil i energt:ation under high coil temperature conditions) C+1.03 ' b.
the potential for water hammer when the valve is opened C+1.03 REFERENCE 1.
Maine Yankee Operations memo 9-D-6.
and 9-D-3; ELO
- SNO-0302-9.
001000A201 059000K504 193006K104 ...(KA'S) i ANSWER 4.02 (3.00) , a.
1.
normaltro chargir.g and letdown C+0.753 l 2.
normalize condensate pumps C+0.753
b.
If 4160 V but 5 or 6 is cause of i nstree.eret bus power loss C+0.~53 and eeiergency diesci for bus affected cannot be j brought on line C+0.7S3.
( Q l.
Q Ci,4 Gn $) REFERdNCE t. // /Pf t p. ry
/ru y eM sqfe. J'v.CJ l ,
2.
a 1.
Maine Yankees Frocedure No. AOP 2-11; ELO #EAs-0150~5.
000057A219 000057K301 ...(KA'S) ! f . ! [
1 ANSWER 4.03 (.75) , trip the reactor C + 0', 2nd tu-bin (and enter E-0) [*? 252 I
REFERENCE
1.
Maine Yankee AOP 2-21, p.
ELO #EAS-0150-5.
001000A203 ...(KA'S) [ i I , ! ! . - - -. - -. - -. . - -. . .
3.._ _ th0C(L)U6[h_;_Ug6006 3_6kygbd@6 t _ EUGBQE UQ'1_ OND PAGE
BOD 1.9L90.i cet.cggI60t.
ANSWF. RS -- MAINE YANFEE-80/08/09-GRUEL.
R.
ANSWER 4.04 (2.25) a.
loss of control air C+0.753 .7.9~ b.
1.
trip reactor C + 0,4f) 2 :d tu-b : r "*2.222 2.
trip the reactor coolant pumps (within 45 seconds) C+0.75] REFERENCE 1.
Maine Yankoe: AOP 2-28. pp.
I through Og ELO #EAS-0150-2 and-5.
0000654206 000065K300 ...<KA'S) ANSWER 4.05 (3.00) 1.
FR-5.1 4"Nuclear Powesr Generation /ATWS") C+0.52 all trtppable CEAs not inserted C+0.53 2.
ES-0.1 ("Reactor Trip Respoque") (+0.53 57AS not required C+0.52 3.
FR-H.1 ("Loss of Sacondar y Huat Sink *) f+0.5] fendwater flow n o *. established C+0.53 REFERENCE 1.
Maine Yanlee: E-0.
"Emurgency Shutdow., from Power or Safety injection." Stups 2, 5, and 10: ELO WEAG-0101-8.
000007h301 ...(VA'S)
Az lbVGEUVEM : UVbd0lt ODNUbMOL s _EMESSENGLGNp PAGF ea.
60010LOGICOL_ CON 1 hot ANSWERS -- MAINE YANLEE-88/08/09-GRLIFL.
R.
ANSWER 4.06 (3.00) c.
(Immediate) closure of the EFCVs C+1.03 b.
1.
check if steam supply is open (MS-T-163) C+0.53 2.
check sf AFW overspeed trip is reset L+0.53 ' 3.
vent AFW pump (to eltmtnate steam binding) C+0.53
ensure an SG steam suppl y header isolation valve is open C+0.53 REFERENCE e 1.
Maine Yankee ECA-0.0, Steps 3 end 5: ELO #E AS.-0101-6.
000035K302 ...(KA'S) ANSWEA 4.07 (1.50) 1.
NR \\cvvi racing unrixpectedly 2.
high SG sample activity 3.
high radiation f:*cm any stoam inne
hign radiation from SG blowdown 5.
high steam /fued tiow mismatch - Any three (.3 ) C+0.53 each, +1.5 mansmum.
REFERENCE 1.
Maine Yanetee: EOP.
E-3, Step 21 ELO #EAS-0103-7.
000030A203 ...(KA'S)
. I hi rt.I,l st n. ) t, ,Ni% M.H, A);rJiihMeu.i_F_r_h_.Fjtgry_.N_,eyaly F (p,r c.
b e ti t ti t it. l t e il t !!N 1 Fg)l, A!6W6.li!, - N.i ! Ni i nrJi i i_ - u6 / ru, W,- ont ei L.
i<. ANSWF.h 4.08 (1.25) a.
(: vrr [+0.5) b.
r m y _ 7e 3 _g (. 9 7. _3 g.
g=1 3 _. = 1 g g t ;.1 _, _. _,=6_ _, _ _ _. _ __ g _ ;. __ 4_. i _a - r r. S ra J.. c.
o _ 3 3,,, _,
1 "
hEFEF i 1.
Masno N ani cre Frocedurr No.
1-26-5.
"Shtft Mantit rig and Overtime h.* qu i r ement s. " pp.
I and 2.
2.
Matne Y a n i. c e : Techntcal Sp r> c 1 i i c a t 1 on t 5. 2 : ELO DAD-0104-11.
19 4 0 01 A 10'*. ...O A'S) ANSWER 4.00 (1.00) 1.
Crew Document Review B o e l' C+0.53 2.
Shaft Informat1en Bool-C+0.53 AEFERENCE 1.
Maine Nan 6ce: Froceou o Nc,. 1 - 2e -3.
p.
4: ELO 400-0101-1.
t94001A10e ...OA*3) , AilHWEA 4.10 ( 1. 50 ) a.
f a l s e-(a second Itcensed oper.rtor i t. coautred) L+0.53 b.
true C+0.5] c.
false (may not operate under any circumstances) C+0.5) REFERENCE 1.
Maino Yan6 ee 0-14-1. Settions 4.5.
4.8.
and 5.1.7 pp. O through 5: ELO #M- 030.2-7.
194001F102 ...O A'5)
I hl)CI l_'lJFjLp. ; Nt ih Mijl
- 9Jilhi.Vit, t,,F;MF IjGE Nij i (pJls l'At L cH F6alill>L L)p ill(jl L()N 1 hl)L liN L, W E h b -- - M141 NF
- v oNi I L
-- Em / 00.' 0 9 - t h t)L L. h.
f.ss l'o.so) 4 . A * + d # 5 J P w u '.=* = = CL. . = -- & W* -_^. y' wi. & d d y(=sh [d.fW7m %_ e -_-n ) _
b. A)e Co.pf) ,,A-'.& ~-- J ) AM M& meQY M [d.so) ANSWER 4.11 (2.25) 1x1 2._, s _ __ _
_ 1_g.n.
_- _.t_.
,r3 2+ ., - _7 g 3 2 n._. t - . , 3.
,, ! _'. "_ j b.
1- >>~d'- di-et s>w-i='~-o~ !!cer>eed t;er++- r - 0 ' 't ?- _ - F2 0_??2 E_ t" el4wuc 1 inner t<eintng p-' y r-REFERENCE 1.
Meine Yankees 10CFR55. Subparts 13 and 50.
199001A10; ...(KA'5) ANSWER 4.12 (1.50) 1, 5 meem in 1 he C+0.53 or 100 mrea,in 5 contentt a ve dayt, C+0.51 2.
excess of 100 mrem in 1 hr Cto.53 REFERENCL 1.
h)ar.e Yankcc Rad:ataon F r et er: t i on Manuci.
p.
0-2: ELO nAD-0100-5.
i 19400D.100 ...O A*5)
t i ANSWEA 4.13 (2.00) a.
1.
75 rom whole bony (+0.51
2.
12.5 rem whole bodv C+0.53
b.
Long-terms increased 14.folshood of cancer, particularly ' ! leutemia C+0.53 ' Short-terms none (blood changes) C+0.53
r REFERENCE 1.
Maine YanLues h ocedure No. 2.50.14 p.
11: ELO MAD-0103-2.
194001K103 ...(LA'5) t I \\ ' - - - .. }}