IR 05000423/1986031
| ML20207S699 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 03/03/1987 |
| From: | Collins S, Keller R, Norris B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20207S690 | List: |
| References | |
| 50-423-86-31OL, NUDOCS 8703200189 | |
| Download: ML20207S699 (140) | |
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{{#Wiki_filter:U. S. NUCLEAR REGULATORY COMMISSION REGION I OPERATOR LICENSING EXAMINATION REPORT EXAMINATION REPORT NO. 86-31.(0L) FACILITY DOCKET NO. S0-423 FACILITY LICENSE NO. CPPR-113 i LICENSEE: Northeast Nuclear Energy Company P.O. Box 270 Hartford, Connecticut 06141-0270 FACILITY: Millstone Unit 3 EXAMINATION DATES: December 15-19, 1986 CHIEF EXAMINER: IY B~ S. No ris, R actor Engineer (Examiner)
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REVIEWED BY: W 40 F0,f R. M. Keller, Chidf, Projects Section 1C 1 'M' ff 7 Date APPROVED BY: h/lh)d $d%1 6. J. Coirins,. Deputy Director, DRP Date SUMMARY: Five Senior Reactor Operator (SRO) candidates, seven Reactor Operator (RO) candidates, and one Instructor Certification (IC) candidate were
, examined during this period. All candidates received their licenses /certifica-tion with the exception of one SRO candidate who failed the simulator portion of the operating examinatio PDR ADOCK 05000423 V .PDR - _ _ _ _ - _ _
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REPORT DETAILS i TYPE OF EXAMSi Replacement EXAM RESULTS: R0 SRO -Inst. Cert Pass / Fail Pass / Fail Pass / Fail ~ Written Exam- 7/0 4/0 1/0 Oral Exam 7/0 5/0 1/0 Simulator Exam 7/0 4/1 1/0 Overall 7/0 4/1 1/0 CHIEF EXAMINER AT SITE: B. S. Norris, NRC OTHER EXAMINERS: D. H. Coe, NRC N. F. Dudley, NRC N. C. Jensen, EG&G T. J.-Kenny, NRC B. A. Picker, EG&G P. D. Swetland, NRC R. R. Temps, NRC
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' The followire is a summary of generic knowledge or ability weaknesses which were .ted during the written and operating examinations. These ,
weaknesses are provided to allow an assessment of the effectiveness of the training program, and should be considered when developing future requali-fication programs. Future examinations may audit these knowleges and abilitie The ability to use the Emergency Plan to classify accident condi-tion The knowledge of the amount of decay heat that is produced after a reactor shutdow The knowledge of the method used~to cooldown the reactor coolant after various changes in the steam dump syste The knowledge of the effect of the Tavg signal.on various control system The knowledge of the effects of an instrument failure on the Cold Overpressure Protection Syste The knowledge of what actions should be-taken if a Response-Not-Obtained (RNO) cannot be satisfied during the performance of the Emergency Operating Procedure . The knowledge of what conditions are necessary to remove safety tags from equipmen . Personnel present at Exit Meeting: NRC B. S. Norris, Reactor Engineer (Examiner) N. F. Dudley, Lead Reactor Engineer (Examiner) T. J. Kenny, Senior Resident Inspecter, Salem P. D. Swetland, Senior Resident Inspector, Haddam Neck
'R. R. Temps, Reactor Engineer (Examiner)
Facility K. L. Burton, Unit 3 Operations Supervisor H. F. Haynes, Manager, Operator Training R. F. Martin, Unit 3 Operator Training M. J. Moehlmann, ATS, Operator Training S. E. Scace, Station Superintendent, Millstone R. G. Stotts, Supervisor, Operator Training-i
4 Summary of comments made at Exit Meeting: i It was noted by the Chief Examiner that most of the candidates performed very well in the simulator, both board manipulations and use of the proce-dures; especially noted was the effective and efficient use of the Emer-gency Operating Procedures (EOPs). Additionally, the candidates exhibited a good understanding and familiarity of the Piping and Instrument Diagrams (P& ids).
It was noted by the Chief Examiner that many of the SR0 candidates could not properly classify accident conditions using the E-Pla It was noted by the Chief Examiner that " Adverse Containment" is used in the interpretation of the E0Ps, but it is defined only in the background documents. The facility stated that this would be incorporated into the next revision of the E0P . It was noted by the Chief Examiner that the cleanliness of the plant was much improved compared to September, 198 It was noted by the Chief Examiner that during one of the plant walk-throughs that two different revisions of E0P-3503 " Shutdown Outside Control Room" were in the plant. In the Control Room Revision 3 (6/16/86) was being used, but at the Auxiliary Shutdown Panel Revision 2 (11/5/85) was in the binder. This item has been turned over to the MP3 Senior Resident Inspector for followup. During the simulator portion of the examination, an evaluation was made of the operators' understanding of the Emergency Operating Procedure The simulator scenarios included:
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Steam Generator Tube Rupture
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Turbine Trip with no Reactor Trip
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Main Steam Rupture
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Loss of Coolant Accident followed by a Loss of Offsite Power
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Loss of All Feed
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Control Rod Ejection
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Failed Fuel with a Steam Generator Tube Leak
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Feed Water Rupture Inside Containment
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Earthquake followed by an RCS Cold Leg Rupture Results of the evaluation are: I The operators were familiar with their responsibilities and with the required actions during the emergencies, both individually and as a tea The procedures were performed by the minimum staff identified in the Technical Specification ;
- 5 The operators did not physically interfere with each other while performing the E0P i The operators did not duplicate actions unless required by procedure (i .e. , independent verification). Where transitions were necessary_from one E0P to another E0P or to other procedures, precautions'were taken to ensure that all necessary steps, prerequisites and initial conditions were met or completed. The operators were knowledgeable about where to enter and exit the other procedure . The R0 and SR0 written examinations and answer keys are enclosed in Attachments 1 and 2; facility comments on the written examinations, and the NRC resolutions, are enclosed in Attachments 3 & 4. As noted on Attachments 3&4, the system descriptions need to be updated on a continuing basis as plant modifications are mad Attachments: Written Examination and Answer Key - R0 Written Examinations and Answer Key - SRO Facility Comments on the R0 Written Examination and NRC Resolution Facility Comments on the SRO Written Examination and NRC Resolution i
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i U. S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION FACILITY: _MILLSTgNE_2.____ _ REACTOR TYPE: _PWR-WEg4 ______________ DATE ADMINISTERED: _@6fj_2/15________________ EXAMINER: _NgRRISz_Dz_$. _ ,_ _ _ CANDIDATE: dk ([ .[ INSISUCIIQN5_IQ_C6UDID61El Use separate paper for the answer Write answers on one side onl Staple question sheet on top of the answer sheet Points for each question ee indicated in pe entheses after the question. The passing grade req; ires at least 7t^ " . in each category and a final grade of at least 80 Examination papers wili be picked up sit (6) hours after the examinatior start ~4 OF CATEGORY % OF CANDIDATE'S CATEGORY __y66UE_ _I0166 ___@ggEL___ _266UE__ ______________C6IEQQEX_,,___________ _2E199__ _2Et99 ____._______ _ _ _ _ _ . . . _ . _ PFINCIPLEO OF IJUCLEAR POWE7 PLANT OPERATION, THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW _2Ez99-_ _25sgg ___________ ________ PLANT DESIGN INCLUDING EAFETY AND EMERGENCY SYSTEMS 2.3. 4~b _ _z____ _2Ez29 ____--_____ ________ INSTRUMENTS AND CONTROLS _2Ezgg__ _g5 99 ___________ ________ PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL 19g199__ ___________ Totals Final Grade All work done on this examination is my ow I have neither given nor received ai Candidate's Signature g
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NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules apply: Cheating on the examination means an automatic denial of your application and could result in more severe penaltie . Restroom trips are to be limited and only one candidate at a time may leav You must avoid all contacts with anyone outside the examination r oorc. to avoid even the appearance or possibility of cheatin . Use black ink or dart pencil gnly to facilitate legible reproduction . Print your name in the blank provided on the cover sheet of the examinatio . Fill in the date on the cover sheet of the examination (i f necessary). Use only the p ager provided for answer . Frint you nar,e i t. the upper right-hent corner of the first page ci each secti on of the answer shee . Consecutively number each cmsw4r sheet, write "End of Ccitegory __" as appropriate, start each category on a neti page, write gnly gn gn; sidg of the paper , c.n c; write "Last Page' on the last answer shee . Numt-er each e r. s w a tu catecc y and number, 4cr eMampl .4, . Slip at lesnt tir y line b e t w: e r each answe . Sepa ate a r t.wer sheets f r om pad End plate finished answer sheets face doon on your desk c- tabl . Lise ab brevi at i cm 3 oni, ii t h are common 1y used in iaci1ity ;_1 t e r_ s t_u ce . 13. The point voluo for eacn questien :s indicatec in parentheses after the
- question ena c+r o e- use* aw a qu i c c- f or the depth of answer require . Show all calculeticos, methode, or assumptions used to obtain an answer to mathematic +1 problems whether indicated in the question or no . Partial credit may be gi ve Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLAN . If p arts of the examination are not clear as to intent, ask questions of the e >1a .3 Ln er_ onl . You must sign the statement on the cover sheet that indicates that the work is your own and you have not received or becn given assistance in completing the examsnatio Th 2 s- must be done a+ter the es
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(1) E:: am questicos on to (2) Exam aids - figures, tables, et (3) Answer pages ir:cluding figures which are part of the answe Turn in your copy of the examination and all pages used to a7swer the examination question Turn in all scrap paper and the balante of the paper that you did not use for answering the question d. Leasc the e:. amination area, as dcfined by t h e- eneminer . If a f t e."
ieav;ngs you ee foand in tt i c a . = e. v.h i l e the e~ec.nstion is still n p"OgrEsh, yot } I CerWE rit ? y L. 9 c er.) ed ()' rE,. C. C .
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IUESd?DYEBUICg,_HEGI_IESUgEEB_6ND_E6UID_E6gy OUESTION 1.01 (3.00) The reactor is at.15% power, equilibrium Xenon and Samarium, boron concentration is 1200 ppm, BOL, Control Bani: C rods are at 200 step Using Figures 1.1 to 1.11: What will be the final baron concentration if power is raised to 100%, ARO, steady state conditions? State which figures you us State all assumptionc and show all wor (2.401 How many gallons of pure water or boric acid will have to be added?
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DUESTION 1.62 C.ON , The Ur= : t 3 calculated Shutdown Margin is 10% delte f./I' acsuming the most r reactive control rod is 1000 pc The Source Ra r.o 1 count rate is 50 cp Show sl1 wer; and ut.ato a..y asna,ptita Cons i der eacti situatior sepa atel , What would t,e thc f i n e.: count rate i4 the shutdown banks are fully withcrewn? (-ssucc t"* thatdown bank rod worth is 5600 pc Wi + e t would be the finel cou,t rate if a 100 ppm d i l u t i or. of the RCS w e r t- performud? GUEDllON 1 . 0 ". (T.75) A reactor at POL is critical at 10E(-9) amp Rods are withdrawn at 48 steps per minute for 10 seconds in bank sequence, Calculate the SL'R i mmedi ately AFTER rod motion stop Assume differential rod worth is 10 pcm/ step, effective delayed neutron fraction is 0.006 and the effective precursor decay constant is 0.1 sec- (1.25) Compared to part (a) obove, HOW and WHY would the SUR change if the initial conditions were at EOL? No calculations are necessar (0.75) Conpared with part (a) ebove, HOU and WHY would tho SU! change if it were j ust bef or e rod mo t i a. is stopped' No calcul6tions are necessar (0.75)
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_ w PEINQlELEg_QE_NUQ6EGE_EQWEE_E66NI_QEEEGIlgN t PAGE 3 - ISEEdODYNGdlCgt_SE61_lE6NSEEE_QND_E6QlD_ELQW QUESTION 1.04 (2.50) What is the suocooling margin of the plant if the f ollowing conditions exist: (1.00) That = 587 F Tavg = 572 F Tcold = 557 F Ppzr = 2235 psig Psg = 1033 psig If power is raised from 50% to 100%, how will the subcooling margin change (increase, decrease, or remain the same)? Justif (0.75) Which one of the following conditions would result in the smallest subcooling margir." Assuma RCS pressure is the same for all case Justi' (0.75) Centrolled natural circulation cooldown immscistely following a reactor trip f rom loss of flo . Continued operation at 5% powe . All RCFe'ere opc-r ed i ng e t n or n.al no-los: temperature after an e.:tendeu st.utdow . QUZETIDN 1.05 (2.251 If r eac t or power >= Increeser fsom 50% to 10J.r4, how wi.1 DI FFEREN11 AL rod wortr> chang.e (Increa=c. d ec r e a r,e , or remain the same) for the following cond i t i on L Justley your answe Consider each cese separatel Rod position and baron cor. centr a t i on sre held ccn st ant , temperature is allowed t c ct-t;e e a u , Bo*on is held constant, rods are withdrawn from 150 steps to maintein temperature constan Red position is constent, boron concentration is diluted to maintain temperature constan ( t t' 4 4 4 CATEGORs 01 CONTINUED CN NEXT PAM (14*4) f
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ISEBOOpyg8DIC53_ME6I_IB6BSEEB_8UD_E6UID_E60W OUECTION 1.06 (1.50) WHAT percentage of full power is produced by decay heat at the followino times after a reactor shutdown from 100% power? Assume equilibrium was reached prior to shutdow One second after shutdow One hour after shutdow One de.y after shutdow CUEST I n:, 1. t C t2.0 ' 1he reactn i =, in Mcce 1. , c'. E!.utdown banks are full out, and tr.e control banLL ace withdrauri to 18J stepu or. Bent. Using the belc. information e.id F1gcr e !.12, d e t e r r.;; n e the criticai barcn conceottation by e. 1/M plo Sha sll wari: bor o. : -co entration Lourt Rete 15;' ppa 100 cp.> tU 125 13:9 1 t,5 1 Of_ 0 240 110: 445 10 :" > 333C QUESTION 1.00 f r . ->:)) Fiquee 1.13 show: e s y s t e .or ce tnd t. h t-e characteristic curvem for tv, centrifugal pt s Eact. pung is eenpped wi t!i e c. h e c valve on its d i t,c h a r g e . De i c aii r.e the s ys t en. pressure and the flow rete for: The two pumps in PARALLE The two pumps in SERIE QUESTION 1.09 (3.00> Thr-re are THREE primary per c meter s that affect DND and can be controlled by the Rea c t o: Operato Assuc.ing four-loop operaticn, brtcfly cuplaire h u r, an increats in each of tt e p a r e; .u.e t e r s affects D NF: if the other two p a r &.:.-5 t er t remain constan (*#t** CATEGOR t' 1 CCU T I NUED Of.' f1E ri PAGE *8144)
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-- ItEEd991E5diggi_HEBI_IEBMEEES_6Sp_ ELL'Ip_ELgg GUESTICN 1.20 C . OC i
The plant ic being cccled by Natural Circulation. As the fission product dccay hcet decreese Describe HCW and WHY the below parameters will chang Assume that E/G pressure is being maintained at 1000 psi l l Tccld 1 Th t I Cerc'dcits T
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22__E660I_DESIGU_IEGLupIgg_g8 Eely _8Bp_gdE8@gNgy_SYSIgd5 PAGE 6 !1 QUESTION 2.01 (3.00) ! !
'a.. List the automatic start conditions'for the Motor Driven and Turbine Driven Auxiliary Feedwater Pump Include the logic where applicabl (1.50)
' List, in order of. priority, the THREE sources of water-available to the AFW pump (1.50) i OUESTION 2.02 (2.40) r What FCUf-: conditict's will automatically close the steem generator blowdown cente i nme. ,L i sol a ti or valves (CTV 2 2 s '> S (1.60) i Whet TWO conditican will cutomatically closh the blowdown flow
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control vel s ea ( H'. ' 20c)^ (0.80) QUESTICN 2,07 (2.00)
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For each case b e i r-. esplein the essultant method of reactor cool an t s ys t e ct-temparaturc ccnttc a r.d indicete the approximate final RC5 Tav Assume at: sy s t ea.s a r e. norms? c:; c e p t es stetet and that no operator action is take Consider each case separately, The norme' set poi: .t on tbh steam dump system is reduced by ES psi while :n Hot Stand;' y anciting reactor startu The Train A utsc, dump i nter l oci switch is taken to "OFF" while s t ata l e at 0% ree-tor pove Reactor power is 100%; the pressure setpoint on the steam dump system , ' is raised to 1200 psig and steam pressure control is selected at the same time a reactor trip occurs.
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. 2 __PLONI_DESlEU_lyg(UD18@_S6EEIY_680_EUESQEggy_Sy@IEME PAGE 7 . QUESTION 2.04 (0.00) Given the below conditions following a Loss of Coolant Accident, which 4160 vac pumps will be running? Be specifi RWST level: 200,000 gallons Containment pressure: 18 psia RCS pressure: 850 psia Time since accident: 1 hour Loss of all offsite electrical power B Diesel Generator out-of-service DUESTION 2.05 (2.80) State whethcr the Lelow l oa d s a r c,- nor r.,s i l y supplied by RFCCW 1 rain A, Train B, or Bot (1.60) RHf heat exchanger Reactor coolant pumps E >: c e ss l e t doo.n heat enchanger Letdowr hest exchanger Boron retove / ssstem Chsrgir.g p u o,p coaling sucge tant Saeet i oj e: L i on cooling surgo t e Fuei paal coole- For the above loads, state which subheader is the n or r.ia l supply - Containment. Safety-Related, or Nonsafety-Relate (1.2O) CUESTIOfJ 2.06 (3.25' Describe the flowpath used to fill Accumulato- Tant- A when RCS pressure is 1500 psia and RCS temperature is 300 (1.25) What are FOUR basis for the nitrogen volume and pressure limits of the Accumulators? (2.00) Ii4513 CATEGORY O2 cot!TINUED O';fEyT PA3r 4*A44' ..
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.. 21__E66NI_ des 193_INCLUQ1NQ_g6EEIy_6BD_EDES9ENCY_Sy@IEU3 PAGE B QUESTION 2.07 (2.80) A heat detector in the East switchgear room has activated an automatic initiation of the fire suppression syste What precautions should have occurred to warn personnel of imminent or past CO2 discharge? (2.00) HOW and WHERE-can the discharge be defeated? (0.80) OUCETION 2.OS (2.50) If tt e Instrumeat Air IIA) pressure inside cont 6inment starts to decrease, what 1WO outomatar actions should oc cur to mainLair the pressu m? (1.00) On o c ompl ete losw of IA, how will the fo;Icwang velves fails (1.50) Excess }etduwn hand control vC ve (HCV-123) Di'e se l Generator s-er v: ce water outlet velves (AOV-39 A E. B)
~. Feedwater Regu1 M : r g val ven (FCV-510, 520. 530. L 540? Atmospherie: dump valves (PV-20A. Lt. C, &D) ". L1quiC west o di scher ce val w ( H'/- 7 7 )
CUESTION 2.07 (2.25) The plant is ir Hot Stendby' . Uculd a Con t a i n r.en t Isoletion Phase A signal CaJsF the Reactor Coolant Pumps (RCPs/ to stop? Justify your answer essaming no operator action (1.00) Would a Containme..t Isolation Phase B signal cause the RCPs to stop? Justif y your answer assuming no operator actio (1.25)
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Wsuld the below events cause the INCICATED nuclear power to increase, dccreesc, cr r e r.e i n the usmc a s sar.i n ;; thet the actual pcwer remains unchanged st 75*. befcre and after tha even Assume all ccntrol systems arc 2n a u t ar.c t i c . J a = t i -f , ycar an s.< r; . Considc - .sach event separatal T _ ' . '- ' '
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Th: r ee: to- in tpar atiig + '. e e t c- a d 7 statt 25*/. pcwc , s '. 1 contrcl systems c_ i- sti 'r _. - L ; e I c: f i s i r.cr es red to ir.'*. and r steser pressurc de: . : '. ; - Jc: '* 1 2 '2 si;c; c al t h e- 25*: valu Eaplaim, in detail, HOW and h" thin n : : m rf_ct f: c *. c a r . gt: _ atar Ic.c . Assu.Te n Opereta- actio QUEETION 3.04 (1.5C U tc t THREE. p cress radiation moni.or alarms that would be indicative of c stea: ;cnera'.cr tubc leal
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a. l .c_T ,. J, s, n v.C- a (v v0s For each cf the following situations determine whether the rod control interlocks should prevent cutward rod motion. For those conditions whers outward rod motion is prevented, explain what actions must be taksn to reerstablish cutward red moticn. Assume rod control is in manua Consider each casa separately.
l' An intermediate range nuclear instrument fails high during a plant startup with reactor power at 10%. A power range nuclear instrument fails high during a plant startup with reactc: pcwcr at 60%. The turbin; first sta;s imp;1ss pressu-c trarsmitter fails low dering e p: s
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ut;~ tw o i t h r t e c. '. c - p c- e- et CC'. . E i C J 1 t a h E J _'. d l , Ltcp 1 Th fc.ils high and Lccp i Tc fails low while < c,e vting e; 'CO. powc . u,2 :,-n, . a ,- - s: m
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, A s e. : thr pisnt is shutda - at 503 ~ and 20C0 psig and the Ccid C.crpresssre oratectic- (2:r' Eystem is inad.crtently arac Will the CCC syster act tc re d.::e pl ant oresnu^2 if a locp Tc instrument fails ice- Lctify y t, s : 6.r.c u c; . ancludt hco ca:h Train is Mf ected, and what e c h 0 7. taLII ple (2.00? Ll: . c '. a e r rJ r . , r. ~2 A d tt.c F a c.c t c - Operator have of the condition
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Sketch tha ele:trical distribution to bus VIAC-3. Show all alternate scartes cf electr: cal power (5 AC sources .5 1 DC source). Indicate bus voltages, show all breakses, and label all buses and component Breaker numbers are not require Assume that all of the service station , transfernsre (NEETs ?, R3ETs) are deenergi ad.
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QUESTION 3.05 (4.00) _Give the' basis for-the following. protective action Indicate which of the ectier.s can bc blocked, identify HOL' and WHEN'the Llock it-sccomplished: Sourca Range High Flux Power Range Hi gh Flux - Low Power. Range High Flux Rate - Negative High Pressurizer Leve: Centainment Pressure High-1
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Th? ca: tar _ s at 100% pows with all central s y'E t e.m s in auto.T.atic; and
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g :n y o'.w answcr ir. 1ure. s!)the plant response, (2)what F:FS/EEF signals will b. ; Ire ettd 3 6 r. d (3'the fi m:1 appro i mate RCS pressur Es tp oi r.t s a e n st r e qu i r e:. A sums no operator a:tic J (M t t t END C~ C,S.~ECCRY O! 11i11)
_ . . . . i.___ ESC C E DU BE l_;_UQBU66 t_8 EUQ BU GL t_E UEBG E NC Y _6M D PAGE 12
* -E60106001GOL_COUIBOL QUESTION- 4.01 (2.50)
You are working inside the. containment while the reactor is at power. The rad i a ti ca fiele is.850 mrem /hr gamma and 30 mrad /hr thermal and fast neutro You ara 28 years old 6nd have a lif etime exposure through last quarter of 48 Rem on your NRC Form 4; additionally,.you have accumulated 1.5 Rem so far this querter, How long can you wort: in the area before exceeding your 10CFP2O limits? Show all work and state all assumption (1.50) During a declared emergency, you volunteer to enter a high radiation area and pc. -farm work necessary to prevent further effluent releas Irr acc or danc.-< u) t i . the t'P3 Procedures , what i s year maximum allcwed whole I; o6, expo wre? (0.50) In ac cordanc e- with the He,d th Physics Procedures, whose authorization
-
is require < in pnl t.' (0.5G) OUESTICt! 4.02 (3.00) For each of t h e f o f I om r u,; si tuat i or L, deterraine whether the plent should be TRIPPED, SHU1DOWN, FEDUCED IN POUEP, c- ALLOWED TO CONTINUE AT POWE Assune the- plant is opesatir.g ct 10 t M'. pownr er:d com-i der ecch case separately, Instr ument air preswre falls to 90 psi High RCS activit.y is indicated by chemistry sample and a failed fuel monitor alar Number I sesl cn a reactor coolant p u rr.p has faile Pressurizer level is slowly decreasing due to a leak, one charging pump is in operatio Condenser vacuum decreases to 8.0 inches Hg The contaioment pressure has been above 13.O psia for over one hou (t*11X C AT EGOR'. 04 CONTINUED ON NEXT PAGF 41114) r.... ...
. PROCEDURES - NORMA! t_AgyORMAlt_EMEEGENCY_ANQ PAGE 10
" EODIRLggICeL_CogIRg6-QUESTION 4.00 (1.50) What is the. reason for the follcwing note from EOP 35 ECA- " Loss of All AC Power":
"CSF Status Trees should be monitored for intormation only."
OUESTION 4.04 (2.40) What would happen if RHR were initiated when RCS ten.perature was 390 F? Why? What woult happer. if PHP werc initisted wh er. PCS pressurre we 500 psi a'
,
Wl; y DUESTION 4.05 (2.25) In accordar.ce oi th ihe O P--3 2O 2 "feeattor St e r i e p and the (1P Technical Speci f i c a ti on s : What is the M : n i n,,u Terr per a tur e for Cr i t i c e l i t(' ( 0 . 5 '> > Whet action must be tat.en in Mode 1 if the temaerature ic less than the fli r.i mum Ter:iper e t ur e for Criticality? (1.50) QUCSTION 4.06 ( .' . 0 0 ) In accordance with the Emergency Operating Procedures: What is the difference between a FAULTED steam generator and a RUPTURED steam generator? What constitutes Adverse Containment?
(*t*** CATEGDRY 04 CONTINJED ON NEXT PAGE *t848)
/
_ _ _ _ _ _ _ _ _ _ _ . - -
,
5:__[695EDUEEE_ 6980Sbs 6EU98066A_EdEBgEUgy_6BD PAGE 14 66 RIP! Os1C66 GOBIBOL QUESTION 4.07 (3.50) Answer the following in accordance with ADF 3566 "Imrrediate Boration": List FOUR conditions that require immediate baratio C . OO i If boration flow is at least 33 gpm, how many gallons of 4% boric acid will have to be added to raise t ' . - . - ._
' '
by 100 pctn? Nac'd*% (0.50) Describe the TWO flowpaths available for immediate baration, indicate the preferred and alternat (1.00) Q:.JES i I GN 4. OEt ( . -' m Whet are the operefor's ac_ t i on s ie, t.FTER refrw rin to e " Response f40t Obtainec. (RNO)" action etep. the s pected RiiO r espoase cannot be sat.siied? l
'
,
CUE 31IGN 4.ui ('2.50i I r, acc or de.ic e n.th t he fo'r- o c Linat e of the- Emergency Response Pt ocedeser, WHEN at s ttc operatore tequired to s '. a r t ir.cn i t or i ng of LI e Cr- i L '. c e l Sa+e: 7 P o:ic t i o. i Stetus Trees (CBFSTL). ( 1. Oro Frio-itize the b.= : ow lidt A C r i t. i c s ' Safety Function Status Trees f r on highest t c. l ouest . (1.50) Conte.nmcnt -- ".'. Cor e Cooliog - Red Heat Sini - Yellow Integrity - Orange Inventory - Green Subcr i t i t.a1 i t y - Orange QUESTIOtJ 4.10 (1.60) It is discovered toca>. 15 December day shift (0800 - 1600). that a monthiy surveillance due last Fridar, 5 Dr:cember mid shift (0000 - 0900), was not per f or rned . Thiu survei1:i r r e has been per f or tned on tirw for the pact si: month In thin i t e_ s c orisi dered operable" E:: p l a i n your answe (*#t4i C /.TT.G U;:i' n4 CON t T NUED CN IJEXT PAE.F 14411)
- _ _ . . ,
dz__ESQGEDUSEg_;_NDBUB62_8BU98066 _EUESGEUGY_86D PAGE 13
*
B6DI96991GB6_G9dIB9L QUESTION 4.11 (2.00) Answer the following in accordance with ACP-QA-2.06A " Station Tagging"s Who are the only personnel that are authorized to issue Safety Tags to listed quali fied indi viduals? What is the purpose of a " blue tag" found on a valve? ' What col or tag, if any, may be attached to a component which alreatly has a DLUE tag on it?
(Wittt END Oc CATEGORY G4 *****)
($ts444*4A4**6 END OF EXAMINATION *****4**44****: 4 )
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~* 1;
'. _P81NQ1ELEg_QE_NQCLE68_EQWEB_E(@NT QEERATIQNz PAGE 16 ISEEbQQYN6dlCSt_ME61_IB6NSEEB_6NQ_E(QIQ_E(QW ANSWERS _---MILLSTONE 3' -86/12/15-NORRIS, B. . ANSWER- -1.01 (3.00) Reactivity due.to power increase [ Fig 1.23 200 - 1350 = -1150 pcm (0. 40 )-
Reactivity due to-rod withdrawal EFig 1.1] 425 - O = +425 pcm (0.40) Reactivity due to Equilibrium Xenon Change [ Figs 1.3 t< 1.43 1320 - 2760 = -1440 pcm (0.40) Baron worth CFig 1.8]
=* -9.2 pcm/ ppm (0.40)
No reactivity changes due to Samarium (0.40) Total: -1150pcm + 425pcm -1440 pcm = -9.2 pcm/ ppm (12OOppm - BC)
-2165 pcm = -9.2 pcm/ ppm (12OOppm - BC)
BC = (11040 pcm - 2165 pcm)/(9.2 pcm/ ppm) BC = 965 ppm (0.40) Dilute '12,000 gallons CFig 1.113 (0.60) REFERENCE Reactor Theory, Ch 7 " Controlled Reactivity Effects" Ch'8 " Fission Product Poisoning Effects", pg 27 MP3 Curve Book
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
K&A OO1010K5.21/IF OO1000K5.09/IF .
.. PRINQlELE@_OF NQGLEAB_EQWE8_ELANI_QEggATIQN z PAGE 17
- ~
IME80QQyN6dlGSz_HE61_IE8NSEEB_6NQ_E(Q1Q_E(QW ANSWERS - ' MILLSTONE 3 -86/12/15-NORRIS, B. ANSWER 1.O2 (3.00) CRdf) = CR (i ) E (1-Ki ) / (1-Kf ) 3 (0.25) Reectivity in core (i) = -10,000 pcm + (-1000 pcm) = -11,000 pcm (0.25)
(f) = -11,000 pcm + 5600 pcm = -5400 pcm (0.25)
SDM = (1-Keff)/Keff OR p= (Keff - 1)/Keff ; Keff = 1/(1 p) (0.50) Ki = 1/(1 + 0.11) ==> Ki = 0.9009 (0.25) Kf = 1/(1 + 0.054) ==> Kf = 0.9488 (0.25) CR (f ) = 50 cps C (1 - 0.9009)/(1 - 0.9488)3 = 96.8 cps (0.25) Assume Baron worth = 10 pcm/ ppm (0.25) K (i ) = 0.9009 CR (i ) = 50 cps Reactivity in core (f) = -11,000 pcm + (100 ppm * 10 pcm/ ppm)
= -10,000 pcm (0.25)
K(f) = 1/(1 + 0.10) = 0.9091 (0.25) CR(f) = 50 cpsE(1 - 0.9009)/(1 - 0.9091)] = 54.5 cps (0.25) REFERENCE CAF
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
K&A OO1000K5.09/IF , , '1z__EBINGlELES OF NUGLEAR_EQWER_ELANT_QEERATIQNu PAGE 18
.ISEEM9QYNQMIGSt_ME@l_IBQNEEEB_@NQ_ELUID FLQW ANSWERS'-- MILLSTONE 3 -86/12/15-NORRIS, B. ANSWER . 1 . 40 3 (2.75) Lambda = 0.1 sec-1 (0.25)
Beta eff = 0.006 (0.25) Rho = (10 sec) (1 min /60 sec) (10 pcm/ step) (48 steps / min)
= 80 pcm (0.25)
After rod motion: - SUR = 26(lambda (rho)) / (beta ef f - rho) (0.25)
= 26(0.1(BE-4))/(5.2E-3) = 0.40 dpm (0.25) At EOL, beta effective is less (0.50)
which gives a higher SUR (0.25). Due to the rho dot factor
-
(0.50)
the SUR would be higher (0.25) REFERENCE Reactor Theory Ch 4 " Reactor Ki net i c s" , pgs 212-216, 235-244 & 263-268
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
K&A OO1000K5.03/IF OO1000A1.06/IF A1.02/IF ANSWER 1.04 (2.50) Tsat for 2250 psia (2235 psig) (0.2O)
= 652.67 F (0.40)
SCM = Tsat - That = 652.67 - 587 = 65.67 F (0.40) SCM will decrease (0.25) That will increase as power increases (0.50) Natural Circulation Cooldown (0.25) Core delta-T during NC cooldown will approach full load delta-t (0.50) REFERENCE Steam Tables MP3 NSSS Vol 1, RCS, pg 33 NSSS Vol 1, P:r & PRT, pg 16 HTFF Fund, Ch 3 " Thermodynamics", pgs 43-51 Ch 13 " Natural Circulation", pg 4
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
KLA OO1000K5.56/IF , - _
'
- .
'Iz__EBINQlELES_QE_NQQLE88_EQWEB_E68MI_QEE88IlgNs PAGE 19 I *
ISE85QQYN8dlGQu_ME81_IE8NSEER ANQ_ELUlQ_ELQW ANSWERS -- MILLSTONE 3 -86/12/15-NORRIS, B. OO2OOOK5.09/IF :
ANSWER 1.05 (2.25) Decrease (0.25 for direction, 0.50 for justification) Lower temperature increases the density thus reducing the number of l neutrons available for capture by the rod Decrease There is less flux available for interaction as the rods move towards the top of the core Increase Decrease baron concentration increases the number of neutrons available for interaction with the rod REFERENCE Reactor Theory Ch 7 " Controlled Reactivity Effects", pgs 30-34
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
K&A OO1010K5.04/IF OO1000K5.02/IF ANSWER 1.06 (1.50) WMv (5-7% acceptable)4.EK F* (0.50 each) (1-2% acceptable) /. J fe er'M'. (9. T- C "*' acceptabl e)#.Yf fo _ 4. t *fe REFERENCE CA
~ ~ ~ ~~ dans./or 7Itae fE L M~~f f ~ ~ ~ ~~~~~~~ ~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
K&A OO5000A1.06/IF <
-
>5 1, __ PRINGlPLES: OE_NUGLEAR_PQWER_ELANT OPERAllQNs PAGE ~:20 IMEEM9DYNOMIGSz_ME61_IB6NSEER_AND_FLUIQ_E6QW ANSWERS -- MILLSTONE 3 -86/12/15-NORRIS, ANSWER 1.07 (2.00) 1/M = CRO ___ CR1 Starting graph at 1/M = 1.00 (see Figure 1.13) (0.50) Correctly plotting given points for 1400 -> 1000 ppm (5 @ O.20 each) Correct answer 966 +or- 33 ppm (0.50) REFERENCE Reactor Theory Ch 5 " Sources & Subcritical Multiplication", pg 17
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
KLA OO4000A4.02/IF OO4000A4.03/IF OO4010A3.04/IF- ANSWER 1.08 (2.00) Pres = 50 psig (0.50 each) Flow = 77 gpm Pres = 65 psig Flow = 96 gpm REFERENCE HTFF Fund Ch 12 " Fluid Flow Applications", pgs 33-36
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ,.~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
K&A Components: Pumps-Centrifugal /IF .. _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ __ _ _ _ _ _ _ _ _ _ _ ..
- PRINGIPLEg_gE_NgGLEAR POWER __ PLANT OPEBATigN2 PAGE' 21-IHEBDggyN6d1GS2_ME91_IB9NSEEB_8Ng_ELylg_E6gW ANSWERS -- MILLSTONE 3 -86/12/15-NORRIS, l ANSWER 1.09 (3.00).
' Thermal power (0.50) Increasing power results in increased heat flux and thus closer to DN (0.50) 2.- Pressurizer pressure (0.50) Inc.sasing pressure causes an increase in the subcooling and thus further from DN (0.50) Highest Tavg (0.50) Increasing temperature decreases the subcooling and thus closer to DN (0.50) REFERENCE ' MP3 TS, pgs 2-1 & B2-1 HTFF Fund Ch 10 " Reactor Protection", pgs 4-12
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
KLA OO2OOOA1.01/IF OO2OOOA1.06/IF OO2OOOA1.09/IF ANSWER 1.10 (3.00) Tcold will remain constant (0.25) Since it follows S/G saturation pressur (0.50) That will decrease (0.25) Since less fission product heat is being produced (0.50) Core deltaT will decrease (0.25) Since the amount of decay heat is decreasing (0.50) Loop transit time will increase (0.25) Since the driving head for flow is decreasing (0.50) REFERENCE HTFF Fund Ch 13 " Natural Circulation", pgs 2-12
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~ 'KLA OO3OOOK3.01/IF _____ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _
- ..
- _ _ _ _ _ - _ _ _ - _ _ - _ - _ _ _ - _ _ _ _ _ _ _ - _ _ _ _ _ . _ - - _ .
...
,
A__ELONI_DEGIGN_lNGGyDING_S8EETY AND_EMERGENGy_ SYSTEMS PAGE 22 ANSWERS -- MILLSTONE 3 -C6/12/15-NORRIS,-B. ANSWER 2.01 (3.00) MDAFWP:- Saf ety injection signal, deed a[ /PM/* b #
(bI N each)
Low Low level 1/4 SG jC,p /P l TDAFWP: Low Low level 2/4 SG
~ Demineralized water storage tank (0.40 each for sources, Condensate storage tank O.30 for correct order)
Service water system REFERENCE MP3 NSSS Vol 3, Auxiliary Feedwater System, pg 17
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
KLA 061000K4.02/IF K4.01/IF ANSWER 2.02 (2.40) MDAFW pump auto start signal (0.40 each) TDAFW pump steam supply valve open High radiation on SG BD High radiation on steam jet AE exhaust Blowdown tank high pressure Main condenser'1ow vacuum REFERENCE l MP3 BOP Vol 2 Steam Generator Bl owdown, pgs 3-4 .~~~~~~~~~~~~~~~~~~~~~~~~~~~ss~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~.~~~~ l K&A 035010K4.03/IF 2.6 ,.
- - . _ _ _ . . _ _ _ _ _ - _ _ _ . . - _ . - . . _ _
-
,
. , Sz__ELON1_QESIGN_INC6QQ1NG_S@EEIY_6NQ_EMEEGENCY_SYSIEMS PAGE 23 ANSWERS -- MILLSTONE 3 -86/12/15-NORRIS, ANSWER 2.03 (3.00) (The normal steam pressure setpoint of 1092 psig maintains Tavg at 557 F.) A decrease in the setpoint to 1007 psig would cause the dumps to open and cool Tavg to '553 F (0.50) where the P-12 interlock would close all steam dumps (u.50). Steam dump operation would be blocked (0.30), secondary pressure woulo rise to the setpoint of the secondary pressure relief valve would maintain pressure at 1125 psig (0.40) causing primary temperature to steady out at 561F (0.30). In pressure control mode, the output of the turbine trip and load rejection controllers is blocked (0.30). Temperature would be controlled at 561 (0.30) corresponding to the pressure relief valve setpoint (O.40).
REFERENCE Steam Tables MP3 NSSS Vol 3 Ste6m Dump System, pgs 19-23
~~~~~~~~~~~~~~~~~~~~~,ss~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
K&A 041020K3.02/IF ANSWER 2.04 (3.00)
'
o h CMN h MJ/****V"!
~~~~
4. Ok, A or C RPCCW pump (0.50 each) A Safety Injection pump 4 "* /Y A ' Auxiliary Feedwater pump Jg gg -Ag, g/g.d sc/ A&C Service. Water pumps A&C Containment Recirc pumps A or C CVCS pump
[ NOTE: RHR and Quench spray pumps will NOT be running]
REFERENCE MP3 BOP Vol 1 " Electrical Systems Introduction" pgs 10 & 20-21 ,
~~~~~~~~~~~~~~~~ ~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
K&A OO5000K4.OB/IF OO5000K4.12/IF OO6000K2.01/IF ,
..
,
~3t__EL6NI_DEgl@U_INGLUDIN@_S6EETY AND_EMERGENGY_ SYSTEMS PAGE 24 i ANSWERS -- MILLSTONE 3 -86/12/15-NORRIS, B. ANSWER 2.05 (2.80)
, t RHR heat exchanger: both trains, SR header (Or20-for correct header, RCPs: both trains, Containment header Oc45-for correct train)
' Excess LDHX: B train, Containment header , .gc LDHX: A train, Containment header Baron Recovery system: both trains, NSR header Charging pump cooling surge tank: B train, Containment header SI pump cooling surge tank: A train, SR header Fuel pool cooler: Both trains, SR header REFERENCE MP3 NSSS Vol 3 "RPCCW" pgs 2-3
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
K&A OO8000K1.02/IF ANSWER 2.06 (3.25) RWST ==> Safety Injection pump ==> SI Accumulator Master Fill Isolation Valve (CV8888) ==> SI Test Header Cntmt Inner Isolation Valve (MV8871)
===> Accumulator A Fill Valve (MV8878A) (0.25 each) Pressure high: forces more tank water into the RCS before the end of blowdown and therefore the water is assumed los Pressure low: the tank water is not injected fast enough Gas volume low: injection flow rate is low and sufficient injection may not occur Gas volume high: less available water volum (0.50 each)
REFERENCE-OP-3310B, pg 4-5 MP3 NSSS Vol 2 "ECCS" pgs 47-48 &.52-53
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~ .KLA OO6000K6.02/IF OO6020A1.07/IF .
3t__PL@NI_ DESIGN _ LNG 69Q1NQ_ SAFETY ANQ_EMERGENgy_Sy@TEMS _PAGE 25 a ANSWERS -- MILLSTONE 3 -86/12/15-NORRIS, B.. ANSWER 2.07 (2.80) second time delay (0.50 each) Predischarge alarm Strobe lights at entrances and within zones Wintergreen scent Locally (0.40) Lockout the system to prevenrl accidental discharge (0.40) REFERENCE MP3 BOP.Vol 6 " Fire Protection System" pgs 7-9
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~,,3,~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
K&A 086000K4.06/IF ANSWER 2.08 (2.50) Standby Instrument Air Compressor starts (90 psig) _ (0.50) Service Air Cross-connect valve (3IAS-ADV14) opens (85 psig) (0.50) . Fail closed (0.30 each)
, Fail open- Fail closed Fail closed Fail closed REFERENCE MP3 BOP Vol 6 " Instrument Air" pgs 7-9 OP-3332B " Containment Instrument Air" pg 7 P& ids _S&W Dwgs 12179-OO3A-4, 130A-4, 123B-4, & 106A-5 ~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
K&A OOOO65EK3.08/IF K3.02/IF K1.03/IF 3.3 .
- - . . . .
. . . . . l3i__ELONI_QE@l@N INGLUDINQ_EAFETY_AND_EMER@ENGY_ SYSTEM @ PAGE 26
. ANSWERS -- MILLSTONE 13- -86/12/15-NORRIS, B. ANSWER 2.09 (2.25) No -
(0.25)
Seal.injectionflowwouldcontinuetotheRCPs(butthereturnflow would be to the PRT vice the CVCjk (0.75) Yes (0.25) The RPCCW to the pump motors would be isolated (0.50) causing the bearings to heatup and seiz (0.50)
-REFERENCE MP3 Required Drawings Nos. 304 & 311 MP3 NSSS Vol 1, " Reactor Coolant Pumps" Fig RCP-15 ~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
K&A OO3OOOK1.08/IF OO3OOOK6.04/IF OOOA2.'03/IF 3.5 i ? e
. .
3c__1NSIBydENIS_6ND_CQUIBQLS PAGE 27 ANSWERS -- MILLSTONE 3 -86/12/15-NORRIS, B. ANSWER 3.01 '2.25? [a,7f) Om m. _
(0.25 for direction, 0.50 for justification)
Ortreter cra !ccc I r r':2;r ecultin; ' r- decrc rrd * c; Increase f Due to the shifting of the neutron flux toward the perimeter of the core ??.;ht i n c r :2 c t-( Nc t; t!.c d cre __ . Sc e- 2 b : r p t i r -- 4- +"' d~" r- r- ~' f ^ ^
-
REFERENCE C*A*F
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
K.tA 015000A1.06/IF A1.07/IF A1.09/IF W YYY & W W e*d25
} n, im .a w --y.a z& & c 0 W W " N^f0) W n-q A_
l I l l [ l l i
_ _ _ _ . . _ . _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ __
, _ _ _ , _ _ _ _ _ , - _
_ _ _ _, ..
. INSTRUMENTE_AND_GQNTROLS PAGE 28 ANSWERS -- MILLSTONE 3 -86/12/15-NORRIS,-B. ANSWER -3.02 (3.00) Compared +d th Tref to develop rod speed and direction (0.50)
R 72- l +++ (0.25) O l + D ! +
+
S 8- : <+++++++ P l v^ E _O--! :---l--- -+<+++++++++>+-:---l--- ---:-- E v^ D -8- +++++++> !
+ l + l + l-72+++ ~
l l : ! ! ! ! ! : :
-5- -4 -3 -2 -1 0 1 2 3 4 5 Tref - Tavg Auctioneered high Tavg (0.25)
' Tavg is used as the reference for pressurizer level (0.50) Tavg 557F - 587F --> Level 25% - 61.5% (0.25) Auctioneered high Tavg (0.25) &am Low Tavg coincident with Reactor trip causes feedwater isolation (0.50) Tavg = 564F (0.25) 2/4-logic (0.25) REFERENCE MP3 NSSS Vol 3 Temperature Indicating, pgs 13-16 Vol 4 Rod Control,pg 23 Pzr Pres & Level, pgs 23-24
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
K&A OO1000A1.01/IF A1.04/IF A3.06/IF :3 __IN@IBUMENI@_BND_CONIBOL@ t PAGE 29 ANSWERS -- MILLSTONE 3' -86/12/15-NORRIS, B. ANSWER 3.03 (3.00) As power increases, steam flow detector delta-P increases (0.30) As power increases, steam pressure decreases (0.30) m-stm = K(P-stm) (sqroot (del ta-P) )
==>since the steam pressure component stays constant (it should go down) while the delta-P increases, indicated steam flow will be higher than actual steam flow (0.60)
The summing network for flow will send a signal to the total controller to open the feed regulating valv (0.60) As level starts to increase, the level error will signal for the FRV to close 'O.60) Eventually, the flow error will be cancelled out by the level error, and the FRV will be positioned such that steam flow equals feed flow at some higher leve (0.60) REFERENCE MP3 NSSS Vol 4 "Steae Generator Water Level Cont rol "
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~pgs 11-14
~~~~~~~~~~~~~~~~
K&A 035010K4.01/IF '035010A1.02/IF A2.03/IF ANSWER 3.04 (1.50) Air ejector discharge (0.50 each) Steam generator blowdown Main steam line REFERENCE AOP-3556 " Steam Generator Tube Leak" pg 2
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
K&A 073OOOK1.01/IF OOOO37EA2.01/IF .
-
. , st__INEIRUMENI@_@ND_CQNIRQLS PAGE 30
. ANSWERS -- MILLSTONE 3 -86/12/15-NORRIS, ANSWER 3.05 (3.00) f*p [
g,,- Rod motion is prevented 7;pa.c th; P ch:rnc! cr block C1 signal 4, p [[evf, C-/ (0.504 25 each) Rod motion is prevented (0.50&
": ~ r m . ;- th; ^^ chcrnc! cr trip the PR bistables (0.20 each)
t,/ .. . s, 5 fe No effect (0.50) No effect (0.50) REFERENCE MP3 NSSS Vol 4 " Rod Control" pgs 62-64
" Rod Position Indicating" pg 21 ~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
KLA 012OOOK6.10/IF ANSWCR 3.06 (3.00) Train A inputs (PCV 455A) are auctioneered low Th (WR! (0.30) and wide range pressure (PT 405) (0.30) Therefore, Train A PORV will not open (0.40) Train B inputs (PCV 456) are auctioneered low Tc (WR) (0.30) and wide range pressure (PT 403) (0.30) Since the CDP system is armed and the Train B pressure setpoint is low due to the failed Tc instrument, PORV 456 will ope (0.40) ALARM warning when temperature instrument fails (0.50) ALARM when within 30 psi of setpoint (0.50) REFERENCE MP3 NSSS Vol 4 "Pzr Pres & Level Control" pgs 13-15
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
K&A 010000K4.03/IF A2.03/IF . L . _ . ..
. _ .
1 _INSIBQMENIQ_AND_CQNIBQL@ ~PAGE 31 ANSWERS.-- MILLSTONE 3 -86/12/15-NORRIS, B. . ANSWER 3.07 (3.2O)- see attached drawin REFERENCE Millstone 3LRequired-Drawings #322 and 323
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
K&A 062OOOK4.~10/IF OOOK1.03/IF '063OOOK1.02/IF ' ANSWER 3.08 (4.00) .
.a.- -BASIS: uncontrolled RCCA' bank withdrawal from (0.40 each)
a subtritical condition-BLOCK: manual when both IR > 10E-10 amps ' BASIS: reactivity excursions from low, power which are too rapid for temperature and pressure protective actions J BLOCK: manual when 2/4 PR > 10% cc. lBASISt mul tiple rad drop BASIS: back up to High Pressure tripgf [sesser/ W9 b "# -
-BLOCK: automatic when 3/4 PR < 10% & 2/2 Pimp < 10%
, . BASIS:. . LOCA . or: MSLB inside containment BASIS: loss of heat sink BLOCK: automatic if both' hot leg and cold leg isol ation valves are shut lin that loop REFERENC MP3 NSSS Vol 5 "RPSAS" pgs 39-56 MP3 TS pgs 2-5, 2-6, & 3/4 3-26
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~-
K&A 012OOOK4.02/IF OOOK4.06/IF OOOK6.03/IF . 013OOOK1.01/IF n ,. - - .- ,--. , , - , - . - . . - ,-,-m,- - - - , - , - - , , - - . . , - - - - , - , , , , - . - - ~ - - - , - , - , - , . , - - - - - - , .- - - - - - - -
. - . ...-
3 t__INSIRQMENIS;AND_GQNIRQLS .PAGE 32
. ANSWERS.-- MILLSTONE 3 -86/12/15-NDRRIS, B. S.
': ANSWER 3.09 (2.05) One PORV (PCV 455A) will open due to the actuation signal of all four pzr_ pres channels (> 2200 psia) (0.30) When. actual plant pres decreases towards setpoint (2200 psia), the functioning pzr press channels will cause the PORV to close (0.30); Both spray valves will modulate full open (0.30) Reactor trip on low pressurizer pressure (0.30) Pressure will continue to decrease until safety injection initiates (0.30) As SI continues, the pzr will eventually go solid and cause pressure to raise to the PORV setpoint (0.30) Pressure steady stcte pressure would be slightly > 2200 psia (0.25) REFERENCE MP3 NSSS Vol 5 " Instrument Failure Analysis" pgs 11-13
~~~~~~~~~~~~~~~~~~~~~~~~~..~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
K&A OOOO27EA2.03/IF OOOO27EK2.02/IF K3.03/IF s
4 y , ,_
,. - -- - - .-m- .- -- , - , , - - _ _-- ._ - -
.,
* 4 __PBQCEQUEES_ _NQ8d@6t_6ENQ8d66t_EMEBGENCY ANQ -PAGE 33 B6 Dig 6QGIC66_CQNIBQL ANSWERS -- MILLSTONE 3 -86/12/15-NORRIS, B. ,
ANSWER 4.01 (2.50) (N-18) = 50 REM gg s- - (O. 30) . Total lifetime to date = + 1.5 = 45WF Rem Total lifetime available = 50 - 49 5 = p.5 Rem (0.30) Total this quarter available = 3 - 1.5 = 1.5 Rem (0.30) O_- _:-1- lifetime limit J.<5 H ' is more restrictive than O.85. Rem /Hr gamma + (.03 Rad /Hr)(10 QF) neutron =1.15 Rem /Hr dose rate
- #. J J6 (0.30)
0.5 Rem /1.15 Rem /Hr = ._ : Hrs = 79 Min (0.30) EO.2 f or using the conservat' a quality factor] Rem whole body one time exposure (0.50) Director of Site Emergency Operations (0.50) REFERENCE' 10 CFR 20 SHP-4902 , pgs 13-14
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
K&A Plant Wide Generic #15/IF ANSWER 4.02 (3.00) Ch _M d ( m d .a f p p ,- (0.50 each) Continue at power c .- Reduce power (below 37%) Continue at power if within capacity of both charging pumps Trip Shutdown REFERENCE ADP-3562 " Loss of Instrument Air" pg 3 AOP-3553 "High RCS Activity" pg 3
.ADP-3554 "RCP Trip or Seal Failure" pg 3 AOP-3555 " Reactor Coolant Leak" pg 3 ADP-3559 " Loss of Condenser Vacuum" pg 3 AOF-3565 " Loss of Containment Vacuum /Ir tegrity" p
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~g 3
~~~~~~~~~~~~~~~~~~~
K&A System Wide Generic #10/IF ,
. - .
,
4 t__P8QQEQQ6ES _NQRMAbt_ABNQRMA6t_EMERQENQY_ANQ PAGE 34 BeQ1060GIGe6_GQNIBQL-ANSWERS'-- MILLSTONE 3 -86/12/15-NORRIS, B. . ANSWER 4.03 -(1.50) -All FRGs are written on the premise that at least one AC emergency bus is energize REFERENCE WOG ERGS, Background Document.for ECA O.0, pg 75 ~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~.,~~~~~~~~~~~~~~~~
K&A System Wide Generic #7/IF ANSWER 4.04 (2.40) a.- The RCS would heat up (0.60) due to the RHR system being unable to remove all decay heat (0.60) Relief. valve would' lift (0.60) to protect the RHR piping (0.60) REFERENCE OP-3201 Plant Heatup, pg 13
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
K&A OO5000K4.07/IF ANSWER 4.05 (2.25) a.- 551F (NO tolerance allowed) (0.75) With Tavg < 551F restore to within limits withir. 15 minutes (0.75) or be in Hot Standby within the next 15 minute (0.75) REFERENCE
.TS, pg-B2/4 1-2 OP-3202, pg 6 ~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
K&A-OO1000K5.15/IF OO1000K5.16/IF OO2OOOK5.18/IF OO2020SG#5/IF OO2020SG#8/IF 3.5 l-l I
. -- ,
e;
'4 .' [PRQQEDURES - NORMAlt_ABNQRMGLt_ EMERGENCY ANQ PAGE 35
!*-
.BeQ106061G66_GQN18QL ANSWERS - . MILLSTONE 3 -86/12/15-NORRIS, B. > . ANSWER 4.06 (3.00)
Ja . FAULTED - a. break in -the secondary pressure boundary (0.75) RUPTURED - a break in the primary pressure boundary (specifically the steam generator tubes) (0.75)
' Containment temperature >_180 F (0.50 for each parameter, Containment radiation levels >'10E5 R/Hr 0.50 for each value)
REFERENCE WOG-Executive Volume, Writer's Guide section, pgs 48 & 61 MP3 EOP Background Document
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
K&A-035010A2.01/IF' System Wide Generic #10/IF ANSWER 4.07 (3.50) Rod height below the Low-Low limit (4 required at 0.50 each) Failure of one or more rod clusters to fully insert on a reactor trip or shutdown Uncont- '. led cooldown following a reactor trip or shutdown Unconteulled or unexplained reactivity increase
. Failure of the Makeup system to borate ~ pcm = 10 gal ==> must add 100 gallons boric acid (0.50) Preferred - Boric acid tanks to BAT pumps to Immediate boration valve (MV 8104) to suction of charging pumps (0.50) '
Alternate - Boric acid tanks to Gravity baration valves (MV B507 ALB) to suction of charging pumps' (0.50) REFERENCE ADP-3566 "Immediate Boration" pgs 2-3
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
K&A OOOO24EK1.02/IF- OOOO24EK3.01/IF OOOO24EA2.05/IF OOOO24EK3.02/IF ._
.
..:
*- ds__EBOGEEMEES_ _NQBd66t__ABNORMAkt_EMERGENQY_ANQ PAGE 36 E601069 GIG 86_QQNIBQL ANSWERS -- MILLSTONE 3 -86/12/15-NORRIS, B. ANSWER 4.08 ( .75)
If the action contained in the RNO column cannot be performed, then continue on with the next step in the left hand colum (0.75) Acj * 191f3 f*f T/am'eseer Vffjf ANSWER 4.09 (2.50) , When directed to transition from EOP 35 E-O W G each) or when ins (ructed to implement the CSFSTs in EOP 35 E- Aen % Kri g F CA~ . Core Cooling - Red (0.25 each, proper Containment - Red sequence required) Subcriticality - Orange Integrity - Orange Heat Sink - Yellow Inventory - Green REFERENCE EOP Training Text, pgs.11-16
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
K&A OOOO74SG# 10/IF ANSWER 4.10 (1.60) The item is NOT operabl (0.40) Surveillance intervals for a monthly are not to exceed 7.75 days (25% of 31 days) (0.40) The surveillance is nine days overdue (0.40) Failure to meet surveillance requirements constitutes a failure to meet operability requirement (0.40) REFERENCE TS, pg 3/4 0-1 L 3/4 0-2
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~o~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
K&A System Wide Generic #5/IF System Wide Generic #7/IF .
. :4- E8QGEQU8ESf NORMALt _ABNQBMAkt_EMER@ENQY_ANQ PAGE 3 71 "
869196991G86_ggNIBQL
,
ANSWERS--- MILLSTONE 3 -86/12/15-NORRIS, B. ANSWER 4.11 (2.00) :The onshif t SROs (0.757 The valve is to be operated only by order of the individual to whom the tag is issue (0.75) No other tag may be attache .(0.50) REFERENCE MP3 ACP-DA-2.06A " Station Tagging" pgs 4 & 15
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
. K&A Plant Wide Generic #14/IF 3.6 I
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U. S. NUCLEAR REGULATORY COMMISSION hWMf"7 K SENIOR REACTOR OPERATOR LICENSE EXAMINATION
FACILITY: MILLSTONE 3 REACTOR TYPE: PWR-WEC4 DATE ADMINSTERED: 88/12/15 EXAMINER: JENSEN. R C0 CANDIDATE INSTRUCTIONS TO CANDIDATE: Use separate paper for the answer Write answers on one side onl Staple question sheet on top of the answer sheet Points for each question are indicated in parentheses after the question. The passing grade requires at least 70% in each category and a final grade of at least 80%. Examination papers will be picked up six (6) hours after the examination start % OF CATEGORY % OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY
&V. 75/f
_ .2&-00 25.00 THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS,AND THERMODYNAMICS 25.00 25.00 PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION 25.00 25.00 PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL 25.00 25.00 ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS 10 Totals All work done on this examination is my ow I have neither given nor received ai . Candidate's Signature
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, NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules apply: Cheating on the examination means an automatic denial of your application and could result in more severe penaltie . Restroom trips are to be limited and only one candidate at a time may leav You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheatin . Use black ink or dark pencil only to facilitate legible reproduction . Print your name in the blank provided on the cover sheet of the examinatio . Fill in the date on the cover sheet of the examination (if necessary). Use only the paper provided for answer . Print your name in the upper right-hand corner of the first page of each cection of the answer shee . Consecutively number each answer sheet, write "End of Category __" as EpPropriate, start each category on a new page, write only on one side of the paper, and write "Last Page" on the last answer shee . Number each answer as to category and number, for example, 1.4, . Skip at least three lines between each answe . Separate answer sheets from pad and place finished answer sheets face down on your desk or tabl . Use abbreviations only if they are commonly used in facility literatur . The point value for each question is indicated in parentheses after the question and can be used as a guide for the depth of answer require . Show all calculations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or no . Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLAN . If parts of the examination are not clear as to intent, ask questions of the examiner onl . You must sign the statement on the cover sheet that indicates that the work is your own and you have not received or been given assistance in completing the examination. This must be done after the examination has been complete . _ _ _ _ _ _
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18. When you complete your examination, you shall: i . Assemble your examination as follows:
(1) Exam questions on to (2) Exam aids - figures, tables, et (3) Answer pages including figures which are part of the answe Turn in your copy of the examination and all pages used to answer the examination question Turn in all scrap paper and the balance of the paper that you did not use for answering the question Leave the examination area, as defined by the examiner. If after leaving, you are found in this area while the examination is still in progress, your license may be denied or revoke N i
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- . THEORY OF NUCLEAR POWER PLANT OPERATIO Paga 4 - FLUIDS.AND THERMODYNAMICS l
L QUESTION 5.01 (3.00) The reactor is at 15% power, equilibrium Xenon and Samarium, boron concentration is 1200 ppm, BOL, Control Bank C rods are at 200 step Using Figures 5.1 to 5.11:
< What will be the final boron concentration if power is raised to 100%,
ARO, steady state conditions? State which figures you us State all assumptions and show all wor (2.40) How many gallons of pure water or boric acid will have to be added?
(0.60)
e b l.ON Y ey 5.02 (2.25) g pekd . h%c 9 QUESTION lu ( , jgor Figure 5.12 is a sketch, power v t e; prior to time "0", the reactor had been shutdown for 0 days. Using Figures 5.1 through 5.11 as a reference, ! sketch he aproximate xenon concentration associated with this power histor U the same form provide .
(2.95) , A $
QUESTION 5.03 42.40t A reactor at BOL is critical at 10E(-9) amps. Rods are withdrawn at 48 steps per minute for 10 seconds in bank sequenc Calcu hte the SUR immediately BEFORE rod motion stops and immediately AFTER rod motion stops. Assume differential rod worth is 10 pcm/ step, effective delayed neutron fraction is 0.006 and the effective precursor decay constant is 0.1 sec- .(.1.4&T How and why would the SUR change, if at all, if the initial conditions (2.lo) were at EOL? No calculations are necessar .00,60') p.n) l (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)
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0UESTION 6 - Tha r6cetor in in Mod 2 2, all chutdown bani's are full out, end the control banks are withdrawn to 180 steps on Bank Ucing the belcw i nf orma ti on and Figure J~12, determine the critical boron concentration by a 1/t1 pl ot . " Show all work: Baron Concentration Count Rate 1500 ppm 100 cps 1400 125 1300 165 1200 240 1100 445 1000 3330 e
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. * . - THEORY OF NUCLEAR POWER PLANT OPERATIO Paga 5 - FLUIDS.AND THERMODYNAMICS ' QUESTION 5.04 (2.25)
If reactor power is increased from 50% to 100%, compare how DIFFERENTIAL
rod worth changes from the 50% value (increase, decrease, or remain the same) for the following conditions? Justify your answe Consider each case separatel Rod position and boron concentration are held constant, temperature is allowed to decreas Boron is held constant, rods are withdrawn from 150 steps to maintain temperature constant.
- . Rod position is constant, boron concentration is diluted to maintain
'
. temperature constan QUESTION 5.05 (2.00)
List TWO factors which affect the Doppler Fuel Temperature Coefficent (FTC) as the core ages AND briefly explain how each
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factor affects the value of FT (2.0) QUESTION 5.06 (3.00) The Unit 3 calculated Shutdown Margin is 10% delta K/K assuming the most reactive control rod is 1000 pcm. The Source Range count rate is 50 cys.
Show all work and state any assumption Consider each situation l separately.
! i- What would be the final count rate if the shutdown banks are fully l withdrawn? Assume the shutdown bank rod worth is 5600 pc What would be the final count rate if a 100 ppm dilution of the RCS were performed?
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i QUESTION 5.07 (1.50) A cooling water pump is operating at 1500 rpm. Its capacity is 250 gal / min at a discharge pressure of 15 psig which requires 40 KW of powe Determine the pump capacity, speed and power requirement if the pump discharge pressure drops to 10.0 psig due to reduced speed.
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(***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)
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\ THEORY OF NUCMAR POWER PLANT OPERATIO Pag 2 6
. FLUIDS.AND THERMODYNAMICS
:
I l QUESTION 5.08 (2.50) l What is the subcooling margin of the plant if the following conditions exist: (1.00) Thot = 587 F Tavs = 572 F Teold = 557 F Ppzr = 2235 psig Psg = 1033 psig If power is raised from 50% to 100%, how will the subcooling margin change (increase, decrease, or remain the same)? Justif (0.75) Which one of the following conditions would result in the smallest subcooling margin? Assume RCS pressure is the same for all case Justif (0.75) Controlled natural circulation cooldown immediately following a reactor trip from loss of flo . Continued operation at 5% power with all RCP's runnin . All RCPs are operating at normal no-load temperature after an extended shutdow QUESTION 5.09 (3.00) There are THREE primary parameters that affect DNB and can be controlled by the Reactor Operato Assuming fcur-loop operation, briefly explain how an increase in each of the parameters affects DNBR if the other two parameters remain constan QUESTION 5.10 (3.00) The plant is being cooled by Natural Circulatio As the fission product ' heat decays away, describe HOW and WHY the below parameters will chang Assume that S/G pressure is being maintained at 1000 psi , Tcold Thot Core delta T Loop transit time (***** END OF CATEGORY 5 *****)
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. PLANT SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION Paga 7 .
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QUESTION 6.01 (2.50) While operating at 80% power, one safety valve on #2 S/G fails ope How will the nuclear and non-nuclear instrumentation alert the operator that a problem has occurre State TWO way (1.0) What three signals cause automatic closure of the HSIV's? Indicate coincidence; additionally, if.any of the signals can be blocked, identify HOW and WHEN the block is accomplishe (1.50) QUESTION 6.02 (2.25) Would the below events cause the INDICATED power to increase, decrease, or remain the same assuming that the actual power remains unchanged at 75% before and after the event. Assume all control systems are in automati Justify your answe Consider each event separately, Cooldown of the reactor coolant Core aging ppm decrease in boron concentration QUESTION 6.03 (3.00) oha For each of the following control systems, explain MOW"the Tavg input signal is,deri d and WHAT control functions the Tava signal provide Include set points as appropriat Rod control Pressurizer level control Feedwater control (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
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. PLANT SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION Pasa 8
. QUESTION 6.04 (2.40) What FOUR conditions will automatically close the steam generator blowdown containment isolation valves (CTV 22s)? (1.60) What TWO conditions will automatically close the blowdown flow control valves (HV 20s)? (0.80) QUESTION 6.05 (2.00) What TWO conditions must be satisfied to open the CVCS Orif ce Isolation Valves? (1.0) WHatTWOconditionswillcause..heCVCSOrifdceIsolationValves to automatically shut other than the interlocks stated above? (1.0) QUESTION 6.06 (3.00) Assume the plant is shutdown at 500 F and 2000 psig and the Cold Overpressure Protection (COP) System is inadvertently armed. Will the COP system act to reduce plant pressure if a loop Tc instrument fails low? Justify your answer, include how each Train is affected, and what action takes plac (2.00) What warnings would the Reactor Operator have of the condition described in part (a) above? (1.00) QUESTION 6.07 (2.00) State TWO Diesel Generator conditions which will always automatically stop the diesel engine? (1.0) What relay actuation will cause a Start Failure (SFR)? (0.5) What action is required (as a minimum) before another startin attempt can be made? (0.5)
(***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
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8 PLANT SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION Pc2 9 QUESTION 6.08- (1.50) What precautions are taken to warn personnel prior to or after the release of CO2 discharge? (1.5) QUESTION 6.09 (1.35) State TWO actions / signals that would occur as a result of both Reactor Bypass Breakers being closed at the same tim (1.0) . List the location (s) where the Reactor Trip Bypass Breakers (BYA and BYB) may be opened AND close (0.35) QUESTION 6.10 (3.00) ' ' State TWO of THREE interlocks associated with the RHR suction valves (8701 A/B or 8702 A/B). Include any applicable setpoint (1.5) , How is RCS pressure controlled during cold solid conditions with cleanup via CVCS domineralizers in progress? (0,5) State TWO conditions that would AUTOMATICALLY trip an RHR pump, excluding loss of powe (1.0) QUESTION 6.11 (2.00) What are FOUR of the FIVE major sources of Hydrogen generation that the Hydrogen Recombiner is designed to contro (2.0)
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' . PROCEDURRR - NORMAL. ABNORMAL. EMERGENCY Paga 10 -
AND RADIOLOGICAL CONTROL l QUESTION 7.01 (2.25) You are the on-duty SCO and a Radiation Work Permit (RWP) is brought to you for approva In accordance with SHP 4912 Radiation Work Permit Completion and Flow Control, your approval signature signifies what THREE conditions with respect to the plant? QUESTION 7.02 (2.50) The following concern " Refueling Operations" procedure OP 3210 Briefly explain the allowable exception to the requirement for maintaining residual heat removal flow during core alteration Include any applicable time limitation (1.0) What is the basis / reason for maintaining 10.5 feet of water above the top of each fuel assembly during all handling operation (0.5) Who, by job position / title can approve / authorize loads greater than that of a fuel assembly and RCC to travel over irradiated fuel in the vessel with the head removed? (0.5) What count rate indication requires suspension of fuel handling operations? (0.5) QUESTION 7.03 (1.00) Answer the following with respect to OP 3330A " Reactor Plant Component , Cooling Water": Why should the shift from A or B train RPCCW to C Swing RPCCW pump and heat exchanger be done swiftly? Why must you limit RPCCW flow to 8100 gpm? . I ! '
(***** CATEGORY 7 CONTINUED ON NEXT PAGE *****) - . - _ . _ _ . - . . - . - . - - . - _ . -. - - _ - - - . .-. .- - .-_ - .
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. PROM >URES - NORMAL. ABNORMAL. EMERGENCY Paca 11
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AND RADIOLOGICAL CONTROL
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QUESTION 7.04 (2.50) The following concern " Reactor Coolant Pump Operation" procedure OP 3301D precautions, and Why should the Reactor Coolant Pump (RCP) seal leakoff isolation valve be closed when RCS pressure is below 115 psia? (0.5) How long can RCP operation continue if the seal leakoff isolation valve was shut due to #1 seal leakoff exceeding the limit for safe operation? (0.5) If either Number 1 or 2 Reactor Coolant Pump (RCP) is stopped, what action is required AND why? (Assume both Number 1 3 and 4 RCP's remain in operation.) (1.0)
' Why are_RCP starting duty requirements necessary? (0.5)
, QUESTION 7.05 (3.50) The following concern " Reactor Startup", procedure OP 320 What TWO operator actions are required if criticality is NOT achieved when control rods reach the MAXIMUM rod position on the ECP? (1.0) , What operator action is required when diluting the RCS boron concentration by more than 50 ppm? (0.5)
- Briefly explain why you ARE NOT permitted to adjust boron concentration while withdrawing the shutdown bank (0.5) How is proper group alignment and bank overlap determined I during rod withdrawal for criticality? Include in your answer i WHAT is done and HOW OFTEN (or at what points) it is don (1.0)
- While recording data at 10E-8 amps, you determine that loop D Tavs l has been 535F for the last 15 minutes. What action is required?
I Include any applicable time limitation (s). Assume no failed instrument (0.5)
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. PROCEDURES - NORMAL. ABNORMAL. EMERGENCY Pra 12
. AND RADIOLOGICAL CONTROL QUESTION 7.06 (1.50) In accordance with OP 3319A " Condensate System": When initially starting up the system, why should you ensure proper motor amperage on the pump before letting go of the switch? Prior to placing the system in operation, with steam generator pressure less than 700 psig, why should you ensure that the feed-water isolation valves are shut? QUESTION 7.07 (2.50) A maintenance man is working inside the containment while the reactor is at powe He is working in a radiation field of 850 mrem /hr gamma and 30 mrad /hr thermal and fast neutron. The man is 33 years old and has a lifetime exposure through last quarter of 72.5 Rem on his NRC Form 4. Additionally, he has accumulated 1.5 Rem so far this quarte How long can the man work in the area before he exceeds his 10CFR20 limits? Show all work and state all assumption (1.50 During a declared emergency, this individual volunteers to enter a high radiation area and perform work necessary to prevent further effluent releas In accordance with the MP3 Procedures, what is his maximum allowed whole body exposure? (0.50 In accordance with the Health Physics Procedures, whose authorization (by job title / position) is required in part b? (0.50 l
(***** CATEGORY 7 CONTINUED ON NEXT PAGE *****)
' . . PROCEDURES - NORMAL. ABNORMAL. EMERGENCY . AND RADIOLOGICAL CONTROL Peca 13 QUESTION 7.08 (2.50) .For each of the following situations, determine whether the plant should be TRIPPED, SHUTDOWN, REDUCED IN POWER, or ALLOWED TO CONTINUE AT POWE Assume the plant is operating at 100% power and consider each case separatel Instrument air pressure falls to 90 psig, High RCS activity is indicated by chemistry sample and a failed fuel monitor alarm, Number 1 seal on a reactor coolant pump has faile Condenser vacuum decreases to 8.0 inches Hg The containment pressure has been above 13.0 psia for over one hou QUESTION 7.09 (1.00)
According to the foldout page (Reactor Trip /RCP Trip Criteria) of AOP 3561 " Loss of Reactor Plant Component Cooling Water", state TWO of the five listed conditions which require you to stop the RCP' ' QUESTION 7.10 (2.00) What constitutes Adverse Containment? (Include specific parameters and values.) Under Adverse Containment conditions, some parameter values speci-fled in the EOP's are different than values listed for the same parameters under normal containment conditions - (for example: SG Narrow Range Level, RCS Pressure). EXPLAIN why this is necessar . l QUESTION 7.11 (0.75) What are the operator's actions if, AFTER referring to a " Response Not Obtained (RNO)" action step, the expected RNO response cannot be satisfied? l (***** CATEGORY 7 CONTINUED ON NEXT PAGE *****)
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. . . PROCEDURES - NORMAL. ABNORMAL. EMERGENCY Pag 3 14 -
AND RADIOLOGICAL CONTROL QUESTION 7.12 (2.50) In accordance with the Rules of Usage of the Emergency Response Procedures, WHEN are the operators required to start monitoring the Critical Safety Function Status Trees (CSFSTs)? State BOTH criteri (1.00) Prioritize the below listed Critical Safety Function Status Trees from highest to lowest: (1.50) , Containment - Red Core Cooling - Red Heat Sink - Yellow Integrity - Orange Inventory - Green Subcriticality - Orange QUESTION 7.13 (0.50) Concerning EOP 35 ES-0.3, Natural Circulation Cooldown With Steam Void In Vessel (With RVLMS), why is the operator cautioned NOT to depressurize the RCS until the entire system is below 200F7
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(***** END OF CATEGORY 7 *****)
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' . . ADMINISTRATIVE PROCEDURES. CONDITION AND LIMITATIONS Peca 15 QUESTION 8.01 (1.50)
In accordance with the Station Tagging procedure ACP-QA-2.06A, what THREE conditions must be met in order to lift safety tags from equip-ment, thus allowing temporary operation, such as a retest or a functional check? QUESTION 8.02 (1.50) According to ACP-QA-2.02C Work Orders, which of the following ARE primarily the responsibility of the Shift Supervisor / Supervising Control Operator (SS/SCO)? (Assume work is being completed by an outside contractor.) Approve or ammend retest recommendation Identify any LCO requirements involved on the Work Orde Prepare Supplemental Work Orders, if require Assure a fire watch is provided, if necessar Authorize work to commenc Obtain RWP, if necessar Specify and place appropriate safety tag Coordinate the performance of the retest / functional verificatio .
(***** CATEGORY 8 CONTINUED ON NEXT PAGE *****) . , _ - - _ _ _ _ ~ _ .___
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ - _ _ _ _
' . . ADMINISTRATIVE PROCEDURES. CONDITION Paga 16 - AND LIMITATIONS QUESTION 8.03 (3.00)
The following concern " Removing Equipment from Service for Maintenance", procedure OP 3250, When is a system considered high pressure, high temperature? (0.8) What is the required order of isolation of a high pressure system pump suction and discharge valves? (0.7) Can a discharge check valve act as a pressure barrier? (0.5) Maintenance is to be performed on a hydrogen system. The affected portion has been purged with six system volumes, isolated, vented and tagged. What additional action is required before allowing the work to be performed? (1.0) l QUESTION 8.04 (2.00) The following concern " Station Bypass / Jumper Control" procedure, ACP-QA-2.06 If a Technical Specification change is required, or an unreviewed safety question is found to exist, then approval is required from (1) AND (2) before bypass / jumper installation can be authorize What condition allows the Shift Supervisor to grant exception to performing a second verification of a jumper installation? Which TWO individuals, by job position / title, must complete and sign the Assessment Section of the jumper-lifted lead-bypass control sheet? (Do not include the PORC review / approval signature.) Under what conditions can a jumper be installed on operable equipment WITHOUT using procedure ACP-QA-2.06B7 .
(***** CATEGORY 8 CONTINUED ON NEXT PAGE *****) . .
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
i
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.
. ADMINISTRATIVE PROCEDURES. CONDITION Paga 17 ,
- AND LIMITATIONS
QUESTION 8.05 (1.50) In accordance with ACP-QA-2.12 System Valve Alignment Control, state TWO of the four criteria which require independent verification checks of valve alignment QUESTION 8.06 (1.50) The CODE OF FEDERAL REGULATIONS (10 CFR 55) defines the general provisions Operator's Licenses. In accordance with these regulations: What are the " controls" of a nuclear facility ? Who may operate the " controls" of a nuclear facility without an Operator's or Senior Operator's License ? QUESTION 8.07 (2.00) What is the basis for the Technical Specification limit on Reactor Coolant System activity? Include any specific postulated accident (s). What is the basis for the Technical Specification limit on Steam Generator activity? Include any specific postulated accident (s).
QUESTION 8.08 (2.50) During performance of routine surveillance, it is determined that the reactor coolant system total leakage rate is 2.2 gallons per minute, distributed as follows: 0.43 gpm through S/G "A" tube .18 gpm through S/G "C" tube .31 gpm through S/G "D" tube .15 spm through Loop "A" RTD manifold hot les isolation valve packing The remainder of the leakage is unidentifie Describe any technical specification limiting condition (s) for operation which is/are exceeded by these leak rate (***** CATEGORY 8 CONTINUED ON NEXT PAGE *****) _ __
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l
. ADMINISTRATIVE PROCEDURES. CONDITION P G 18
- AND LIMITATIONS ,
!
l QUESTION 8.09 (3.00) The plant is operating at 300% power, all control systems are in automatic, and all equipment is operable except as stated below. Using Section 3/ the Millstone 3 Technical Specifications provided, state what Limiting Condition for Operations (LCO) is violated. (NOTE: Reference to the page number & paragraph number is sufficient; if there is more than one action statement for a system, be specific as to which paragraph). If the situation is not a violation of an LCO, justify by reference to page number and paragraph numbe Consider each situation separately: The TDAFW pump (3FWA-P2) failed its latest surveillanc The "B" Train SI pump (3SIH-P1B) circuit breaker is racked out for replacemen Charging Pump (3CHS-P3C) motor is being replace Quench Spray Pump (3QSS-P3A) has seized bearing Containment average air temperature is 76 QUESTION 8.10 (2.00) The plant is in Mode 3 with a routine startup in progress. During surveillance testing on one of the Diesel Generators it is determined that its day tank level switch is out of commission and will not control its fuel oil transfer pump The Maintenance Supervisor assures you that repairs can be completed within 48 hours. Explain why the startup CAN or CANNOT procee QUESTION 8.11 (3.00) In accordance with EPIP 4010A "Shif t Supervisor'.', when must the SS assume the responsibilities of the Acting Director of Station Emergency Operations? (1.0) In accordance with EPIP 4010B " Acting Director of Station Emergency Operations" what four conditions must you consider when determining whether or not to evacuate? (2.0)
(***** CATEGORY 8 CONTINUED ON NEXT PAGE *****)
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.
. ADMINISTRATIVE PROCEDURES. CONDITION Pago 19
AND LIMITATIONS QUESTION 8.12 (1.50) Which individuals shall be allowed access to the Control Room during emergencies, according to ACP 6.01 Control Room Procedure? (List THREE categories of individuals.)
.
(***** END OF CATEGORY 8 *****) (********** END OF EXAMINATION **********)
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.
We-lead 1 10 1200 430 We-Lead 1.14
'800 400 No Lead 1.18 400 230 ,
No-Lead 1.20 400 300 Solid Water 1.33 , 400 300 No-Lead 1.28 400 200 ( Solid Vater 1.40 400 200 Solid Vater 1.47
- 400 100 , .
Mm1: COMECUCN FACORE ARE APPLIED A8 70LLCUS:
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. THEORY OF NUCr.rAR POWER PLANT OPltRATIO Page 20
- FLUIDS.AND THERMODYNAMICS ANSWER 5.01 (3.00) Reactivity due to power increase [ Fig 5.2] 200 - 1350 = -1150 pcm (0.40) Reactivity due to rod withdrawal (Fig 5.1] 425 - 0 = +425 pcm (0.40) Reactivity due to Equilibrium Xenon Change (Fiss 5.3 & 5.4] 1320 - 2760 = -1440 pcm (0.40) Boron worth (Fig 5.8)
=~ -9.2 pcm/ ppm (0.40)
No reactivity changes due to Samarium (0.40) Total: -1150pcm + 425pcm -1440 pcm = -9.2 pcm/ ppm (1200 ppm - BC)
-2165 pcm = -0.2 pcm/ ppm (1200 ppm - BC)
BC = (11040 pcm - 2165 pcm)/(0.2 pcm/ ppm) BC = 964.67 ppm (0.40) Dilute ~12,000 gallons (Fig 5.11] (0.60) REFERENCE Reactor Theory, Ch 7 " Controlled Reactiv3ty Effects" Ch 8 " Fission Product Peisoning Effects", pg 27 UES~$?E!*~E??b~~b*$~*$$$PE? Ebb *~bb5?E*~$b$b*?!?b**$~"?'N*E*$$$$5??b~~~ K&A 001010K5.21/IF K5.09/IF ANSWER 5.02 (2.25) Sorm unadenllon vs.llM See attached Figure 5.12 (*****+;r: vide f4:er: titi t^t:Cr') REFERENCE , Reactor Theory, Ch 8 " Fission Product Poisoning Effects", pas 7-25 MP3 Curve Book (****** provide figure title *******)
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
K&A 001000K5.13/IF (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)
__ __ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ __
. . THEORY OF NUCr.r4R POWER PLANT OPERATIO Page 21 *
FLUIDS.AND THERMODYNAMICS 5.03 u.as-), STEf ANSWER L? 6Gt 0.30 Lambda = 0.1 sec-1 & Beta eff = 0.006 (0.25) Rho = (10 sec)(1 min /60 sec)(10 pcm/ step)(48 steps / min) o, yo
= 80 pcm Rho dot = (10 pcm/ step)(48 steps / min)(1 min /60 sec) (AM)
,, s o
= 8 pcm/sec Before rod motion stops: (ove6)
,, 3 ,
SUR = 26(lambda (rho) + rho dot)/(beta eff - rho) (4re5)
= 26(0.1(8E-4) + 8E-5)/(6E-3 - 8E-4) = 26(1.6E-4)/(5.2E-3) o. J o = 0.80 dpm (Gres)
After rod motions o. so SUR = 26(lambda (rho))/(beta eff - rho) (Aces)
= 26(0.1(8E-4))/(5.2E-3) o. so
= 0.40 dpm (Ares) At EOL, beta effective is less o. s o which gives a higher SUR (Aves)
(Gre5)
o. a o REFERENCE i ' Rea . . tor
. Th.eory
.. Ch 4 ."R.eactor
. Kinetic.s"..,.
. . . . .
pa..s
...
212-216,
. --.
235-244
. ..
& 263-268
.
i ' K&A 001000K5.03/IF A1.06/IF A1.02/IF ANSWER 5.04 (2.25) Decrease (0.25 for direction, 0.50 for justification) Lower temperature increases the density thus reducing the number of neutrons available for capture by the rods, Decrease There is less flux available for interaction as the rods move towards the top of the core l Increase Decrease boron concentration increases the number of neutrons available for interaction with the rods, i
(***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) - _ . - _ - _ . _ - - _ _ . _ .
_ - . - - - - - _ _ _ _-_-_ --- __ _ -_ - . - .
.
. THIORY OF NUCf,RAR POWER PLANT OPERATIO Page 22
- FLUIDS.AND THERMODYNAMICS REFERENCE b**f13 fib'3fEbb!.293335333'$b'*31b!b1E{{{eg}s]f,,,pgsgg,,pj,,,,,,,,,,,,,, ,, K&A 001010K5.04/IF K5.02/IF ANSWER 5.05 (2.00) BUILDUP OF PU240 [0.5] -- Causes an increase in the resonant absorption resulting in a MORE negative reac Per degree temperature change [0.5]. CLAD CREEP / PELLET SUELL [0.5] -- Causes an increase in gap conductivity and with increasing power the pellet edge remains cooler at EOL resulting in a LESS negative FTC [0.5]. FISSION GAS BUILDUP [0.5]--Decrease gap conductivity making FTC more negative [0.5]. , _ , , , ,
, . . . . . ., ..mo u. . ,
If anner // is i i is wor /] 2.c paial REFERENCE U "" **" O * given,
'# i fren> / bey are woei), l.0 foid mef. (dbeslio., ur}f a,aai,,.a ,
Rin/2 sullrocle/ [or incorreef bsSormallo Millstone Re @ or Theory, Chapter 6, pp 317-321 o f 2.0 poi,,0s.)
(***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)
. . THEORY OF NUCMAR POWER PLANT OPERATIO Paga 23 -
FLUIDS.AND THERMODYNAMICS ANSWER 5.06 (3.00) CR(f) = CR(i) [(1-Ki)/(1-Kf)] (0.25) Reactivity in core (1) = -10,000 pcm + (-1000 pcm) = -11,000 pcm (0.25)
(f) = -11,000 pcm + 5600 pcm = -5400 pcm (0.25)
SDH = (1-Keff)/Keff OR p= (Keff - 1)/Keff ; Keff = 1/(1 p) (0.50) Ki = 1/(1 + 0.11) ==> Ki = 0.9009 (0.25) Kf = 1/(1 + 0.054) ==> Kf = 0.9488 (0.25) CR(f) = 50 cps [(1 - 0.9009)/(1 - 0.9488)] = 96.8 cps (0.25) Assume Boron worth = 10 pcm/ ppm (0.25) K(1) = 0.9009 CR(i) = 50 cps Reactivity in core (f) = -11,000 pcm + (100 ppm * 10 pcm/ ppm)
= -10,000 pcm (0.25)
K(f) = 1/(1 + 0.10) = 0.9091 (0.25) CR(f) = 50 cps [(1 - 0.9009)/(1 - 0.9091)] = 54.5 cps (0.25) REFERENCE 5 $ E . ~ $.?..$ ~ $l f E ~ .!! W ~ '. .! . .'. E!. ~ "~ $ '$.". .' ~ ~ K&A 001000K5.09/IF ANSWER 5.07 (1.50) N1=1500 rpm V1:250 gym Hp1:15psis Pl= 40 KW l N2 = 1500 sqr root (10.0/15) = 1224.7 rpm [0.5] 4 V2 = (1224.7/1500)(250 rpm) = 204.1 gym (0.5]
P2 = (1224.7/1500) (40 KW) = 2 KW [0.5) REFERENCE Millstone 3 Thermodynamics text, Chapter 12, pp. 21-40
: (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) -- _ _ __ . - _ . _ _ _ __ _ . . . _ _ . _ _ _ . . , _ _ _ , _ . _ . _ _ _ _ _--.
- _ . . . THEORY OF NUC W AR POWER PLANT OPERATIO FLUIDS.AND THERMODYNAMICS P c3 24 ANSWER 5.08 (2.50) Tsat for 2250 psia (2235 psig) (0.20) = 652.67 F (0.40)
SCM = Tsat - Thot = 652.67 - 587 = 65.67 F (0.40) SCM will decrease (0.25) Thot will increase as power increases (0.50) Natural Circulation Cooldown (0.25) Core delta-T during NC cooldown will approach full load delta-t (0.50) REFERENCE Steam Tables MP3 NSSS Vol 1, RCS, pg 33 NSSS Vol 1, Pzr & PRT, pg 16 HTFF Fund, Ch 3 " Thermodynamics", pgs 43-51 Ch 13 " Natural Circulation", pg 4
' ~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
K&A 001000K5.56/IF K5.09/IF ANSWER 5.09 (3.00) Thermal power (0.50) Increasing power results in increased heat flux and thus closer to DN DNBR decrease (0.50) Pressurizer pressure (0.50) Increasing pressure causes an increase in the subcooling and thus further from DN DNBR increase (0.50) Highest Tava (0.50) Increasing temperature decreases the subcooling and thus closer i to DN DNBR decrease (0.50) l [ (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) l { ,
.,- , - , - - ------ -- r - - - - , - - - - - - - - - , - - -
. - . THEORY OF NUCWAR POWER PLANT OPERATIO *
FLUIDS.AND THERMODYNAMICS Pr o 25 REFERENCE MP3 TS, pas 2-1 & B2-1 HTFF Fund Ch 10 " Reactor Protection",~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~ pas 4-12
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
K&A 002000A1.01/IF A1.06/IF A1.09/IF . ANSWER 5.10 (3.00) Teold will remain constant (0.25) Since it follows S/G saturation pressur (0.50) Thot will decrease (0.25) Since less fission product heat is being produced (0.50) Core deltaT will decrease (0.25) Since the amount of decay heat is decreasing (0.50) Loop transit time will increase (0.25) Since the driving head for flow is decreasing (0.50) REFERENCE HTFF Fund Ch 13 " Natural Circulation",~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~ pas 2-12
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
K&A 003000K3.01/IF 3.7 i l l i (***** END OF CATEGORY 5 *****) _ ____ _ __ . . _ _ __ _ _ _ ~
. _ __. _ . _ _ ___ _ - - . - - _ . _ _
* .
w~ PLANT SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION Pc.co 26 ANSWER 6.01 (2.50) Nuclear power will increase above turbine powe Tavs will decrease below Tre Tavg/ Tref deviation alar Steam flow / Feed flow change on #2 S/ g, p 0.5 #-} OR other LOGICAL indications on a case by case basis.[Ad/ 11.^) ) 2/ igh I
.ias] (0.00)
2) tainment low steam pressure pressure*f y 2/3s oaf ,Ity icep isoletion velves she' sw4tgf.;/ blockedaby steamline SI block
'
" uler leep(0.00)
3) 2/5B/G hi negative rate steam pressurk'Orblocke e pek en steamline SI is NOT blocked (P-11)f./as] 'O.50) mp REFERENCE [)nwig 108Dd89 MP3 BOP Vol 2 " Main Steam System". pg 20 and Figure 1
. ~ ~ . - ~ ~ . . . -~~ . -~ .
K&A 039000K1.01/IF K4.05/IF A2.05/IF ANSWER 6.02 (2.25) Decrease (0.25 for direction, 0.50 for justification) Detectors see less leakage resulting from decreased Tavg Increase Due to the shifting of the neutron flux toward the perimeter of the core Slight increase Due to the decrease in boron absorption in the downcomer region REFERENCE EIb25 .Y. d.J b[[$ # '.../ . f' fIC 5 f"Off I 1~ . [ K&A 015000A1.06/IF A1.07/IF A1.08/IF 3.3 ,
(***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) , , - , - , , - - - , - , - - , . ,,-,,,,,,,_,_n_..,-
__
. , . , . _ , . , , , , ..m,.,-,m
-
,,_,,,,-,,,,,___e___ .__._____g- _ _ _ _ _ _ _ _ _ .
. _
,
'
. l
. PLANT SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION Paca 27
. ANSWER 6.03 (3.00)
: Compared with Tref to develop rod speed and direction (0.50) l l
R 72- l +++ (0.25) O l + D l + l + s 8- l <+++++++ P l v^ E 0--l---l---l---l-+<+++++++++>+-l---l---l---l-- E v^ l D -8- +++++++> l
+ l + l + l-72+++ l l l l l l l l l l l l-5 -4 -3 -2 -1 0 1 2 3 4 5 Tref - Tavg Auctioneered high Tavg (0.25) Tavg is used as the reference for pressurizer level (0.50)
Tavg 557F - 587F --> Level 25% - 61.5% (0.25) Auctioneered high Tavg (0.25) ( Low Tavg coincident with Reactor trip causes feedwater isolation 0.7f-(0.50) Tavs = 564F (0.25) 0,' : '
-J = _ ( 0 . ^ ^i7 REFERENCE MP3 NSSS Vol 3 Temperature Indicating, pgs 13-16 Vol 4 Rod Control,pg 23 Pzr Pres & Level, pgs 23-24 ~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
K&A 001000A1.01/IF A1.04/IF A3.06/IF (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
- - ._ - . __ . _ - . - _ - - _-. .. ' . . PLANT SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION raga 28 .
ANSWER 6.04 (2.40) CEA MDAFW pump auto start signal -( 0. ' O ::;i. ; TDAFW pump steam supply valve open High radiation on SG BD (SSR-REos) High raAiation on steem jet AE exhaust (ARC -REAh Loss of Yower loss of Air ( A,,y y, g o, yo ea,] Blowdown tank high pressure Main gondenser low vacuum loss of Le# bss o f Air [Arry A> @ 0 YO ea..] REFERENCE hP3 Nsss %I. 2, C,or bi.,,,,e.,d Is./a/to,yS sier.,, pl,le CIS - MP3 BOP~~ Vol
.
2 Steam Generator Blowdown, pgs 3-4
~ . ~ . ~~ . ~ ~ -~ .., ~ . ~ ~ ~~
K&A 035010K4.03/IF ANSWER 6.05 (2.00) . >17 percent Pzr Leve . Valves 459 and 460 ope . Loss of Powe . Loss of Instrument Ai REFERENCE MP3~ ~NSSS
~ Vol 1 ".CVCS". ~page 4 . . ~ ~ ~ ~ ~ ~
K&A 008000K1.02/IF 3.3 i
(***** CATEGORY 6 CONTINFID ON NEXT PAGE *****) . _ . . _ _ . _ _ _ _ . _ . -
. - . . . 1 PLANT SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION Paga 29 .
ANSWER 6.06 (3.00) Train A inputs (PCV 455A) are auctioneered low Th (WR) (0.30) , and wide range pressure (PT 405) (0.30) Therefore, Train A PORV will not open (0.40) Train B inputs (PCV 456) are auctioneered low Tc (WR) (0.30) and wide range pressure (PT 403) (0.30) Since the COP system is armed and the Train B pressure setpoint is low due to the failed To instrument, PORV 456 will ope (0.40) ALARM warning when temperature instrument fails (0. 50 P ALARM when within 30 psi of setpoint Olso accepf 4llawi n, SI and (0. 50 P au mM alar-s, ya.,d alarms: CoPPS i,ra&calia.,e aro,ef
: failrip de-p. t, PRT level , foRV *[t PRT CoPPS ac/walef pn ssure t'
REFERENCE PRT / emf. 1, RCS fressur-e L) [ A,,y .2, g o.Sn ea, } MP3 NSSS Vol 4 "Pzr Pres & Level Control" pgs 13-15
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
K&A 010000K4.03/IF A2.03/IF ANSWER 6.07 (2.00) . Low lube oil pressur . Engine overspee . Generator differenta [2 required, 0.5 each] (1.0) The cranking time limit relays time out (7 secs) before the low speed contacts energize the low speed rela (0.5) Operation of the engine shutdown rese (0.5)
REFERENCE Millstone 3 Vol 1, Diesel Generator and Support Systems, ,50,5 S&W DWG. NO 12179-LSK-24-9.3J and -LSK-24-9.2D.
l l l l ANSWER 6.08 (1.50) Predischarge alarm (0.5 each) Strobe lights at entrances and within zones Wintergreen scent !
(***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
i
._- --. -- .-. . - . - - -
-
. .
.
, U LANT SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION Paga 30 REFERENCE MP3 BOP Vol 6 ". Fire Protection System" pgs 7-9
. _,. . . _ . .
K&A 086000K4.06/IF ANSWER 6.09 (1.35) . Energizes both bypass shunt coils (Trips both Bypass Breakers) Sends Trip signal to both trains of Reactor Protection to trip RTA, RTB , BYA and BY Gennf Uarni,,y dl arm (on NB sf Q )' g0.5 each] Y (1.0) At the bypass Weaker enclosure.), (0.35) REFERENCE MP3 NSSS, Vol 5, "RPSAS", page 21) ff. M 3 ANSWER 6.10 (3.00) Will not open unless RCS (loop WR) pressure is <390 psi Will auto close at 765 psia-Will not open unless valves 8804,8812,8837,8836 are close [2 required, 0.75 each] (1.5) Pressure P /3/ iiend control valve RHR to CVCS (RCV-138-) . (0,5)
-fou RWST level lowf(<36 feet) WITH an SI signal present-Motor protection lockout relay-Buss differential lockout relay (Bus 34C or 34D) [Any 2, 0.5 each) (1.0)
REFERENCE NSSS MPQ) Vol 1, "RHR".
Mi'3 OP 3908' P I d a l 4 n ,.
(***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
. . . , PLANT SYSTEMS DESIGN, CONTROL. AND INSTRUMENTATION Paca 31 ANSWER 6.11 (2.00) (4 of 5 required 9 0.5 each) Metal water reaction from Zir .
" Pressurizer gas space or rys es M . Radiolytic generation,in water collected on containment floo . Radiolytic generation in reactor cor . Corrosion of metals by solutions used for containment spra REFERENCE MP3, Vol 3, Hydrogen Recombiners, page 6 l l l
(***** END OF CATEGORY 6 *****) - - _
. . . PROCEDURES - NORMAL. ABNORMAL, EMERGENCY Pcco 32 *
AND RADIOLOGICAL CONTROL ANSWER 7.01 (2.25) No evolutions are planned which could change the radiological conditions as listed on the RW . Any evolution that would change the radiological conditions will be reported to H . The work on the RWP does not jeopardize the plan REFERENCE MP3 SHP 4912, Para. 4.2, Pp. 3- t ANSWER 7.02 (2.50) Flow may be suspended for up to 1 hour per 8 hour period during performance of core alterations in the vicinity of the vessel hot leg (1.0) To ensure the gamma dose rate at the water surface is within limits (2.5 mrem /hr). (0.5) Shift Superviso (0.5) Excessive (or unanticipated) count rate multiplication (i.e. doubling). (0.5) REFERENCE
l MP3 OP 3210B, Pp. 5-7.
i , ANSWER 7.03 (1.00) There is a momentary loss of RPCCW flow [0.5]. To avoid tube vibration effects in the RPCCW heat exchangers [0.5].
(***** CATEGORY 7 CONTINUED ON NEXT PAGE *****)
!
.
. . . ._
. .- . -. .. . - - _ . _ . . ..
-.. .
.
. : PROCEDURES - NORMAL. ABNORMAL. EMIN ENCY Pasa 33
-
AND.. RADIOLOGICAL. CONTROL . REFERENCE
!
MP3 OP3330A, Pp. 6, 2 l ANSWER 7.04 (2.50) ! To prevent contaminants from the RCP seal leakoff line from being forced back into the RCP seal chambe (0.5) J minutes (0.5) Associated pressurizer spray valve should be taken to manual and closed [0.5] to prevent short cycling the remaining spray flow [0.5]. A
- To prevent damage to the RCP motor winding (0.5)
REFERENCE MP3 OP 3301D Pp. 5- ANSWER 7.05 (3.50) < . Terminate the startup by fully inserting all control bank . Recalculate the EC (1. Energize PZR heaters (to induce spray flow). (0.5) Because with the reactor in the source range, positive reactivity must not be changed by more than one controlled method at a time. (0.5) Rod motion is stopped every 114 steps, and bank demand position is compared to digital rod position indicatio (1.0) Be in Hot Standby within the next 15 minute (0.5) REFERENCE MP3 OP 3202, Pp. 6, 7-8, 10.
!
, (***** CATEGORY 7 CONTINUED ON NEXT PAGE *****)
- - . _ _ _ _ . . _ _ _ _ _ _ _ . _ . _ . , _ . _ _ , _ . - . _ _ _ _ _ . _ . . _ _ , . _ _ _ _ . _ _ , . . , _ . _ , _ . _ . , , _ _ . . _ _ .
_ _ _ - _ - _ _ _ _ _ _ _ _ _ _ - _ . _ _ _ _ _ _ _ _ _ _ _
. . . * PROCEDURES - NORMAL. ABNORMAL. EMERGENCY Paga.34 AND RADIOLOGICAL CONTROL ANSWER 7.06 (1.50) When starting the pump, if the breaker has not closed (proper amperage) the other pumps will Auto-Start if their switch is not in Pull-to-Lock [0.75]. To prevent seat leakage past the SGWLC valves [0.75].
REFERENCE MP3 OP 3319A, Pp. 6, 1 ANSWER 7.07 (2.50) (N-18) = 75 REM [0.30]. Total lifetime to date = 72.5 + 1.5 = 74 Re Total lifetime available = 75 - 74 = 1.0 Rem [0.30]. Total this quarter available = 3 - 1.5 = 1.5 Rem [0.30]. Lifetime is more restrictive than quarterly limi .85 Rem /Hr gamma + (.03 Rad /Hr)(10 QF) neutron = 1.15 Rem /Hr dose rate [0.30]. I 1.0 Rem /1.15 Rem /Hr = 0.87 Hrs = 52 Minutes [0.30',. Rem whole body one time exposure [0.50]. Director of Site Emergency Operations [0.50]. REFERENCE 10 CFR 20 MP3 SHP-4902 , pas 13-14
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
K&A Plant Wide Generic #15/IF {
(***** CATEGORY 7 CONTINUED ON NEXT PAGE *****)
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
, . . . PROCEDURES - NORMAL. ABNORMAL. EMERGENCY - Pcca 35 AND RADIOLOGICAL CONTROL ' ANSWER 7.08 (2.50) **
Og lip q e a[fouer E050.], OR - I'f air [mwre
" ' ' ' ' ~ ~ " ' '
bl ten $tif Oe reac by- [0 95* .), is rYWh "'if I#* "- Continue at power Y
$..m. . .032._ ,... w . _ _ s t ._. ,. ._ . ,,w .. , Trip Shutdown [0.5 ea.]
REFERENCE AOP-3562 " Loss of Instrument Air" pg 3 AOP-3553 "High RCS Activity" pg 3 AOP-3554 "RCP Trip or Seal Failure" pg 3 AOP-3559 " Loss of Condenser Vacuum" pg 3 AOP-3565 ".. Loss of Containment Vacuum /.. Integrity". pg 3
~ . . . . . ~ ~ . . ~ . .. ~ __ ~~
K&A System Wide Generic #10/IF ANSWER 7.09 (1.00) l RCP bearing oil temperature exceeds 190 . RCP thermal barrier cooling flow is lost, AND seal injection flow CANNOT be maintained >6 GP . RPCCW pressure CANNOT be restored to BOTH containment header . RCS temperature is >400F, AND VCT temperature is >135F.
] VCT temperature is >150 [Any 2, 9 0.5 ea.] REFERENCE MP3 AOP 3561.
l l I (***** CATEGORY 7 CONTINUED ON NEXT PAGE *****) _ - . - __- _.- - . _ _ _ _ _ . _ _ _ _ - .
. .
. PROCEDURRR - NORMAL. ABNORMAL. EMERGENCY-
- Pcca 36 AND RADIOLOGICAL CONTROL ANSWER 7.10 (2.00) Containment temperature [0.25] >180F [0.25], containment radiation [0.25] >10E5 R/Hr. [0.25]. Instrument accuracies (or indications) are affected (by high temperature and/or radiation levels.) [1.0] REFERENCE MP3 EOP Background Document Westinghouse Emergency Response Guidelines Executive Volum ~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~ K&A System Wide Generic #10/IF ANSWER 7.11 (0.75) Goes on with the procedure [.5] while still attempting the RNO action.[.25] REFERENCE CAT, CNS Exam Question Bank Number Q-EP-EP1-5 MP3 EOP Training Text, Chapter on EOP Format and Use, P. ANSWER 7.12 (2.50) a. /.When directed to transition from EOP 35 E-0 hr 8 g(0.50 each] A12 3. Whe,yhen
,
instructed
<de r,'*4 to implement Eof 35' EC4- the CSFSTs in EOP 35 E- . Core C6oling - Red [0.25 each, proper 1 Containment - Red sequencerequired} Suboriticality - Orange Integrity - Orange Heat Sink - Yellow Inventory - Green REFERENCE EOP Training Text, Pp. 11-16 of EOP Development Cha ~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~pte ~~~~~~~~~~~~~~~~~~
K&A 000074SG# 10/IF (***** CATEGORY 7 CONTINUED ON NEXT PAGE *****) _ __ .
. . . ' PROCEDURES - NORMAL. ABNORMAL. EMERGENCY Paga 37 '
AND RADIOLOGICAL CONTROL ANSWER 7.13 (0.50) May result in additional void formation in the RC REFERENCE MP3 EOP 35 ES-0.3, P. 7.
(***** END OF CATEGORY 7 *****) - . - - .-
. .
. ADMINISTRATIVE PROCEDURES. CONDITION Pcca 38
AND LIMITATIONS ANSWER 8.01 (1.50) The work is coordinated between the SS/SCO/SRO and the Job Supervisor (s). Any workers protected by additional tags / clearances, (that would be affected by operation of the equipment), shall be advised and remain in the clear before the tags are lifte . The lifted tags shall be maintained with the work documentation in the custody of the SS/SCO (until the operational evolution is completed).
REFERENCE MP3 ACP-QA-2.06A, P. 16-1 ANSWER 8.02 (1.50) a,b,e,g, h REFERENCE MP3 ACP-QA-2.02C Pp 8-1 ANSWER 8.03 (3.00) >500 psig, >200F (1.0) Discharge first, then suctio (1.0) No (0.5) Chemistry samples the immediate area and inside closed volumes for explosive concentration of hydroge (1.0) REFERENCE OP 3250, Pages 4- (***** CATEGORY 8 CONTINUED ON NEXT PAGE *****)
.. .
.
8'. ADMINISTRATIVE PROCEDURES. CONDITION Paco 39 - AND LIMITATIONS ANSWER- 8.04 (2.00) . NRC NRB [0.25 ea.] If the second verification would result in significant radiation exposur [0.50] SS and Duty Officer [0.25 ea.] If identified and controlled in another approved procedure. [0.50] REFERENCE ACP-QA-2.06B, Pp 7-10, 1 ANSWER 8.05 (1.50) All safety related system . . Components that if mispositioned could cause an unmonitored release of radioactive material to the environmen . Systems considered important to the safe shutdown of the plan . Surveillances whereby the valves manipulated could directly affect the safety function of a syste [Any 2 9 0.75 ea.] REFERENCE o2 MP3 ACP-QA-y.12, O ; ANSWER 8.06 (1.50) Apparatus and mechanisms, the manipulations of which directly effect the reactivity or power level of the reactor, An individual may manipulate the controls as part of his training to qualify for an operator license under the direction and in the l presence of a licensed operator or senior operato (***** CATEGORY 8 CONTINUED ON NEXT PAGE *****)
. . _ . - - - .
i
. . 1 . * ADMINISTRATIVE PROCEDURES. CONDITION Paco 40 ;
AND LIMITATIONS REFERENCE 10 CFR 55 ANSWER 8.07 (2.00) Based on not exceeding 10 CFR 100 exposure limits at the site boundary [0.5] following a STGR. [0.5] Ensures that the resultant offsite dose will be limited to a small fraction of 10 CFR 100 values [0.5] in the event of a steamlime rupture [0.5]. ' REFERENCE MP3 TS B3. MP3 TS B3.7. ANSWER 8.08 (2.50) Max. S/G tube leakage of 500 spd, (exceeded by leakage through #1 S/G - 619.2 gpd). Max, unidentified leakage of 1.0 gpm, (exceeded by remaining unidentified leakage of 1.13 gpm).
REFERENCE VEGP, TS 3.4. MP3 TS 3.4. MP3 TS B3. ANSWER (3.00) ' 8.09 Pg 3/4 7-4, para 3.7.1.2 Action Statement "a" (72 hours) [0403 Pg 3/4 5-3, para 3.5.2 Action Statement "a" f 0 403 1 -1, 3.1.3.3. b (NOT an LCO) [0 Go](72 hours) , 'parapara 3.1.2.4 (NOT an LCO) L d. 2 03 3 5-3, [0. ,20)
. /4 6-12, para fre 3.5" 3.a CNO Tan L CO)
3.6.2.1 Action Statement (72 hours) [0.40,7 Pg 3/4 6-9, para 3.6.1.5 Action Statement (8 hours) [0.60.eeeh] ,
, (***** CATEGORY 8 CONTINUED ON NEXT PAGE *****) . _ - _ _ . . . _ _ _ - . - _ - . - - _ _ _ _ - _ - _ _ _ _ _ _ _ _ _ _ _ - . - _ _ . . . .. ..
. - - ~ - . . _- . . _ , _ _ - - _ .- .. . . ADMINISTRATIVE PROCEDURES. CONDITION Pcco 41 *
AND LIMITATIONS REFERENCE MP3 TS Pages as noted in answe ANSWER 8.10 (2.00) A diesel fuel oil transfer train is out of service due to the inability of components to perform their intended functions [1.0]. Thus, you are in an action statement and the startup CANNOT proceed [1.0] (until the LCO is met. Entry into a operating mode is not allowed unless all LCOs are met for that operating mode without reliance on action statements.)
> REFERENCE , MP3 TS 3.8.1.1 and 3. , l
ANSWER 8.11 (3.00) If the emergency condition is classified as an Alert, Site Area Emergency, or General Emergenc (1.0) . Will assembly help or hinder the situation? 2. Personnel dose rates exceeding limits (limits: >10 mrem /hr or I-131 levels > 10 x MPC) 3. Personnel exposure exceeding limits (limits: >500 mrem whole body or 500 I-131 MFC hours) l . 4. Actual or potential personnel hazards exis [0.5 ea.] REFERENCE
- MP3 EPIP 4010A, P. 5; EPIP 4010B, P. '
! ANSWER 8.12 (1.50) Authorized individuals responsible for direct operation of the uni . Authorized personnel who may be required to support or advise the ' operation.
. . Resident NRC inspector (***** CATEGORY 8 CONTINUED ON NEXT PAGE *****) i
- _ . - - - _ . . - _ - - . _ _ __ _ - _ _ - . _ _ - . _ -
. . . ADMINISTRATIVE PROCEDURRS. CONDITION Pcco 42 *
AND LIMITATIONS REFERENCE ACP 6.01 Pp. 9-10.
t (***** END OF CATEGORY 8 *****)
(********** END OF EXAMINATION **********) -- . _ _ _ _ _ . _ _ _ _ _ _ . - - . _- . - - - - - . _ . --- ._._--_. __,__ _ . _ - - - - - _ _ - . _ - , _ - - - _ . . _ _ _
- -. - . . - .-. . . . . . - - .
TEST CROSS REFERENCE Pega 1
.
QUESTION VALUE REFERENCE 5.01 3.00 ZZZ0000001 5.02 2.25 ZZZ0000002 5.03 2.50 ZZZ0000003 5.04 2.25 ZZZ0000004 5.05 2.00 ZZZ0000005 5.06 3.00 ZZZ0000006 5.07 1.50 ZZZ0000007 5.08 2.50 ZZZ0000008 5.09 3.00 ZZZ0000009 5.10 3.00 ZZZ0000010 ______ 25.00 6.01 2.50 ZZZ0000011 6.02 2.25 ZZZ0000012 6.03 3.00 ZZZ0000013 6.04 2.40 ZZZ0000014 6.05 2.00 ZZZ0000015 6.06 3.00 ZZZ0000016 6.07 2.00 ZZZ0000017 6.08 1.50 ZZZ0000018 6.09 1.35 ZZZ0000019 6.'10 3.00 ZZZ0000020 , 6.11 2.00 ZZZ0000021 ______ 25.00 7.01 2.25 ZZZ0000026 7.02 2.50 ZZZ0000025 7.03 1.00 ZZZ0000027 7.04 2.50 ZZZ0000023 7.05 3.50 ZZZ0000022 , 7.06 1.50 ZZZ0000028 7.07 2.50 ZZZ0000029 7.08 2.50 ZZZ0000034 7.09 1.00 ZZZ0000024 7.10 2.00 ZZZ0000030 7.11 0.75 ZZZ0000033 7.12 2.50 ZZZ0000031 7.13 0.50 ZZZ0000032 ______ 25.00 8.01 1.50 ZZZ0000043 8.02 1.50 ZZZ0000044 8.03 3.00 ZZZ0000040 8.04 2.00 ZZZ0000041 8.05 1.50 ZZZ0000045 8.06 1.50 ZZZ0000035 8.07 2.00 ZZZ0000037 8.08 2.50 ZZZ0000038 8.09 3.00 ZZZ0000039 8.10 2.00 ZZZ0000036 8.11 3.00 ZZZ0000042 8.12 1.50 ZZZ0000046
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e MILLSTONE-3 REACTOR OPERATOR DECEMBER 15, 1986 1.02.a Facility Comment: The question combines independent concepts: MP3 definition of Shutdown Margin, and actual shutdown reactivity effect This may lead to misinterpretation, as MP3 SDM calculations add other conservati sm to actual reactivity beyond the stuck rod assumption; c.andidates may make assumptions-beyond face value of the question and should be evaluated on a case basi (Ref. OP 3209) Resolution: Candidates' answers will be evaluated closely on a case basi The question requires candidates to " state any assumptions," and candidates will be graded based on any assumptions state If no assumptions are stated by a candidate, his answer will be graded in strict accordance with the answer ke .06.c Facility Comment: Agreed that a range of values greater than 0, but less than 1% would be acceptable as an answe Resolution: Answer key modified accordingl .09 Facility Comment: Question asks for effects upon DNB (not DNBR, and not
" proximity to DNB"), which is misleading. Candidates may interpret literally and provide opposite direction from answer ke Agreed that this may have to be graded on a case basi Resolution:
, Candidates will be graded on a case-by-case basis, assumptions and consistency within the answers will be considere ___. _- _ - . . - - -
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2.01.a Facility Comment: Key excluded LOP.and CDA signals which start MDAFW pump (Reference: AFW Text p. 9) Resolution: Answer key modified and points redistribute .03.b Facility Comment: , Agreed that statement that steam dump operation is blocked is not required for full credit as long as ' obvious understanding of plant response is eviden Resolution: Candidates will be graded based on an understanding of the operation of the steam dump syste .03.c Facility Comment: ,, As 2.0 ' / , Resolution: .
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As 2.0 .
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3.02.c Facility Comment: ,
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Low Tave coincident with reactor trip not low-low Tave causes FW (Reference: MP3 Text Temperature Indicating System p. 14) Resolution: Answer key changed to Low Tavg, vice low-low Tav .05.a Facility Comment: Agreed that answer key should account for I.R. high If IR,'..
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flux tri If trip is blocked, C-1 is blocke ' instrument fails high and no block is present, a '
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reactor trip will occu ' a Resolution: i Answer key modified to allow for candidates' assumptions, will be graded on a case-by-case bas.s ,
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3.0 Facility Comment: Agreed that_" Prevent water passage through safety valves" could be acceptabl Reference: CRx Trip Handout] Resolution: Modified answer key to allow for additional answe .0 Facility Comment: Question gives value of 48 Rem lifetime exposure, Key uses 44 Re ' Resol'ution:
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Answer key correcte t , i I 4.0 Facility Comment: *
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Agreed that ADP 3562, Loss of Instrument Air does not require shGtdown os plant based on air pressur (Ref: AOP 3562)
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-fu Answer key changed to read, "Continuh at power CO.53, , ( '
e OR - If a:r pressure is rapidl/f ' decreasing CO.253, then
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trip the reactor CO.25]./ '
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l 4.0 Facility Comment: J' Agreed that will accept tripping the reactor if proper
' - assumptions s'peci+ied i.e. AOP 3555 Reactor Coolant 4 -' Leak directs operator to trip the reactor if PZR LVL-
! continues to decrease with both CCP's runnin (Ref: , ADP 3555) f
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Resolution: Candidates' answers will be graded on a case-by-case basis depending on assumptions.
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4 e 4.0 Facility Comment: Agreed that question was vague and placing RHR in service at 390 F could have many effect OP 3201 says not to initiate RHR when RCS temp >350 F and pressure >440 psi (Ref: OP 3201, Plant Startup) Resolution: Question did not ask whether or not RHR could be initiated at the given conditions, the question was what would happen IF RHR were initiate Question will , be graded based on Candidates' assumption .0 Facility Comment: Agreed that answer key should allow for RHR suction valve interlocks. RHR suction valves from RCS are interlocked to prevent opening if RCS wide range pressure is >390 psia, preventing RHR from being initiated at 500 psi (Reference: RHR Chapter p. 3) Resolution: Same as 4.04.a abov The following additional changes were made to this exam during the grading process: 1.06- Answer key corrected to show specific values for Millstone 3; also, reference adde .04 If Candidate assumes that a CDA has initiated, then will allow credit for a Quench Spray Pump (but not for an RPCCW Pump).
2.05 Corrected point distribution on answer key to be consistent with questio .09 Modified answer key to denote that part of the answer was supplemental information for the grader.
- 3.01 Parts a and c were delete Several candidates assumed that control rods would move to compensate for temperature chant,e The questions became ungradable due to too many variable .08 Added reference.
l 4.0 Added additional answer to key and redistributed i points.
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c . 1Tnebn7ctyf Y MILLSTONE-3 SENIOR REACTOR OPERATOR DECEMBER 15, 1986 5.03a Facility Comment: Transient SUR equation is not included on the SR0 equation shee Agreed that an accurate discussion of SUR during rod withdrawal will suffice for full credi Resolution: Only for the portion of the question which deals with SUR imme-diately BEFORE rod motion stops - an accurate discussion of transient SUR will be accepted for full credit. The remainder of the question will be graded as keye .05 Facility Comment: Question asks for " Fuel Temperature Coefficient", however the answer key appears to deal with the Doppler Power Coefficient. Agreed that the actual answer is given by #1 in the key and must be graded on a case basis. (Ref. Millstone Rx Theory, Chapter 6, pp 317-321) Resolution: If keyed answer #1 is given, it will earn full credi If keyed answer #2 or #3 are given, they will car, half-credit each. More than full credit will not be given. Points will be subtracted for any information given which is incorrec .06 Facility Comment:
(same as comment on 1.02 of R0 exam)
1.02a Facility Comment: The question combines independent concepts: MP3 definition of Shutdown Margin, and actual shutdown reactivity effects. This may lead to misinterpretation, as MP3 SDM calculations add other conservatism to actual reactivity beyond the stuck rod assumption; candidates may make assumptions beyond face value of the question and should be evaluated closely on a case basi (Ref. OP 3209) Resolution: i Candidates' answers will be evaluated closely on a case basis. The question requires candidates to " state any assumptions," and candidates will be graded based on any assumptions stated. If no assumptions are stated by a candidate, his answer will be graded in strict accordance with the answer ke I .
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6.Olb Facility Comment: Answer #2 no longer includes loop isolation valves shu (Ref: 108 D. 684 Sh 7 Rev. 6) Resolution: Removed reference to loop isolation valves position from the answer key. Point distribution remains unchanged. Added MP3 Drawing 108D684, Sh 7 to the reference lis .03c Facility Comment: See 3.02 c - Low Tave, not low-low Tave coincident with reactor trip causes FW .02c Facility Comment: Low Tave coincident with reactor trip not low-low Tave causes FW (Reference: MP3 Text Temperature Indicating System p. 14) Resolution: Answer key changed to Low Tavg, vice low-low Tav .09a Facility Comment: Agreed that answer may be reactor trip and general warning alarms on MB (Reference RPSAS Text pp 36-37) Resolution: Answer key modified to accept " General Warning Alarm (on MB4)" as an additional correct answer. Two answers required at 0.5 points each; total question value remains unchanged. Added facility supplied reference to the list of reference .10b Facility Comment: Agreed answer is PCV131 (Reference: OP 3208 Plant Cooldown) Resolution: Answer key changed to " Pressure control valve RHR to CVCS (PCV-131)."
Point distribution remains unchanged. Facility supplied reference added to the reference lis .10c Facility Comment: Agreed that Low low level RWST not Low level RWST trips RHR pump (Reference: ECCS Chapter p. 82)
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Resolution: Answer key changed to require "RWST level Low-low..." vice "RWST level low...". Point distribution remains unchanged, and the facility supplied reference is added to the reference lis .08a Facility Comment: See 4.02a 4.02a Facility Comment: Agreed that AOP 3462, Loss of Instrument AIR does not require shutdown of plant based on air pressure. (Ref: A0P 3562) Resolution: Answer key changed to read, " Continue at power [0.5], OR - If air pressure is rapidly decreasing [0.25], then trip the reactor
[0.25]."
7.08c Facility Comment: Agreed that SHUTDOWN should also be acceptable since we are not licensed for 3 loop operation Resolution: The NRC did not agree to accept both " Shutdown" AND " Continue at power (<37%)." Since Millstone 3 is not licensed for 3-loop operation, the only acceptable answer can be " Shutdown." Answer key changed to " Shutdown", and point distribution remains un-changed. It should be noted that reference to and/or procedures for 3-loop operation appear in several places throughout the reference material supplied to the examiners, INCLUDING the Technical Specifications. (A copy of the unit's operating lictnse was not forwarded with the reference material.) It is recommended that the facility change all procedures and training materials which imply or allow 3-loop power operation such that they are in conformance with actual license limitation .12a Facility Comment: Agreed that when entering ECA 0.0 is acceptable answe (Reference ECA 0.0, Loss of All A.C. Power) Resolution: Answer key changed to read:
" . When directed to transition from E0P 35 E- " . * ,- . . When instructed to implement the CSFST's in E0P 35 E- . When entering E0P 35 ECA [Any 2, 9 0.50 each]"
E0P 35 0.0 added to the reference lis The following additional changes were made to this exam during the grading process: 6.11 Keyed answer #2 has been expanded to accept either " Pressurizer gas space OR System H2", for full credi .05 Reference corrected to "MP3 ACP-QA-2.12, P.S."
8.09 Following components added to answer part c:
"Pg 3/4 1-8, para 3.1.2.2.b (NOT an LCO)
Pg 3/4 5-3, para 3.5.2.a (NOT an LCO)" Three components now required for part c, at 0.20 points each. Point distribution for remaining parts of answer remain unchange .02 Figure title " Boron concentration vs.1/M" added to answer ke .03 Redistributed point values because original distribution did not total question value of 2.50. Each component of part "a" now worth 0.30 (was 0.25), for total part "a" value of 2.10; each component of part "b" now worth 0.20 (was 0.25), for total part "b" value of 0.4 .06 Incorporated reference: MP3, Reactor Theory, Ch. 5, Subcritical Multiplication.
I 6.01 Clarified point breakdown on answer ke .02 Incorporated reference: MP3 NSSS Vol. 3. "Excore Nuclear Instru-mentation," Pg. 9-1 Deleted "2/4 logic" from keyed answer for part "c", because this is l 6.03 not elicited by the question. Redistributed part "c" point break-l down such that the description of the FWI/Tavg relationship is worth l 0.75 points (was ,0.50).
, 6.04 Added in parenthesis "SSR-RE08" behind "high radiation on SG BD",
and " ARC-RE21" behind "high radiation on steam jet AE exhaust."
Added the following to list of acceptable answers for part "a": l
- CIA - Loss of Poder - Loss of Air Require any 4 (of 7), at 0.40 point each. Total value of part "a" remains unchange _ - _ - - - - _ - . - . _ _ - _ _ - - . ._,
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Added the following to list of acceptable answers for part "b":
- Loss of Power - Loss of Air Require any 2 (of 4), at 0.40 point each. Total value of part "b" remains unchange Added "MP3 NSSS, Vol. 2, Containment Isolation System, Table CIS-1" to list of reference .06 Part "b" of answer key modified to "also accept following alarms:
COPPS armed COPPS actuated, PORY open, SI and associated alarams, and indications: tailpipe temperature increasing, PRT level in-creasing, PRT pressure increasing, PRT temperature increasing, and RCS pressure decreasing." Any 2 (of 11) required at 0.50 point eac During administration of the exam, the following changes were made: Original question 5.02 was deleted and replaced with a new question to determine candidates' ability to predict criticality using a 1/M plo (Question and key answer attached as part of Master Copy of exam.) Question 6.03 clarified. Now reads, "... explain what the Tavg input signal is, and WHAT control functions the Tavg signal
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provides..." Announcement made to all candidates concerning this change during the exam.
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