ML20212N342
| ML20212N342 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 03/06/1987 |
| From: | Cooley R, Graves D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20212N316 | List: |
| References | |
| 50-298-OL-87-01, 50-298-OL-87-1, NUDOCS 8703120451 | |
| Download: ML20212N342 (86) | |
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[ CIS EXAMINATION REPORT No. 50-298/0L-87-01 t
Facility Licensee: Nebraska Public Power District P. O. Box 499 Columbus, Nebraska 68601 Facility Docket No.: 50-298 Facility License No.: DPR-46 OperatorLicenseexaminationsadministeredatCooperNuclearStation(CNS)
Chief Examiner: , M/41 D. M. Graves Date Approved By: kNA R.A. Cooley, Chip',OperatorLicensing 3/4/97 Eati Section Suns.ary:
Examinations were administered to five Reactor Operator candidates and three Senior Reactor Operator candidates. 'All eight candidates passed all portions of the examinations'and have been issued the appropriate licenses.
8703120451 070310 PDR ADOCK 05000298 V PDR
E.
2 REPORT DETAILS _
- 1. CANDIDATES EXAMINED
-Pass - Fall Total SRO Candidates 3 0 3 R0 Candidates 5 0 5
- 2. EXAMINERS D. N. Graves, Chief Examiner, NRC J. E. Whittemore, NRC
- 3. EXAMINATION REPORT Performance results for individual candidates are not included in this report. ,
- a. Examination Review Comments and Resolutions A copy of the facility's review comments is attached. If a coment is not addressed in this section, it has been accepted and incorporated into the answer key. Coments and resolutions are listed by section and question number..
1.03 Answer given is going to depend on whether the.
candidate assumed that power given in the question was sufficient to cause significant burnout. If the candidate assumed that burnout would occur then answer "a" would be acceptable.
If the candidate assumed that the given power was not sufficient to cause burnout then the answer "b" is acceptable. Recommend accepting either "a" or "b".
Resolution: The flux at the power level given in the question should not be sufficient to cause significant burnout at the rate Xanon would be building in.
2.08.b Question is ambiguous. A number of protective devices send signals to the solenoid valve to' protect the turbine generator. Recomend accepting any turbine generator trip signal.
Resolution: The devices in question are independent of each other. Knowledge of the devices available to protect the turbine is considered pertinent, in addition to the individual turbine trip signals.
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e 3.05.b and 6.05.b If a RPIS'inop select block occurs during rod movement then the rod will not be deselected until the rod is stopped. The training material implies in one portion that a select block will i stop motion during~ emergency in. Reconenend 'due i to the confusion of the training material accept ,
either the rod will stop or the rod will continue to insert and rod movement with other rods will be prevented.
Resolution: Answer key changed to reflect that the rod will continue to insert but rod movement with other rods will be prevented. The other answer will not be accepted because it is not correct.
3.09.a and c A Group II isolation is caused by a high drywell signal or a 12.5" reactor level. Recommend accepting 1 (High DW Pressure) and 3 (12.5" Reactor Level) for signals that operate the Reactor Building ventilation valves. Accept 6 (Group II) as a signal that operates RHR Shutdown Cooling valves.
Resolution: Group II signal will be accepted as a signal that operates the Shutdown Cooling Valves. The individual inputs to the Group II signal will not be accepted as answers for the Reactor Building Ventilation valves because they are indirect inputs. Actuation of a Group II signal could occur, through-fault, without a low level or high DW pressure.
7.06.b and c Due to the vagueness of Procedure 9.1.1.4 the answer to this question may vary. The administrative limitation section states that "a SWPmaybeineffectforatotalofone(1) month and seven days, if work requires this SWP to be extended, a new SWP must be issued."
Under Section VI.B.3 the procedure implies that a SWP can be written with an expiration date of one month and seven days and the note says this can be extended for an additional seven days.
Recommend accepting wither one month or one month plus seven days for part b.
Resolution: Discussion with the Training Coordinator indicated the actual intent is for the expiration date to be one month. This can be extended for seven days. That is how the question will be graded.
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' b .- EXIT' MEETING SUMARY~
At the conclusion of the site visit, the examiners met with utility representatives to discuss the visit. The following personnel were
.p[esent: ,
NRC Facility w I U l.. DuBois R. Brungardt -
%^
D. M.- G' raves - J. W. Dutton - J E. A. Plettne'c R. A. Jansky
G. R. Horn i M. Parrish, J..Surette-s .
- Mr. Graves started the discussiotr by ncting that preliminary oral' examination results are no longer provided at the exit meeting in accordance with NUREG-1021,' Operator Licensing Exaniner Standtrds.. r Other items discussed were as follows
(1); The.Gaitronics speaker in the room the,writtbn examination was administered could not be turned off. The examiners felt the candidates were distracted during the written exam by the numerous pages and: communications over.the Sri'tronics..-
(2) The operating staff in the control rcom and the training staff were very cooperative during the 9xasjnations which resulted in minimal disruption of examination tire.' -
s,q
'(3) Facility comments on the written examination were given to the Chief Examinor at the exit meeting.,
(4) Written and operating examination results will be sent to the s/ '
facility as soon as possibl. . _
No generic or widespread candidate weaknesses were noted during the site visit and the utility was so informed. A review of the -
operating examinations in the Regional office indicated that the Reactor Operator candidates were weak in their knowledge of port,able radiation monitoring instrumentation. This information was conysyed to the facility training staff in a subsequent telephone ,
conversation between R. Jansky (CNS) and D. Graves (NRC). s
- c. -EXAMINATION MASTER COPIES . m4 Master copies of the Reactor Operator and Senior Reactor Operator license examinations and answer keys are attached.
- d. FACILITY EXAMINATION COMMENTS The facility comments regarding the written examination are attached.
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,,4 U.'S. NUCLEAR REGULATORY COMMISSION -
REACTOR OPERdiOR LICENSE EXAMINATION
- 1. 1 F ACILIT,f : ._QQQEEE__________________.
N y REACTOR _ TYPE: _QWB-qed _________________
ri DATE ADMINISTERED:_QZlQ2LlZ________________
EXAMINEE: _QBaVElt_Qu______________
3 CANDIDATE: . _________________________
IN11BUQIl0N1110_QaNQ1DSIEl
.Una separate paper for the answers. Write answers on one side only.
Stcple questio{n sheet '
on top'of the answer- sheets. Points for each qu:stion arecindicated in parentheses after the question. .The passing grcde requires at least 70% in each category and a' final grade of at-10 cst 80%. Examination papers will be picked up six (6)' hours'after tha examination starts.
, % OF CATEGORY % OF ' CANDIDATE'b, CATEGORY
__Y6LUE- _IDIaL ___SQQBE___ _VaLUE__ ______________Q61EQQBl_____________ -
'I_25tDQ__ _2510Q ___________ _ _ _ _ . . _ _ _ 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, THERMODYNAMICS,
, HEAT TRANSFER AND FLUID FLOW
_2NAQQ__ _25tDQ _____;_____ ________ 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS-
._25tDQ__:_15,tRQ ___________ ________ 3. INSTRUMENTS AND CONTROLS
- _2QtQQ___2dtQQ ___________ ________ 4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL s .
1Q01QQ__ ___________ ________% Totals Final Grade All work done on this examination is my owr.. I have neither given nor received aid.
Candidate's Signature
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[- NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS Ouring the administration of-this exam'ination the'following rules apply: ,
1.: LCh'esting'on the examination means an automatic. denial of your application
.cnd could result in more severe penalties.
- 2. ' Restroom trips are ,to'.be ~1imited and only one candidate _at a time may leave. You murst. avoid all contacts with anyone outside the examination room to avoid even the appearance 1or possibility of cheating.
- 3. Use black ink.or dark pencil 2D1Y to facilitate legible reproductions.
! 4. Print your name in the blank provided on the cover-sheet of the oxamination.
S. Fill'in the date'on the cover sheet of the examination (if necessary).
- 6. Use only'the_ paper provided for answers.
'7.' Print your name in the upper rig'ht-hand corner of the first page of agEb eaction of the answer sheet.
8.- Consecutively number euch answer sheet, write "End of Category __" as cppropriate, start each category on a Dgg page, write 201Y.QD SDt.11dt of the paper, and write "Last Page" on the last answer sheet.
. 9. Number each answer as to category and number, for example, 1.4,.6.3.
- 10. Skip at le'ast ibcgg lines between each arswer.
- 11. Separate answer sheets from, pad and place finished answer sheets face down on-your desk er s. 10.
- 12. Use abbreviations only if they.are commonly used in f acility- litstglurg~.
- 13.,The point value for each question is indicated.in parentheses after the question and-can be used as a guide for the depth of answer required.
114 . Show all cric"lations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or not.
- 15. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLANK.
- 16. If parts of the examination are not clear as to intent, ask questions of thengE951Dat only.
17.LYou must sign the statement on the cover sheet that indicates that the work is your own and you have not received or been given assistance in completing the examination. This must be done after the examination has been completed.
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i 18.fWhen you complete'your examinatiots,.you shall:
- c. : Assemble'your':examinstion as~follows:
L
, , -Ci) Exam-_ questions on-top.
(2) Examinids' : figures,-tables, etc.. +
'(3)- Answer pages; including figures which are partnof the answer.
'b, : Turn-in your copy of the examination and allipages!used to answer Lthe examination questions.
o.. ^
Turn in'all'scrapy. paper and.the balance of the paper that you did-
- -not.use for answering the questions'. r
+ Id . .- Leave the examination area, as defined by the, examiner. If.after-
, leaving,.you are found'in-this area while'the' examination is still in' progress,-your. license may be denied or revoked.
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QUESTION . 1.01. '(1.00)
With the reactor; initially at a K-eff of 0.99, a certain reactivity change causes the' count. rate to double. If this same amount of rcactivity isEagain.added to the reactor, which of the following call be~the'statusoof the reactor? (1.0)
- c. Subcritical
'b.- Critical
- c. Supercritical
- d. Prompt Critical l
. QUESTION 1.02 (1.50)'
. Why does the same reactivity. change result in different periods over core cycle life (assume plant conditions are the same, i.e. temperature,
. pressure,: flow, etc.)? EXPLAIN.. (1.5)
QUESTION 1.03' (1.'00)
-The r,eactor, trips from full power, equilibrium xenon conditions. Four
.(4) hours.later1the reactor is brought critical and power level is main toined on range 5 of the IRMs for several hours. Which of the-following statements is CORRECT concerning control rod motion during this period?
(1.0)
.c. Rods will have to be rapidly inserted since the critical reactor will cause a high rate of xenon burnout.
- b. Rods will have to be withdrawn due to xenon build-in.
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- c. Rods will have to be inserted sir.ce xenon will closely follow its normal decay rate.
'd.- Rods will approximately remain as is as the xenon establishes its equilibrium value for this power level.
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-QUESTION 1.04 (1.50)
Increasing ~ recirculation pump speed will cause WHAT change (INCREASE, DECREASE, or REMAIN THE SAME) in each of the following parameters?
(Assume normal operating conditions.) (1.5)
- c. actual bundle power b .. critical power
- c. critical power ratio QUESTION 1.05 (2.00)
Match each of the power distribution limits'( 1, 2, &3 ) with its ccsociated FAILURE MECHANISM in column A'AND its associated LIMITING CONDITION in column'B (2.0)
- 1. Linear' Heat Generation Rate (LHGR)
- 2. Average Planer Linear Heat Generation Rate (APLHGR)
- 3. Minimum Critical Power Ratio (MCPR)
A-FAILURE MECHANISM B-LIMITING CONDITION A1. FUEL CLAD CRACKING DUE Bl. 1% PLASTIC STRAIN TO LACK OF COOLING CAUSED BY DNB.
A2. FUEL CLAD CRACKING DUE TO B2. PREVENT TRANSITION BOILING HIGH STRESS FROM PELLET EXPANSION A3. GROSS CLAD FAILURE DUE TO B3. LIMIT' CLAD TEMP TO 2200 F DECAY HEAT AND STORED HEAT FOLLOWING A LOCA
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(QUESTION; 1106- -
-(1.50)
- For?..each of-lthe( f ollowing ' parameter'. changes, indicate., the ef f ect'
- Cincrease~,4 decrease,:or.no: change)-it hasi-on AVAILABLE_: net positive cuction_headito the Mai~n Con'densate Pumps.- (1.5).
- c.qtLowericcsdenser botwell leveli o ;b.y : Change lin condensate subcooling ' f rom 2deg F to.1^-deg F
'c .n (Inc re as e --in' plant " powe r -level V ,
- QUESTION't1.07: (2.00)
'c.. Thetreactorois operating at 100% power;and flow.- Explain WHAT-happens>to core flow, and WHY, with a: reduction in, power by
-control.' rod insertion.
Assume, recirculation pump speed remains .
- const ant.- (1.0):
.' b .~ -At low powericonditions '(15-20%),'an increase ~.in-reactor power by
.controlarod withdrawal;will-(INCREASE, 0ECREASE,.or NOT' CHANGE)' flow
'through'the core.- . Choose the correct answer and BRIEFLY. explain
- your choice.- ' Assume recirculation pumps.are running. (1. 0 );
-QUESTIONL.1.08- (3.00)
~ Indicate HOW: C' increase,! decrease, unaffected) control rod worth changes 1for.each of the situations listed.below.
- EXPLAIN WHY the rodLworth-is affected, if-applicable..
-o. .The reactor is heated ~from 100 deg F.to 200 deg F (1.0) bl Reactor power-is increased from 20% to 40% by control rod'
~ withdrawal (1.0)
- c. Reactor ~powerLis-increased'from 70% to 90% by increasing
. recirculation flow (1.0)
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_ QUESTION l .l.09- (2.00)
>o. Describelthe control rod withdrawal method used that.is meant.to thelp eliminate fast period. scrams-caused by high notchyworths. . (1.5)
>b. -.What scram?is designed to shut:the reactor down in-a.-short period situation during'a reactor startup? 'CO.5);
QUESTION 1.10 (2.50)
'The r.eactor;is operating at.100% when one Turbine Bypass Valve' opens and
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,ctays-open.. Indicate how each of the following parameters will respond -
-(INCREASE, DECREASE, or NO CHANGE) steady state to steady: state. Briefly'
, oxplain 'why each responds that way. Assume no operatorLaction. .No.
~oxplanation ~is required f or bH) CHANGE answers, if applicable. . :(2.5)
- c. Turbine steam flow-
- b. Reactor vessel level
.c . - R'eactor power-
- QUESTION 1.11 (2.50)
A reactor startup is in progress. LYou have been given th'e
- cotimated critical rod position for:the conditions at 0800.
LYou start.to pull control rods at 0800'for the approach to-critical.- HOW WOULD EACH OF.THE FOLLOWING conditions or events
' AFFECT 1the' ACTUAL' CRITICAL ROD POSITION (more rod withdrawal, less. rod withdrawal, or no significant effect)?
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- o. Onetreactor recirculation pump is' stopped (0.5)
' * ~ - b.: Shutdown c'ooling is stopped (significant decay heat) (0.5)
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. c. Reactor head vent is inadvertently-closed. (0.5) s d.LModerator temperature is gradually decreasing. (0.5)
Je. Reactor Water Cleanup System isolates (significant decay heat). (0,5)
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k QUESTION.-1.12 (1.00). )
What.are two indications'.the operator may use to1 indicate that natural ~
circulation.is_taking place?.
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- QUESTION. 1.13 (1.00).
U31ng the' ste'am table's,; indicate whether water 1st each of' the 'f ollowing ic SUBC00 LED, SATURATED,'or SUPERHEATED; (1. 0 3 -
' c .' 900'psig, 531.1 F-b.: 1200 psig,'i603.9 F
- c. 1000Lpsig, 544.6 F
'd. -200 psig,'387.7 F:
- QUESTION - 1.1-4 -(1.50)
.lHOW ~will1the Shutdown Margin ~(Reactivity Margin) just prior to a refueling
.out age compare with'the Shutdown Margin following the refueling? WHY?J .
Tuo (2) reasons required. 'C1.5)
QUESTION 1.15 (1.00)
How can' improper core bypass flow-result in-inaccurate LPRM readings? (1.03-(***** END OF CATEGORY 01 *****)
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-QUESTION ^ 2. 01l (2.00)
.[00scribelthe Backup Scram Val've(s) arrangement and: operation,: inc l u'd i ng .
' number of valves,npower supply (ies), normal state, and required operation-
- during anscram.. (2.C)
- QUESTIONi'2.02! (2.'00)
G: The.RCIC system has received a valid. initiation signal and is.
- ramping up;in' speed when'the RCIC, oil-pump fails.' HOW will the' turbine respond and WHY?. (1.0)
'b.. The HPCI: system"has're'ceivedra valid initiation signal .'and its'-
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. auxiliary oil pump' fails to sta'rt. .HOWLwill the turbine respond' and.WHY? (1.0)'
. QUESTION- 2.03 (2.00)
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,0 .. What interlock pravents1 cross-connecting:the-suppression' pool _
- with.thelrea'ctor vessel 1during shutdown cooling operation?' (1.0)
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- What RHRLpump suction valve lineups will cause a trip of~a RHR g Epump? (1.0) fQUESTION 2.04 (2.00)
Jo. Oe' scribe-how the RHR pumps.are loaded onto the critical buses (1.5)
(include timing, as' applicable) following a valid LPCI initiation'if:
1 .~ Lthe1startup transformer is available.
- 2. 'thelstartup transformer is-not available.
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- b. -What.is the most limiting single failure that can occur with regard
'to the low pressure Core Standby Cooling System (s)? .(0.5)
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8-21__EL8HI_ DESIGN _ INCLUDING _SeEEI1_6ND_EMEBEENGl_S11IEMS -PAGE I QU STION 2.05. (2'.50)
- 0. : What will.cause an INCOMPLETE.STARTUP A;(B) SEQUENCE annunciator- ~
wh'en starting-a recirculation pump?. (1.0)
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- b. What-action occurs if an incomplete start seq'uence-is~ detected? (0. 5)-
- c. Describe any(automatic actions that occur in the recirculation system as'a result of' REACTOR PRESSURE. INCLUDE SETPOINTS. -(1.0)
QUESTION 2.06 (3.00) c..:-What.is. Care);the source (s) of pneumatics to the Inboard and Outboard Main Steam Isolation Valve's?' Include. NORMAL.-and BACKUP supplies, as' applicable.- : ( 1.' 0 )
- b. 'What: provides the. power for;the 11SlV normal operating solenoids-and logics? (1.0)
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'c.- ~How does'the loss of power-to one of the MSIV solenoids a f f e c't -
opening an'd closing ability of that MSIV? ,
.(0.5)-
d.. An MSIV' isolation (Group ~I) has occurred. .The operator ~ attempts to reset the isolation without taking the MSIV control' switches
- tc CLOSE.- Does the11 solation reset,-and if so, what happens ,
Lto the MSIV's? (0.5)
QUESTION--2.07 .(2.00)
I .1 QUESTION 2.08 -(4.00)
- c .1 Nameoor list eight (8) of the valve operations that occur on a turbine trip. (2.0)
- b. Name or list four (4) of the five main turbine protective devices'that operate independently to prevent damage to the unit if it was not taken out of service immediately. (2.0)
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,; QUESTION',2.09; .(2.50)- -
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QThe s p lant!;is iop e r at ing at 100%l power'.with-a normal electrical, lineup.
-Nt shen j aD maindgener ator i.tr ip f o'ccurs. . Desc' ribe ;the: p'ossible--sources of f , ;
- 7 powerdto %thejc r it ic al ' buses',Jinc luding :.p r io r it izat ion . of; poss ib le ;
c o u r c e s '.~ _
(2.5):
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p QU'ESTION:l_2.104 -C3.00)' ,
k 4. : HOW?is e an 'ina'dvertentL a~dmiss io'niof .RHR. Service : Water into the.
.RHR1 System prevented.Cphysically, not; administratively)?!
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(0.5)
- , , .. . .. n .. . .. ., .. . . . .
-, RHR-Service Water' system
- e cb. 5Whatfis the: normal 5 relationship-betweenz spressur'e' andl-RHR1 system pressure andi.WHY?
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i' lc.~ 30W -isSthe relationsh'ip11ni"b'? ?above 1:controlle'd or svarie'd? (0.5) u.
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? d ~ [d . - ~ AjRHR Service Water Booster Pump. control switch isipositioned-
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I to'2 START an~d_the1 switch-sticks inLthis position. : Explain ~the
- (1.0)-
undesirability ofi this condition.. -
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_ QUESTION -- 3 , 0 1 -(2.50) r
'Which~ control; room vessel. level indications are affected by recirc
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o.-
. pump-operation?-
( 1. 0 )'
b.- .What affect (s).does(do) recirc pump-operation nave on the vessel level' indicat' ion? (1.0)
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c.' Which level' indicator (s) in the control-room are, intended for use during and after a LOCA blowdown?' -(0.5)
QUESTION 3.02 (3.00)
-State-whether each of the following parameters directly initiates a scram,'
l rod block, both, or.neither. -Setpoints are not required. (3.0) 0 . -- Main steam line radiation b.. APRM flux to. -Drywell pressure d.- Main steam line tunnel temperature
- o. Reactor vessel high. level-
- f. Recirculation flow
' QUESTION- '3 .~ 0 3 (2.00)
What are-the four indications or types of indications that can be displayed by the APRM meters on the control room'back panel 9-14?'
Arsume the APRM channel is in OPERATE. (2.0)
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-QUESTI'O'N. 3i04'. .(3.00)
- c.~ DefineJ or : describe :the three terms ^below pertaining to: Rod Worth i Minimizer operation. Setpoints are NOT' required. (1.5)
- 1. Low Power 1 Set Point (LPSP)'
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- 2. -Transition? Zone 3.-' Low Power Alarm Point (LPAPj
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ib. Reactor; power'is 17%1andsthe RWM is operable.~
-1. How many. withdraw errors will the RWM allow?..
( 0 . 5 31
'2. .How;-manyJinsertnerrors will the RWM allow? .(0.5).
3.. 'W h at restrictions-are imposed'on rod movement-ifEth'e
' allowable number ~u of errors-is exceeded?- (0.5)~
- QUESTION 3.05I (2.00) s.J What two (2)_ conditions may.cause a'RPIS INOP condition?-
(1.0) b .' HOW and WHY. is' control rod movement affected at by the receipt-of a RPIS INOP while moving rods in the-EMERGENCY IN_ mode? (1.0)'
' QUESTION ~ 3.06 (3.00) 1A'nswer_the following with regard to the DEH system:
e.- What are the three (3) inputs to the pressure controller (s)?- (1.0) b.. "Other than overspeed and_ testing, what will activate the Overspeed Protection Control COPC)' system? Include conditions necessary for-
"the-system to activate.- (1.0) a c.. The plant is operating at. full power. Briefly describe the plant response to-a failing pressure controller (controller output is
_ ' INCREASING slowly to maximum). (1.0)
I
?.
,q
(***** CATEGORY 03 CONTINUED ON NEXT PAGE *****)
r.
. + ,
g? PAGE- 12:
(2t__INSIBudENI1_8NQiGQEIBQLS:
QUESTIdNlJ3.07 (2.00); .
~
1
+- ob iThe reactor 9 1s: operating at,100% with recirc flow control in t mas't e r manual. .The feed fl'ow summer 3 fails to 0 gpm flow.- H0W will:the.
- recirciflow1controlfsystem respond to this occurrence and WHY? (1.0)
' ti. ! The f reestorl is f operat teig at 30% power'with re'c'irc: flow-in
~
g individual manual _ control. HOW will the recirc flow control:
.systemLrespond-~:if'the:A recirc. pump M/A transfer ststionxis takenito AUTO and WHY?L .(1.0)-
-QUESTION . 3.08' -(2.50)
- c.; H ow 'may.'_ 'r e ac t o r f eed pump speed be . varied . and: controlled with er Feed Water. Control Signal Failure present? ( 1' . 0 ) ~
- b. 'The-reactorfis. operating at 100%~ power. A main generator malfunction
~
results-in a turbine trip.
s How do the feedwater and vessel level control systems respond to control-level? .(1.5) 1 QUESTION - 3.09 (2.50)
Match the-following valves or. groups of valves (a - e) with their rcspectiverisolation initiating signal (s). More than one signal
- mcy apply. (2.'5)
VALVES SIGNALS c.- Reactor building ventilation valves 1. High-DW pressure
- b .1 Recirculation. loop sample' valves 2. Low reactor pressure-c .- RHR Shutdown cooling. valves (M0 17 & 18) 3. 12.5" reactor level
- d. RWCU-isolation valves 4. -145.5" reactor level
. o .- MSIV's 5. High reactor building pressure
- 6. Group II signal
- 7. MSL high radiation l
.i A
(***** CATEGORY 03 CONTINUED ON NEXT PAGE *****)
_ _ . - _ _ _ _ _ . _ _ . _ - _ . _ - _. - ____e
p . _ _ _ _ _ - . . _
t -.
- r
~
2" 7 e I ,er ,.,4. - .<I...,
. . .,f . , 4 2 c_IN11BudENI1_8NQ_QQNIBQLS . " PAGE ~ 13 '
UESTION.'3.10 -( 2. 50 );
is. : TWhati three ;(3) lig'u'id: streams ~ are monito' red 'by; the liquid ' process' '
radiation;monitoringj-system? ( 1. 0 ):-
- b. . ::Une::channe1:. of' dhe; Air . Ele $ tor L0f f Gas Rad, Moriitor ing ! System has' a:..
' ~
~
idown's c~a le l a ia rm ; p r es e nt . . A sec'ond channel has'a~lHIGH. alarm.7 What> s
' automat ic act ions', if i any,-4 ar e initisted;by j thisfcondition?' .g ( 0. 5 );
~
- c. -
How'would the.respons'enin;part.."b" -above !be . dif f erent - if .the.'second (1.'0)
' channel had a HIGH-HIGH instead of HIGH7-m .
"yh 5 i
i
.+
r c
k 1
~
(***** END OF CATEGORY 03 *****)
~y w
( :- "
ie - ,,
~
idi_lEBQQEQUBE1_i_UQBd8Lt;8BNQBd8Lt_EMEBGENQ1_8NQ. PAGE- :14.
"B8DIQLQQlG8L_GQNIBQLA W :
x 1 '1
^ '(2.50);
. $QUESTIbN i4.011 -
ij
' Allo'ss of?allisiteJAC powerlhas: occurred. Answer:the!following:
~
, , questions ,concerning' ,EOP ' 5. 2. S il, Loss of;All AC= Power Station;
. ' Blackout.-
l0.- What reactor :wate'r level? ind ic at io.s(s ) are'availableein the
' controliroom'following;this. event? .(1.0)
Ib. :What? reactor water level-indicatibn(s'),are'available'outside' '
(the$ control'roo'm following this event?i '( 0. 5 ):
~ ~
o .'- WhyMshould"reactorfpressure.-NOT be reduced.below the saturation
~
pr,essureicorrespondingctolthe-maximum 3drywell1 temperature?- : ( 1.~ 0')
~
? QUESTION 4.02" (2.00):
I'ndica'te whethers.;eachoof the following statements is TRUE or FALSE: -
(2.0).
O.- A reactor st'artup is NOT permissible under' natural circulation
' flow conditions'.
-b.-- 'Afreactor startup is NOT permissible with only one recirculation pump'in operation.
T c .-- =If the reactor-is operating at power (both recirculation pumps in operation) and one recirculation pump trips,-reactor operation mayfcontinue for no more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Td.- .A-reactor. recirculation pump may not be started if the reactor is in natural circulation' flow and reactor power'is greater than-l%.
< QUESTION 4.03 (1.50)
'Whatfare three (3) methods used in the E0P'S to maintain adequate core cooling? (1.5)-
m
(***** CATEGORY 04 CONTINUED ON NEXT PAGE *****)
_ . _ _ _ _ - _ - _ _ _ - - ___A
~
~~~
r .
dz__EBQQEQUBE1_:_NQBdakt_8BNQBd6Lt_EDEBGENQ1_6NQ _PAGE 15-88D10LQQ196L_QQUIBQL
. QUESTION 4.04 (2.50)
- a. What are three (3) areas or locations that will!be manned by operations personnel following an evacuation of the control room? (1.5)
- b. If._the reactor was not scrammed prior to leaving the control room, _ what are two (2)Lalternate methods.of scramming the reactor, _per E0P.S.2.1, Shutdown from Outside the Control Room? C l'. 0 )
QUESTION ,4.05 (1.00)
Boron inj ection into the.recctor-is required per EOP1,-RPV Control, cnd the Standby _ Liquid Control. System is incapable of inj ecting into
.the RPV. Describe basically how boron injection to the RPV is cccomplished_under the-aboveLcircumstances. Specific procedural ,
ctops_ARE NOT required. 4 (1.0)
QUESTION 4.06 (1.00)
Indicate which of the following methods of operating the recirculation
. pumps is more desirable during extended outages (a or b) AND state why the other method _is. undesirable. (1.0)
- a. Run the recirculation pumps continuously at low pressure.
- b. Shutdown the recirculation pumps and restart them when desired.
(***** CATEGORY 04 CONTINUED ON NEXT PAGE *****)
Y
- P J
ilA2_B89EEQMBEl_ _UQBd8Li_8BUQBd8kt_EDEBQENGl_86Q PAGE' -16 88Q10LQGIG8L_CQNIBQL
-QUESTION; 4.07 - (3. 00 3 -
-Morfeachfof the.following conditions, state'which EOPCs),' if : any,.
(3. 0).
'ohould'beientered:
- o. . ~ Suppression' pool level!41.2 inches
=b. :Drywell pressure / 2.3 psig ic.: . Reactor Building exhaust plenum radiation 12 mr/hr AND-site boundary radiation 0.5 mr/hr
- d.-
RPV' level 15' inches,AND suppression. pool temperature:97.deg.F.
.o.' Reactor-power 5% ANDERPV' water level 8 inches AND Drywell temperature 1165 deg F
- f. RPV pressure 1035 psig AND secondary containment differential l pressure -0.25 in.fH20~AND suppression pool level -1.5' inches.
a ' QUESTION _ 4.08
-(1.50)
Goneral Operating Procedure 2.1.4, Normal Shutdown from Power, requires that reactorJ1evel be maintained above WHAT LEVEL'during ' cold shutdown conditions? 'WHY is it~ desirable to maintain level:above this point? (1.5)
. QUESTION 4.09 (1.50)
-During a reactor ~ startup, a control rod is to':be withdrawn. List three
'possible.9-5 panel indications that the control rod is uncoupled.- (1.5)
. QUESTION- '4'.10 (1.50)
'AssumeHan inadvertent initiation of HPCI during power operation has occurred. P e r A P..' 2 . 4 . 4 . 1 , Inadvertent Initiation of CSCS,
-describe what-actions the Control Room Operator (s) should take. (1.5) 4
(***** CATEGORY 04 CONTINUED ON NEXT PAGE *****)
e f r S isl__E80GEQdBES_:_NQBd8Lt_6sNQBd8Li_EMEBGENQ1_8ND PAGE 171-
-88010LQDIG6L_QQNIBQL ,
t # 4
-QUNSTION 4.11 (2.003--
'EP 5.3.10,; Con'tro1JBu'ilding Basement. Flooding,' lists-two.cond'itions
~
cthat--require the operatorsito initiate..GOP 2.1.5, Emergency Shutdown
-from: Power. LISTEthese two-(2) conditions. (2.0)-
-fQUESTION '4.12 ( 2. 0 0 )-
Match-the following1 Emergency Classifications (a - d) with the appropriate-dcscription of that event'(1 - 4). ~C2.0)
- o. General Emergency 1. Any station related event whic'h ino. cates a potentia 1' degradation-of station safety margins, but
- which is' not likely to affect onsite personnel or the publicJor result in radioactive.
releases requiringoffsite monitoring.
b.- Site Emergency' 2. Any1 condition that involves an actual or potential substantial degradation of'the safety level'of the station.
-c.- Unusu'al Event' 3. Events which involve likely or' actual maj o r failures of station functions needed f or -the protection of the public.
'd . Alert 4. Substantial core degradation or melting has occurred with a potential for loss of containment integrity.
QU5STION 4.13 (1.50)
List the'three (3) methods given in CNS Procedure 0.9, Equipment Clearance and Release Orders, that may be used for verifying the
[ptsition of manual valves in the main flow path of safety related Oguipment when it is. returned to service. (1.5)
(***** CATEGORY 04 CONTINUED ON NEXT PAGE *****)
~ ~
~
.e .. . - ~
- fli __EBQQEQuBER_:_NQBd6Lt_8ENQBd8Li;EMEBGENQ1_8NQ- PAGE 18-86DIQLQQIQ8L_QQNIBQL.
-QUESTION: 4 .14 .- (1.50)L --
'Aniirradiated; component-is surveyed with a portabl~e_ instrument.. The cpen'~ window freading :is c 2.65 Rem /hr endithe closed window reading -.is
- 1.75.-Rem /hr. SHOW ALL.WORKi-
- c .7 "What.isithe beta dose. rate at the-instrument,7 ( 0. 5),
~
'b.-
How'long-could one' remain:at the survey point without exceeding
~
~
administrative and 10CFR20 QUARTERLY ' exposure limits? cAssume
~
zero initial exposure and.N0; approvals are received to exceed
~
the' administrative; quarterly limit._ . ( 1. 0 )j i
A t
a
\',)
(***** END OF CATEGORY 04 *****)
'(************* END OF EXAMINATION ***********n***)
^
i l
NRC LICENSE EXAMINATION HANDOUT EQUATIONS, CONSTANTS, AND CONVERSIONS 6=ifi*C*deltaT p 6=U*A*deltaT P = Po*10sur*(t) p ,po.,t/T SUR = 26/T T = 1*/p + (p-p)/X p T=1/(p-p)' T = ($-p)/Xp P = (Keff-1)/Keff = deltaKeff/Keff p=1*/TKeff+feff/(1+X.T) .
A = in2/tg = 0.693/tg X = 0.1 seconds-1
~
I = Io*e "*
CR=S/(1-Keff) 2 R/hr = 6*CE/d feet d
. Water Parameters 4
- 1. gallon = 8.345 lbm = 3.87 liters i
1 ft3 = 7.48 gallons
- -Density 9 STP = 62.4 lbm/ft3 = 1 gm/cm3 l Heat of vaporization = 970 Btu /lbm l Heat of fusion = 144 Btu /lbm 1 atmosphere = 14.7 psia = 29.9 inches Hg. -
!. i L Miscellaneous Conversions 1 curie = 3.7 x 10iu disintegrations per second 1 kilogram = 2.21 lbm i horsepower = 2.54 x 103 Btu /hr 1 mw = 3.41 x 106 Btu /hr 1 inch = 2.54 centimeters degrees F = 9/5 degrees C + 32 degrees C = 5/9 (degrees F - 32) 1 Btu = 778 ft-lbf
irg7 .Yu
- , e
~ . ,
?1i__EBINGIELE1_QE_NuGLE88_EQWEB_EL8HI_QEEB8I1QNt . PAGE 19' lIBEBdQQ188d1Q1t_BE8I_IB8NSEEB_8NQ_ELu1D_ELQW-
?ANSWE'RS'-- COOPER- -87/02/17-GRAVES, D.
" ANSWER' :1.01 (1.00) o?(1.0).
-REFERENCE
- CNS ReactorfTheory; pg.3-8 K/A=.292003:K1'.02 JANSWER 1.02 (1.50)
'TheLperiod' dependsl upon Beta and reactivity. Beta decreases'overfcycle life (0.5),.due to the' buildup of' plutonium-(0.25) and depletion of
.. u r a n i u m ~C O . 2 5 ) , resulting~in a shorter period at E0C ( 0 . 5 ) ~.
REFERENCE 2CNS Reactor Theory', pg 3-29, 30 (K/A.292003 K1.06' ANSWER ~ 1.03' (1.'00)
' b ;(liO) = f
' ~ ' REFERENCE BFNP: XENON & SAMARIUM LP, pp U,
4 12
'EIH: L-RQ606-TCNS Reactor Theory, pg 6-11, 12
'K/AL292006 K1.02,.K1.07 ANSWER 1.04 (1.50).
e.. : increase (0.5) b.' increase (0.5)
- c. decrease (0.5)
REFERENCE.
- 1..fGeneral Electric Thermodynamic, Heat Transfer, and Fluid Flow Te'xt, pp. 9-85, 9-86, 9-92
.2.' CNS Heat Transfer and Fluid Flow, pg 9-27, 28, 38 K/A 293009 K1.23
[
N.. ; ;
'^ilt_iEBINGIELE1_QE_NWQLEaB_EQWEB EL6NI_QEEBoIIQNi -PAGE -
SIBEBdQQ1NedIQ11_BE81_IB8HEEEB_6NQ_ELMIQ_ELQR 1 ANSWERS:'-- COOPER
-87/02/17-GRAVES,cD..
[
, AN'SWER' 1.05 (2.00)
- FAILURE MECHANISM- ILIMITINGLCONDITION '
w .----------------- . ------------------
- 1.-LHGR -A2.
< B1-
/2.,APLHGR -A3 B3 13.!MCPR. Al B2
^
(6 4 0.33 ea m'2'.'0)
REF RENCE-
'CNS1 Heat Transfer and: Fluid. Flow,.p'g 9-15
- BRUNSWICK 11&12, Student Study Guide, 06-2-A,.' item 3.0.
- K/A_293009 K1.08,'K1.12,7K1.20
~
iANSW$R- 1.06- (1.50)' .
ci- 'DecreaseL(0.5).'
b.~. Decrease'(0.5).-
c.
Dec r e as e }( 0.'5 3 '. -
REFERENCE U _:GE HTFF manual, pg 7-93 through 7-96
'CNSnHeat Transfer and Fluid Flow, pg 6-76-through 81 K/A'293006:Kl.10 (ANSWER. 1.'07 (2.00) c' , Core-. flow would increase (0.5) due to a de' crease'in two' phase flow' resistance (0.5).
- b. : Core flow would increase (0.5) due to an increase in natural
' circulation (0.5).
REFERENCE Rocirculation System Description, Figure 19
, 'K/A-293008 K1.29, K1.37 1 4 - ,.-n r ,...m. , , , , _ _ _ _ . . _ _ _ _ _ . , , , . - ,-,.e_ . - . , _ . - . ,,.-.m. .._ .--..m... ._.
m 1 i
Lli__EBINCIELES_QE_NWQLE6B_EQWEB_EL6NI_QEEBellQNt. ' PAGE 21 IBEBdQDINadIGHt_HE8I;IB6NSEEB_8HD_ELUID_ELQW iANSWERS;-- COOPER ~-87/02/17-GRAVES, D.
A'NSWEk 11.08 '(3.00)
- c. : Increase'(0.25). gas.the moderator density decreases, the-neutrons travel: a greater _ distance'and are more likely to
~ ~
~ interact-with_a control rod-(0.75).
- b. Decrease (0.25). TheLvoidsidepress the, thermal neutron flux which?in turn-decreases the-rod worth (0.75).
c.- -Increase _(0.25). . . Rod. worth decreases'as void' content' increases._
'A slight decreaserin void content means the thermal flux is'not quite as> depressed and control-rod 1 worth subsequently increases (0.75).
REFERENCE pg 37
,'CNS.
GE ReReactor' acto r ._ Theo Theory,ry L Review, pg 5-12 through 14-
-K/A 292005 K1.09 a.
e
' ANSWER 1.09 (2.~00)
~
~
- c. The third and fourth groups withdrawn are withdrawn inca banked configuration to the full out. position (Banked Position Withdrawal Method)-(1.5)..
- b. -I RM .. h ig h E f l u x (0.5)
' REFERENCE
.CNS' Procedure 10.13, Control Rod Sequence and Movement Control, Attachment A,-Rev 13, pg 2 of 6
-Roactor Physics Review, pg 50 CNS' Reactor Theory, pg 6-12
'K/A 292005 K1.09 s
g 4 - -
1 ill__EBINCIELE1_QE_UUQLE88 EQWEB_EL681_QEEBallQNi- ~ PAGE' 22' IBEBdQD1NedIQat_BE8I_IB6NSEEB_8HD_ELu1D_ELQW ANSWERS '- ~ COOPER -87/02/17-GRAVES, D.
H h.
~ ANSWER 1.10s (2.50)'
c .~ : Dec'r e ase ' ( 0. 5) . The BPV opening causes a decrease in pressure.._
+
'at the turbine. inlet which causes DEH to close down on the turbine
-governor valves (0.5). ,
- b. No~ Change (0.5) c.- Increase-(0.5).. With the steam bypassing the turbine, slightly;
.lessJfeed-heating takes place, resulting in.a power increase.(0.5).
. REFERENCE *
-GE'BWR Simulator 1 Reactor Physics Lesson Plan BWR4-Transients
' K / A 29 2 0 0 8 ' K 1." 2 2 --
K/A 241000"K1.01, K1.03, K1.04 K/A 241000'A2.03 ANSWER 1.11 (2.50)
~
- c. No-significant effect
- b. More rod withdrawal
- c.HNo;significant effect
- d. Less. rod withdrawal'
-0. .More rodlwithdrawal (0.5 each)
REFERENCE
. Roactor1 Physics Review, Reactivity Coefficients K/A 292008.K1.01, K1.02 ANSWERL 1.12 (1.00)
- some dp should be indicated across the core plate (0.5)
-esome flow should be indicated through the jet pumps (0.5)
'Also accept total core flow and vessel metal temperatures as possible
~ indications.
-REFERENCE CNS= Heat Transfer and Fluid Flow, pg 8-56 K/A 293008 K1.36 t
b.
7- .
yy - -
111_lEBINQIELE1_QE_NVQLEaB_EQWEB_EL6NI_QEEB6I1QNi '
. PAGE 23-
-IBEBdQQXNedIQ1t_HE81_IBeNSEEB_eNQ_ELUIQ_ELQW
-ANSWERS -- C00 PERE . -87/02/17-GRAVES,'D.
' ANSWER 1.13- -(1.00)-
- x. . .
To. Subcooled-b.- 1Superheated
'o.'.:Subcooled "dv ~ Saturated:
'CO.25)each)-
REFERENCE
' Steam Tables K/A 293003 K1.23
. ANSWER 1.14 . (1. 50 )-
- SDM prior.tolthe outagelwill be-larger (0,5) due to fission-product
. poisoning.(0.5) and fuel. depletion'(0.5).
4 REFERENCE'
- LOTM-TH4.1'-0,' l Shutdown Margin, pg 5 ~
CNS Reactor Theory, pg 1-35-and.36 K/AJ292002 K1.14 ,
' ANSWER 1.15 -(1.00)
.Inproper voiding and-neutronLibermalization' caused by abnormal bypass flow-can result in inaccurate LPRM indications (1.0).
REFERENCE '
CNS--Heat Transfer and-Fluid Flow, pg 8 K/A'293008'K1.33 w-- w.
t w 4 --
,-y j g -- p4,-7 y9 g. --y g .yc- -
p im
,, ..p.h- - - * ' '
- r, v, , -= -= .
- g. !,*';. x . _
_ u _-
Y<
g - 1 2t__PL8HI_QE11GN_INCLMQ1NQ_15EEIY_8ND_EMEBQENCY_1111 EMS PAGE-. [24 :
[ANSWERSL-- COOPER :-87/02/17-GRAVES, 0.
ENSWER 2.01 (2.00)
^
-The,two BU. scram valves-(0.4) are upstream of the individual-HCU's individual ~ scram-solenoids.CO.4). -They are normally-' deenergized (0.4).
.The-power. supply is for the valves is 125 vde'(0.4). 10n a scram, the two valves._ energize to' vent the scram: sir header to' atmosphere (0.4).
Bcckup scram valve-location description may vary and still be acceptable.
REFERENCE Control Rod Drive Hydraulics, pg-CRDH-19, 32 K/A 201001 K1.09, K2.03 <
. ANSWER- 2.02- (2.00)~
cn The. turbine will' speed up and trip ~ on overspee'd (0,5)-b'ecause the governor 1 valve will-fail open (0,5).- The turbine may also. trip oon low oil pressure (acceptable,for full credit).
- b. The-turbine will.not start (0.5) because the governor _and stop
. valves' require. oil pressure to open'(0.5) which-is=normally supplied- by the- auxiliary oil pump.
REFERENCE-RCIC, .pgjRCIC-131
-HPCI, pg HPCI-31 4-
. K / A ~ 2 1 7 0 0 0 : A 2 .~0 7 '
'K/A.206000-'K4.14, KS.05 ANSWER 2.03 -(2.00)
- c. The= suppression pool suction valves (M0-13A, B, C, D) cannot be
- opened unless the companion shutdown cooling suction valve (M0-15A, B, C, 0) is shut (0.75) and vice verse (0.25).
bi . _ If MO-17'ORl18 (Shutdown Cooling Isolation Valves) OR the associated
.MO-15:(Shutdown Cooling Suction Valve) AND the associated MO-13
-(Suppression Pool Suction Valves) is shut, the pump will trip (1.0).
REFERENCE RHR, pg RHR-6, 7
,K/A.205000-K4.04, K5.02
, , _ __ _ _ _ _ _ _ . -_ .~. ,, ,_ , __
5%#$NyhN$$b s , ,
i d M' # -
W 7'y .
Y -
A ' M_ j;</ ..
k M. S _
w m, '
1 3 - 4
.2 ,
" * ; s, .. e + s .s
' J *
)
..\l .T
~
- .'. , ,;s . ..? .
? -. . .
. 521 (_EL8HI_DE11GN'_INGLWQINE 18EEII_8NQ_EMEBGENGI_111IEMS ' - >
~ CPAGE1l256
}sgTja - , _ , _
. E dANSWERS M-- ?C00PER' --87/ 0 2 /17-GRAVES ,v D s - 1 s-- g -
4 y s _
~ ' ~
,4 .
.J
, ,p.
. .' ~> a ;, c.
,3 P 4 4 vn '
y .- x .;. ,
9 .
7 _
D2.041 0 ANSWER 7 s
.LC2.~00)~
<- , , .g
. 2h? 14; A1124)p' umps st' art with9no time 1 delay?(0.5)' '
~
. [ ._ .. + - . ..
~
-!2.o As1.soon-as?thejcritical buses are re-energized (0.5),-;RHR 5 pumps; y ,
R s fA;&10~ start:(0.5). . Five seconds.later kB'&.C. start ( 0 '. 5 ) . - <
t .
f-[' r-
$ b. LPCI:inje'e tion vilv dfa'iling shutc(0.5).l REFERENCE ~
[ , iRHR, pg'.RHR-35,L36 .. i ,
- K/A;203000 K1=.05,1 Kl.08, K4i07
/ ; w
,5 \ +( ;
- ANSWERS' 12205 ( 2. 5 0)' ,
ke.2 l f-thbfield breaker-is not shut within 15 seconds ~afterlth'e'-
~
he ld- ~,
pump. sequence is s'tartedJC1.0).-
.s C ti. 4 lThe;recirc'MGidrive1 motor. b'reaker thips1(0;5).
.g j
~
sc. aThe.;recirc pum'ps trip (0.25);on high reactor pressurelof-1120!psig.(0.25).. The recirc pumps ~ discharge'._ valves-shut-(0.25)
Jif- a. LPCI l initiation signal is present.(0.125) and reactorip'ressure; 1 decreases to between 185~and 235 psig-(0.125). -
f
,,REFERENCEL __ .
tRocirculation System, pg RECIRC-10,-27, 31i, Table 31.
K/A 202001 K1.12, K 1 . 2 7 , .K 4 ~. 0 7 , K4.142 K6.06-E d
' outboard MSIV's'is-instrument air (0.33).
lb.
125 VDC (0.5) and 120 VAC (0.5) RPS acceptable for the 120 VAC
- c. The loss ofi one solenoid will not affect the ability of the valve to open oriclose (0.5). Both solenoids must deenergize to close
~the valve. If either is energized, the valve will open.
- d. TheLisolation will not reset (0.5).
1
[
t 52t__EL6NI_QE11GN_INGLuQ1NQ_16EEI1_iNQ_EUEBEENGl_111IEd3 .PAGE -26
,LANSWERS -- COOPER -87/02/17-GRAVES, D.
I~
~ >
. REFERENCE Main Steam System, $g.MS-7, 8, 9, 16 K/A'239001 K1.12, 2.01, K4.01, K6.01 ANSWER 2.07 (2.00)
When the logic-(Low-Low Set) is. armed by. actuation of any SRV (0.5) and
' a high' reactor pressure ceram' signal-(0.5), the logic will lower the cpening and closing setpoints of two SRV's (0.5). The_ valve blowdown 10 also increased (0.5)~from 30 - 120 psi to 143 or 150 psi.
REFERENCE
~ Nuclear Pressure Relief, pg NPR-6, 10, 17 K/A 239002 K4.01, K4.02 ANSWER 2.08 (4.00)
- c. - main turbine stop valves close
- control valves close
- reheat'stop valves close
- interceptor valves close
- bypass' valves open
- feed system startup flew control valve isolation valves open
- feed pump discharge valves close
- extraction steam non-return valves trip
- extraction steam dump valves open
- reactor' feed pump low pressure steam supply valve closes
- main governor valve drain valves open
- RFP high pressure stop valve-above seat drain opens
- MSL~ drains shift from A5 and 85 heaters to the main-condenser (eight required at 0.25 each) b.- - overspeed tripping device low vacuum tripping device
- low bearing oil pressure trip
- thrust bearing trip
- remote controleed solenoid autuated trip
.C4 required at 0.5 each)
REFERENCE Main Turbine and Auxiliary Systems, pg MN TURB-16, 17 Desigi, Change 86-101
-K/A 245000 K4.05, A2.01 l
r ,
R,, ,s , ..: .
Zi;_EL8HI_DE11GN_INGLMDINQ_18EEI1_8ND_EMEBGENQ1_111IEMS PAGE 2 73 4
- ANSWERS - 2000PER. -87/02/17-GRAVES, D.
' ANSWER 2.09 (2.50)
~
The1 critical buses'are:normally supplied from--the station servic'e transformer. A main generator trip will ceuse a lossEof the station
.corvice transformer.' 11'the. start-up transformer' remains energized, iti uill~ pick up"the' station loads. If it is'notn available, and the ccergency transformer is available, it will pick uptthe,-critical' buses.- If it.is.not available, the-EDG will. pick up'the_ buses.
(4~sourcesiat 0.25 each, 1.5 for.the order-of priority, with each.
4 4stiipulation :to .put them in the correct order worth 0.~5) ,
kNFE3ENCE-
_" 7.C flectrical Distribution, pg AC-33, 34
- K v fe :lt 2 0 01 K1. 01, K3.02,-K4.06,-K6.03 .
, ANSWER. 2.10 -(3.'00)
~
.c. Two' manual, locked (sealed) closed valves are in the lino-(0.5).-
- Number of val'ves not required.
-b. RHRSWJpressure is maintained greater thanERHR system pressure (0.5) to:
prevent any radioactive leakage from.the RHR system into the Service Water System-(0.5).
- c. .The pressure relationship ie maintained by varying the position of ,
the RHR HX Service Water Outlet valve (0.5).
-d. 'The RHR'HX Service Water outlet valve will continue to open and RHRSW pump runout could occur (1.0).
1 REFERENCE Sorvice' Water and RHR Service Water Booster Systems, pg SVW-6, 15, 28 K/A'205000 K4.04, K5.02, A2.10
.K/A 203000 K4.13
'~
~ - ,- .,, . . - - __
p --- -.
'79 111__INSIBuuENI1_8NQ_QQNIBQLS~ PAGE -28 e
- ANSWERS --: COOPER- -87/02/17-GRAVES, D.
ANSWER) 13.01 (2.50)
H so.- Fuel' Zone Indicat'i ors'CO.5) on the 9-3 panel. Alsofcalled the x ~Rosemonts. Shutdown Water Level" indicator on the 9-5 panel.-
~
It is a 0. -70crinch Narrow' Range GEMAC (0.5)., Any of the above information'is sufficient as.long as it can be determined which indicators : arebeing 'descr ibed. Ranges, _ locations, etc. are not required _for fu11' credit.
lb.- 'The-indications ar'e pegged:high or otherwise unreliable l(1.0) fc. Fuel Zone?Rosemonts (0.5).'
REFERENCE Nuclear Boiler Instrumentation, pg.N81-5,6 K/A 216000'K1.23, KS . 09, ~ A2.- 09 LANSWER- 3.'02 (3.00) c.- . scram 4
'b. .both-C. sc r am' E.
d 'neither
-o. neither
- f. rod block CO.'5'each)
- ' REF.ERENCE APRM, pg APRM-7, 10:
'RPS, pg1RPS-15 K/AL212000 K1.01, K1.03 K1.05, K1.13, K1.14 ANSWER 3.03 (2.00)
-~ Average core thermal power
-:.The number of. assigned LPRM's that are-in OPERATE LPercentage of rated total recirculation flow
-' individual LPRM inputs to that APRM (0.5 each)
. REFERENCE-APRM, pg APRM-17 K/A'215005 A4.03
i 4 k,
- f.
,PAGE
..121__INSIBOMENI116ND_QQNIBQLS 29 ANSWERSC-- COOPER- -87/02/17-GRAVES, D.
a .c
- ANSWER 3.04
. (3.00)
2 program'is enforcing adherence to?the> control rod < movement'as.
' compared'to.the rod sequence-(0.5) o r :- s im il a r .
- 2. .The transition zone is the power levels-between ghe LPSPfand 3 the1LPAP (0.5). -
'3. The-LPAP is.the power' level-above which all RWM blocks, alarms; Jand error; displays are' discontinued (0.5):or-similar, b' . . l i- 1 (0.5)
'2. .- 3l..( 0. 5 ) l
-3. Rod blocks'will occur;on'all rods except;for the rod (s) required tc: correct the insert or withdraw errors (0.5).
REFERENCE-Rod Worth Minimizer, pg-RWM-6 through 8 ,
K/A 201004 K4.01,--K4.02,;K4.06,'K4.07-
-ANSWER H3 .~ 0 5 (2.00) c .- 1RPISLcard pulled-(0.5) -
Internal' logic; malfunction (0.5) b ~. . Control rod ~ insertion will continue (0.5) but movement with other
.c ' rods _will be prevented (0.5).
-REFERENCE' Roactor Manual Control System / Rod Position Information System, pg'RMC-8, 15 K/A214000 K3.03 e
i.4 g
li__lN118MdENIl_6NQ_QQUIBQLS; PAGE 30=
ANSWERS --. COOPER' -87/02/17-GRAVES, D.
I L '
ANSWER -3. 06- (3.00)
C .- steam header preasure (0.25)
- pressure-setpoint (0.25)
- bias signal (0.25) on one channel (0.25) b.- -None (1.0)
~
REFERENCE Turbine High Pressure Fluid, pg EH-12, Rev 1
-DEH, pg DEH-4, 29, Rev 1 Ocsign Change 86-112 K/A 245000 Kl.08, K3.08, K6.02, K6.06
' ANSWER 3.07 (2.00)
'o. The individual recirc pump controllers will see < 20% total-feedwater Lflow (0.5) and both recirc pumps will runback to 20% C0.5).
- b. The A recirc pump will speed up to 45% speed (0.5) due to the low signal from the Master Controller dual speed limiter (0.5).
REFERENCE-Racirculation System, Figure 14 K/A 202002 K4.02, K6.04, Al'.01 1
ANSWER 3.G8 (2.50)
- a. By the use of the Dahl contro?ler in manual (1.0).
b.- The. feed pump discharge valves shut (0.5) and the startup flow control' isolation valves open (0.5). The Startup Flow Controller, which is normally left in automatic, will attempt to control vessel level (0.5)
REFERENCE Feedwater Control System, pg FCS-8, 10, 23 K/A 259002 K4.06, K4.08, A1.05 l
l l
__ __ _ _ _____ ______ _ _ _ _ l
y ,, ,
+ m- -
e +
,- g -
7 - ,
12i_JIN11811t!ENI1_6NQ_GQNIBQLS PAGE 31'-
b
~
ANSWERS -- COOPER. -
-87/02/17-GRAVES,'O.
a . . . .
- ANSWER <3.09 -(2'.50);
ia . -
I fo; .6 ;(0. 5):
,Jb.;l4, 7-(2-a't.l0.25 each):
f c, - 1,c3;C2?at 0.25 Teach)(also accept l6)
- d.. . 3 (0. 5 3 ' ~ .
ick 2,-4,J7'(3~-at'O.17 each).
t" ' REFERENCE. >
, =Cdntainment, Table'2 ' '
K/A'223002JK1.01, K 1.' 0 2, ." K1. 0 3, K1.06, K1.08
-ANSWER 3.10 -(2.'50)
E
- c. -
Service water-effluent
-REC
~-
- Radweste effluent-
..C3 sti0.33 each)-
~
- b. : Nonei(0.5) Accept. alarm.
. c. -Theloff' gas timer'would befinitiated (0.5). After's delay of-tapproximately 15~ minutes,-the off gas system isolates-(0.5).
. REFERENCE'.
-Rediation Monitoring Systems,~pg RMS-8, 25, 26 K/A 272000 K1.12, K1.21, K3.05, K4.03 L
e
= } +,' ,e-% --e, ,M*-9 - m- 7 e p-g 7 g- .-1 y',----+y- sp c --,m w y ----+e-- -
y3 m -
ai__EBQGEQUEER_:_NQBd8Li_8HNQBd6Li_EdEBQENGl_6ND- PAGE 32 2B8DIQLQQ196L_GQUIBQL
-ANSWERS ~-- C00PER'
- -87/02/17-GRAVES,_D..
.c:
ANSWER.. _4. 01, ~.(2.50)
- e. -The.3 GEMAC's and associated: recorder on panel.9-5-(1.0).
- b. The Yarways mayLbe monitored locally in the Reactor Building (0.5).
c.- The reactor' vessel level. reference legs.will:begin to flash when' 1
'the RPV pressure approaches saturation' pressure for the,drywell temperature, causing. erroneous high reactor level indication:(1.0).
REFERENCE CNS E0P 5;2.5.1,1 Loss of-All' Site AC Power Station Blackout,-Rev-3,- pg 3 K/A~216000 A2.06, System Generic 1 APE;295003LAA2.02 ANSWER ~ 4!02~ '(2.00) 7
-c. True
- b. False
'o.= False.
-d. True
'CO.5'esch)
~ REFERENCE-GOP 2.1'15,fReactor Recirculat' ion Pump Startup and Shutdown, Rev118, pg 2:
. q CNS Technical. Specif ications 3. 3.F.
K/A 202001 System Generic 5 ANSWER 4.03 ( l~. 5 0 ) -
-1 Maintain level >TAF (0.5)
-: Maintain adequate steam cooling (0.5)
-.Maintein adequate spray cooling (0.5)
~
1 REFERENCE E0P Text'Rev 1 EPE 295031 EKl.01, EK3.02, EK3.03, EK3.04 l
'Al;_EBQQEQuBE1_:;NQBM8Li_8BNQBd&C1_EMEBGENGl_8NQ. PAGE '33 p -
?B8Q10LQQ1Q8LiGQNIBQL-ANSWERS -- COOPER -87/02/17-GRAVES, D.
< ANSWER 4.04- (2.50)
[0. . Reactor ~Buildin'g RCIC Pump Area-o-; Control BuildingfCable Spreading Area Turbine Buildin'.4160V Switchgear. Room-
- 1 Turbine Building Control: Corridor; 882'_ . . .
-nTelephone Switchboard'in.the Administraiion Office-
- Reactor. Building 931'6" instrument' racks
- Alternate Shutdown Panel
-(31 required at 0.5!each)
~
- Deenergize the APRMs at_the RPS Power Panels (0.5) b.
- Trip the Scram Discharge Volume High-High level switches (0.5)
' REFERENCE;
'CNS~EP 5.2.1, Shutdown From Outside-the. Control Room, Rev 13, pg 1,2
.EP 5.4.3.2
' APE 295016 AA1.01,'AK2.02 ANSWER 4.05 (1.00)
REFERENCE-Energency_ Procedure 5.2.14, Alternate Means to Inj ect Boron to RPV, Rev 0
'EPE'795037.EK2.13 LANSWER 4'.06 (1.00)
'b is the desired method of operetion (0.5). Operation continuously at
- low pressure shortens the seal life (0.5).
REFERENCE CNS Procedure 2.2.68, Recirculation System, Rev 25, pg 15 lK/A 202001' System Generic 10 y
i
. . . .. .. . - _ ~ - _ _ _ _. ___
~ dt__88QQEQMBEl_:_NQBdakt_6BNQBd8Lt_EUE89 ENQ1_66Q ' PAGE 34
-BaQlDLQQ198L_QQUIBQL ANSWERS -- COOPER -87/02/17-GRAVES, D.
ANSWER 4.07 (3.00)
O.. None (0.5)
- c. E0P-3 (0.5).
- d. E0P-2 (0.5)
- c. E0P-1 (0.5)
- f. None (0.5) 44 REFERENCE-EcergencyJProcedure 5.8, E0P/C, Rev 1, pg 1 System Wide Generic'for Emergency and Abnormal Plant Evolutions, SG11 ANSWER 4.08 (1.50) 48 inches (0.5) to aid in natural circulation or thermal convection (1.0).
REFERENCE GOP 2.1.4, Normal Shutdown from Power, Rev 24, pg 2
-System Wide Generic SG10 ANSWER 4.09 (1.50)
- no observable response on the nuclear instrumentation as the rod is being moved (0.5)
- R0D OVERTRAVEL alarm past position 48 (0,5)
- Blank rod position indication on 4 rod display past position 48 (0.5)
- Also accept ROD DRIFT alarm as one of three indications.
REFERENCE APL2.4.1.1.2 Uncoupled Control Rod, Rev 3, pg 1 IP 4.3 RMCS, Rev 11, pg 12 K/A 201003 System Generic 15
F V
st__BBQQEQQBEl_:_UQBd6Lt_8BNQBd6Lt_EdEBGEUQ1_6NQ PAGE 35 88DIQLQQIQoL_QQUIBQL
~ ANSWERS -- COOPER -87/02/17-GRAVES, D.
L AN' WER' 4.10 (1.50)
- Verify if HPCI is needed (0.5)
- Depress turbine trip pushbutton and hold (0.5)
.- Lockout Auxiliary oil pump when the turbine is stopped (0.5)
REFERENCE AP 2.4.4.1, Inadvertent Initiation of CSCS, Rev 6 K/A 206000-A2.17
- ANSWER 4.11 (2.00)
- Flood water exceeds 8" (1.0)
- If all station air compressors are lost (1.0)
REFERENCE EP 5.3.10, Control Building Basement Flooding, Rev 5, pg 2 APE 295006 SG11 ANSWER 4.12 (2.00)
- c. 4
- b. 3
- c. 1
- d. 2 (0.5 each)
REFERENCE EPIP 5.7.2, 5.7.3, 5.7.4, 5.7.5 System Wide Generic Statement for Emergency and Abnormal Plant Evolutions SG2 Plant Wide Generic 294001, f.16 ANSWER 4.13 (1.50)
- Position light indication in the control room if the valve is so equipped (0.5)
- Locally by a second operator (0.5)
- Satisfactory performance of a flow operability surveillance (0.5) l
h _
z _
- - .r-lh; ~ ,fN
- Q~
1_
~
s dsh_EBQGEQWBEl_=_NQBd6Li 8ENQBd8Lt_EUEBGENG'LeNQ :PAGEi;36' 1'
< 188Q10LQHIGAL_GQNIBQL -
- ANSWURS;--} COOPER- -87/02/17-GRAVES,fD.
~
>R5FERENCE-
< (CNS2Proce'd'ure 0.9,fEquipment clearance ~and. Release 10r ders; :Rev.-4, pg(41 .
NK/A1294001 PlantfWide Generics ~K1.02- -
JT
4.14.-
SANSWERi (1.50)-
c.' 2.65.-11'75~='O.9 Rem /hr-(0.5)
.'Also' accept-beta corre'ction, factor'if used.- *
~
Eb. ~ 1.75 Rem /hr gamma' field'CO.2)
'10CFRDlimit 1. 2 5. R em / q t r. . ' f,0. 2 3 -
.-CNS - limit c1. 0 Rem /qt r-' (0. 2)
L 10CFR20:- l'.'25/RemL/ (1~.75 Rem / h r ) = . 4 2. 8.L minut es n(0. 2 )--
j cNS L-.l im'it : .1.0 Rem-/EC1.75. Rem /hr) = 34.3 minutes CO.2)-
o
- REFERENCE
- CNS'HPP.~9.1.2.1; Radiation, Contamination,-and Airborne l Radioactivity-X
- Limits,.Rev 16,-pgf4,15- '
.Rediological- Fundamentals -
PlantfWide' Generics 1294001 K1;03 9
f.
- ~
}
I
);
l' E U..S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION h
! FACILITY: _CQQEE8__________________
REACTOR TYPE: _BWB-qed _________________
DATE ADMINISTERED: _BZLQ241Z________________
EXAMINER: _QBaVESt_Qt______________
CANDIDATE: _________________________
INSIBUQIl0U1_IQ_GaUQlRBIE1 U00 separate paper for the answers. Write answers on one side only.
Stcple question sheet on top of the answer sheets. Points for each
., question ore indicated in parentheses after the question. The passing 9rtde requires at least 70% in each category and a final grade of et lacst 80%. . Examination papers will be picked up six (6) hours after tho exsmination starts.
% OF CATEGORY % OF CANDIDATE'S CATEGORY
__VaLUE_ _IQIaL ___1QQBE___ _YoLUE__ ______________QaIEQQBl_____________
_25tDQ__ _25tDQ ___________ ________ S. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND THERMODYNAMICS
_25tDQ__ _25tDQ ___________ ________ 6. PLANT SYSTEMS DESIGN, CONTROL, ,
AND INSTRUMENTATION
_25tDQ__ _25tDQ ___________ ________ 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL
_25tQQ__ _2QtQQ ___________ ________ 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS 100t00__ ___________ ________% Totals Final Grade All work done on this examination is my own. I have neither given nor received aid.
(
Candidate's Signature o
NRC RULES nND GUIDELINES FOR LICENSE EXAMINATIONS During the' administration of this examination the following' rules apply:
- 1. - Cheating on th . examination means an automatic denial of your application cnd could result in more severe penalties.
'2. Restroom trips are to be limited and only one candidate at a time may leave. You must avoid all contacts with anyone outside the. examination room to avoid even the appearance or possibility of cheating.
- 3. Use black inkfor dark' pencil 90lY to facilitate legible reproductions..
- 4. Print your name in the blank provided on the cover sheet of the examination.
- 5. ' Fill in the date on the cover sheet of the examination (if necessary).
6.- Use only the pap'er provided f or answers.
7.- Print.your name in the upper right-hand corner of the first page of gggh eection of the answer sheet.
-8. Consecutively number each answer sheet, write "End of Category __" as cppropriate, start each category on a Dgg page, write SDlY 2D SDg Ridg of the paper, and write "Last Page" on the last answer sheet.
t: 9. Number each answer as to category and number, for example, 1.4, 6.3.
- 10. Skip at least tbtgg lines between each answer.
- 11. Separate answer sheets from pad and place finished answer sheets face down on your desk or table.
- 12. Use abbreviations only if they are commonly used in facility 111gEgiurg.
- 13. The point value for each question is indicated in parentheses after the question and can be used as a guide for the depth of answer required.
- 14. Show all calculations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or not.
- 15. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLANK.
- 16. If parts of the examination are not clear as to intent, ask questions of the gngm1Det only.
t
- 17. You must sign the statement on the cover sheet that indicates that the work is your own and you have not received or been given assistance in completing the examination. This must be done after the examination has been completed.
t
N , - -
( .. . <
{ y; ;
'4, r
d'*'-
+
1 1
. - , s
- P G s.
- - _
r 7
[18MWhen:youEcomplete',yourLexamination,you-shall:
. . . +
-o..-Assemble;your1 examination as'follows:
( 1 ) Exam questions:on top.
(2):.' Exam imidsl- figures,. tables,:etc.
s (3): Answer:pages' including . figur.es which.are'part of the. answer.-
b '. - ~ Turn' in.:your' copy-; of 'the examination-c and 1all' pages'. used t'o . answer the examination questions.
,- c.; :. Turn.in all~ scrap paper..and.the= balance _of the paper"that you Udid! s-m, . not use for(answering the~ questions.
,x. .
t - - -
- d. . Leave theiexamination area, as:definediby'the examiner. If.after-leaving, you'are.found~in'this' area'while-the examination is still
~
-in progress,: yourilicense may be denied, or revoked.
1 a
4^'T
. _ . . . . . l
~
m E!; 51__IBEQBl_QE_NUQLE8B_EQWEB_EL6NI_QEEB8I198t_ELul01i_8N Q ' PAGEi 2'
.IBEBUQQ1N6MIQ1+
s QUESTION L5.01 (2.50) as Concerning control rod worth.during a: reactor startup with 100%. ( l'. 5 )
-peak' Xenon versus_a startupLwith Xenon free conditions,.which 1 statement'below is correct?1 JUSTIFY YOUR CHOICE.
- 1. Peripheral' control. rod worth will'be lower during the 100%
. peak Xenon)startup-than'during th'e Xenon' free 1startup.
=2'. Central: control rad worth'will be higher during the 100% peak'
. Xenon /startupEthan.during the Xenon' free.startup.
-3... Peripheral control' rod, worth will be higher during the 100%
~
peak. Xenon startup'than during the Xenon free startup.
~
- 4. =Both central.and per'ipheral control' rod worth will be the same regardless;of core Xenon concentration..
- b. 'Nnswer the following questions as TRUE or' FALSE, given that the unit :was at rated conditions when a Reactor Scram occurred.. (1.0)~
[ existed. (Assume a-bottom peaked axial flux distribution.):
- 2. At the time of peak Xenon conditions, the core is free of 1135.
QUESTION 5.02 (3.00)
For each of the following parameter changes, indicate the effect (increuse, decrease, or no change) it has on AVAILABLE net positive
.cuction headEto the Main Condensate Pumps. Briefly EXPLAIN your cnswer. Consider each change separately.
o.. Lower condenser hotwell level (1.0)~
b.. Change in condensate subcooling from 2 d*q F to 1 deg F (1.0)
' c .2 . Increase in plant power level (1.0)
')
(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)
\,,_. .. . . .
-- - __ A
Sz__IBEQBl_QE_NQQLE68_EQWEB_EL6NI_QEEB6110Nt_ELUIQ5t_6NQ PAGE 3 IBEBdQQ18801QS QUESTION 5.03 (2.50)
Which BWR thermal limit (s) must be maintained'within design values to
'cncure adequate thermal' margin during: (2.5) 0.' normal steady state operations
~b. transient conditions-
.c. accident conditions QUESTION 5.04 (3.00)
Answer the following!with regard to the Control Cell Core (CCC) operating
'otrategy:
O. What constitutes a CONTROL CELL? (0.5)
- b. How many control cells will be used at CNS? (0.5)
- c. While operating at power, what is the position of the non-control cell control rods? (0.5)
- d. 'Why do control rod. movements result in a lower kw/ft change por notch in a CCC than in a conventional core? (1.0)
- o. TRUE or FALSE. Usinc the CCC operating strategy eliminates the need for control rod sequence exchanges during a cycle. (0.5)
QUESTION 5.05 (2.00)
What adj ustment is made to the MCPR limit for:
- a. Core flows less than rated flow? (1.0)
- b. Single loop operation? (1.0)
(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****) -
. __ ______________________________________-______._J
F F
s a . .
L5z__IHEQBY_QE_NVQLE88_EQWEB_ELaNI_QEEB6110NL_ELVIDSt_8NQi PAGE 4 o IHEBdQQ1NadIQS s
I
' QUESTION'15.06- - -(3.00) .,
~ ~
'd.?-HOW will the' Shutdown. Margin.(Reactiv'ity Margin).;just prior to a-
~
refueling;outageRcompare with.the1 Shutdown Margln following the refueling? WHY?. -Two 2(2) . reasons required. ( 2. 0 )'
Eb '. -' Compliance with.the. Reactivity. Limitation CCore Loading) ensures WHAT'aboututhe' design 1 shutdown capabili'ty'of_the= reactor? (1.0)
. QUESTION -5.07 (1.00);'
- ARRAN'GE the-following in; order of INCREASING heat transfer coefficient.
- (Lowest ^oefficient to Highest Coefficient). (1.0)'
- o. Free: Convection, Air
- 15. -Boiling' Water-(Free Convection)
- c. Boiling. Water (Force'd convection)
- d. Forced Convection,~ Water
- o. - Forced Convection, Air
(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)
a: -
45x;;IBEQBk_QE_NuGLEaB_EQWEB_EL8NI_QEE86IIQNt_ELu1Dat_eND' PAGE :5'
. -IBEBdQQ188d1QS g.
4 QUESTION '5.08- ' .(1.00) -
A react'or heati balance was performed-(by hand) during the-midnight chift~dueLto'.the Process Computer being 000. .The GAF's were ccmputed,'but!theEAPRM GAIN ADJUSTMENTS'HAVE NOT BEEN.MADE.-
LWhich of the f.ollowing statements :is TRUE concerning ' reactor -power? ,
- (1.0)
- SELECT.-ONLY10NETANSWER COnly onetis truel).
' c. If.the feedwater temperature used'in the' heat. balance calcu lation- was LOWER than - the actual feedwater temperature,-then the -
actual-power'is HIGHER than.the currently calculated power.
b.: If the reactor recirculation pump heat input used in the heat balance calculation'was OMITTED, then the actual power is LOWER than'the currently calculated' power.
c.- If"the steam flow used in the heat balance calculation was LOWER-than the actual steam flow, the'n'the' actual power is LOWER than the currently calculated power..
QUESTION 5.09 (3.00) 0: scribe (INCREASE, DECREASE, OR UNCHANGED) the effect on void fraction, doppler reactivity and feedwater enthalpy due to a recirculation flow rcte increase at power. EXPLAIN WHY for each change. (3.0)
I
(***** CATEGORY 05 CONTINUED ON NEXT PAGF *****) !
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-+
tQUESTION, 5.10 (1.50)
- 4 100 scribe the period indic at ion( POSITIVE; : NEGATIVE, -- o r INFINITE)'and'the;
~
JSRMilevel-l indication (INCREASING,.0ECREASING, or CONSTANT) for a reactort
- -th'at is ' 1 ( l'. 5 )
C. -subcritical b '. - ~ exactly critical To. slightly-supercritical NOTE: . Assume--that-conditionssare' constant.Any indication that can
- stabilize has-done'sofand any' indication:that is changing is-changing atEs constant rate.-
= QUESTION- 5.11 (2;50).
e.- HowLdoes-the EFFECTIVE DELAYED NEUTRON FRACTION.(BETA BAR EFF.)
compare'in value to the CORE AVERAGE DELAYED NEUTRON FRACTION:(BETA
-BAR)? Answer with GREATER THAN LESS THAN, or EQUAL'TO. _
.(0.5)
,b. .Two-competing effects account for any difference-that exists.in the
.above two' terms. Describe these two effects. (2. 0 )~
4
?
(***** END OF CATEGORY 05 *****)
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5
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,- QUESTION 6.01 (2.00)
D: scribe HOW and WHY a-leak on a reactor vessel' level indication refer-cnce' leg isolation valve will affect that indication. (2.0)
~ QUESTION .6.02 (3.00)
State whether each of-the following parameters directly initiates a scram, rod block, both, or neither. Setpoints are not required. (3.0)
- c. Main steam line radiation
- b. APRM flux
- c. Drywell pressure
- d. Main steam line tunnel-temperature
- o. Reactor vessel high level
- f. Recirculation flow QUESTION 6.03 (2.003-
.DCscribe how the failure of a single backup scram valve to function on a ceram does not prevent the backup scram system from venting the scram air haader. (2.0) e QUESTION 6.04 (3.00)
- o. The HPCI system has received a valid initiation signal and its auxiliary oil pump fails to start. HOW will the turbine respond and WHY? (1.0)
- b. How would the turbine respond if the HPCI flow transmitter had been failed, indicating 0 gpm flow (auxiliary oil pump functioning properly)? (1.0)
- c. How can turbine speed control be restored in the event the failure of part "b" occurred? (1.0) i
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?-
[_ _.__.____._m_ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _
l.
J 61__EL8HI_d1SIEd1_QESIQNt_QQNIBQLi_660_INSIBudENI8IIQUI PAGE '8 g IQUESTION ~6505 ' (2.00) c.
~
What two..(2)- conditions may cause "a' RPIS INOP1 condition?. (1.0) b.;:HOW and.WHY is control rod! movement affected at by the'receiptoof a . RPIS' INOP' whileLmoving ~ rods 'in the EMERGENCY- IN mode? JC 1.~ 0 ) '
? .
EQUESTION' 6.061 ,( 3. 0 0 ) ~
Answer'the following with~ regard.to?the DEH system:
- a. What are-the-three (3) inputs to the1 pressure controller (s)? (1.0).
b.- Other.than overspee'd and' testing, what will activate.the Overspeed Protection Control'(OPC) system? Include conditions necessary for the system to activate. -
(1.0)
- c. The plant is operating st full power. Briefly describe the plant
' response to a failing pressure controller.(controller output is
~ INCREASING slowly to maximum). -(1.0)
- QUESTION 6.07 -(2.50)
,0.' .How may reactor feed pump speed be varied and controlled with a Feed Water' Control Signal Failure present? ( l'. 0 ) .
- b. The reactor is operating at 100% power. A main generator malfunction results'in a turbine trip. How do the feedwater and vessel level control systems respond to control level? (1.5)
J
' QUESTION 6.08 (2.'50) c.- What three (3) liquid streams are monitored by the liquid process radiation monitoring system? (1.0)
- b. One channel of tha Air Ejector Off Gas Red Monitoring System has a downscale alarm present. A second channel has a HIGH alarm. What
. automatic actions, if any, are initiated by this condition? (0.5)
- c. -How would the response in part "b" above be different if the second channel had a HIGH-HIGH instead of HIGH7 (1.0)
(***** CATEGORY 06 CONTINUED ON WEXT PAGE *****)
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. QUESTION' 6.09' L(2.50) S ,
.. ;r i
Th'eiplantLis' operating at'100% power with a normal' electrical' lineup
-then L-a' main ; generator-itr ipf occurs.
Describe the7possible sources:of Lp werito the; critical l buses, : including _prioritizationiof possible f'., fpources.- ~ '
(2.5) a
.Y lQUESTION-_6.10 -(2.50) s <
D o .' s What.will causeLan ~INCOMPLETEISTARTUP-A CB):. SEQUENCE annunciator.
'l when starting a? recirculation pump?_
i (1.0)
'b - Whatsaction-occursiif fan incomplete ~ start sequence is detected? (0.5)
E c '. _ Describe 1any automatic actions'that occurrin-the1 recirculation system 1as a result-ofLREACTOR< PRESSURE. INCLUDE SETPOINTS. (1.0)
J p
i
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d
(***** END OF CATEGORY 06 *****)
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, :QUESTION L7.01 _(2.50)
{ Ailoss of y all site ~ AC po'wer has - occur red. --: Answer the f ollowing squesti'ons concer'ing EOP 5.2.5.1,1 Loss of All AC Power Station
' Blackout.
10 . .- What-reactor 4 water level-indication (s) are available in the control room following.this. event? (1.0)
. .b. =What reactor water leveliindication(s) are'available outside ~
theicontrol room-following this event? '(0.5)-
fe. !Why should reactor pressure NOT be reduced below-the saturation pressure corresponding to the' maximum.drywell-temperature? (1.0)
QUESTION- 7.02 (2.00)
Indicate'whether each of the following statements-is-TRUE or-FALSE: (2.0)
- o. . A reactor,startup.is NOT
- permissible under natural circulation flow conditions.
Lb. AIreactor .startup :is NOT permissible .with only one recirculation pump in operation. ,
- c. If-the reactor is operating' at power (both recirculation pumps-in operation).and one recirculation pump trips, reactor operation may continue for:no more'than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- d. A reactor recirculation pump may not be started if the reactor is'in natural circulation flow and reactor power is greater than 1%.
4
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L QUESTI'ONi7.03 , (3.00)
M For."each:of..theifollowing' conditions, stste;which E0PCs),->if any,,
~
~
iqhould:be entered:L ~- ( 3 . 0 )
- o. . Supp r ess ion' poolf level 41.'2- ~ inches ~
. b l. - Drywell pressure 2.31psig -
- c. - ReactorfBuilding exhaust" plenum. radiation 112 mr/hr~AND site '
- boundary r'adiationc0.5 mr/hr 1d. 1RPV."levelil50 inches:A'ND suppression pool temperature 97.deg F
- o .- Reactor power 15% AND1RPV; water level 8 inches'ANDLDrywell
. temperatu're 165 deg~Ff '
'f.i RPV pressure 1035 psig AND secondary-containmentfdifferential pressure 40.'25Lin. H2O AND suppression pool level -1.5 inches.
QUESTION- 7.041 -(2~50)
,. .,0.- The procedure covering inadvertent initiation of'CSCS discusses'two
- events-that the operator-should be aware of that could result in inadvertent initiation. Give one of these events.- (1.0)
.b. Assume an inadvertent. initiation of HPCI during power oper'atio'n-has1 occurred. Per AP 2.4.4.1, Inadvertent Initiation of CSCS,-
describe'what actions the Control Room Operator (s) should take. (1.5) .
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-86D10LQQIC6L_GQNIBQL;
-QUESTION 7.05 (1.50).
If the Control Room must be evacuated during power operation and a7 plant chutdown conducted from outside'the: Control Room, the shift watchstanders cre initially required to proceed to certain designated operating stations.
M tch each-of the watchstanders listed below (a - f) with their assigned cperating station. (1.5)
- c. Balance of. Plant Operator 1. Turbine Building Control Corridor, 882' 2.
~
- b. Reactor Operator Telephone Switchboard Administration Building
- o. Turbine-Building Station 3. RCIC pump area Operator
- d. Reactor Building Station 4. Instrument' Racks 25-5 & 25-6 Operator
- c. Shift Supervisor 5. Cable Spreading Room
- f. Control Room Supervisor 6. Turbine Building 4160V Switchgear Room QUESTION. 7.06 (2.50)
- c. List three (3) of the four conditions that require issuance of a Special Work Permit per HPP 9.1.1.4, Special' Work Permit. (1.5)
- b. A Special Work Permit may remain in effect for WHAT NORMAL LENGTH of time (EXPIRATION period)? (0.5)
- c. TRUE or FALSE. A Special Work Permit may be extended past the above expiration date, but not more than 7 days. (0.5) i
(***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)
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. -QUESTIONE 7.07. (3.00)
'Answerfthe1.followingswith regard to GOP;2.1.1, Col'd.StartupfProcedure'
~c.; Who mayl alter the sequence' ofistep' performance.in-this procedure?
4
-TWO required for full credit..
- _(1.0)
- b .. _ What-restriction is.placed on-performingLsteps out'of sequence?
( 0 .~ 5 3 -
Jo . Who-mayfperform the independent-verification of_ control rod moves l
performed with the' Reactor; Mode switch in STARTUP or.RUN?: THREE
- i'- <
required.for' full credit. . (1.5)_ .
k
' QUESTION _ 7,08- -
,(2.00)
Briefly L describe HOW f uel - preconditioning isn accomplished, ' WHY- it is ' '
snocessary, and WHAT.it allows. NO VALUES ARE REQUIRED.' (2.0)
~
-QUESTION 7.09 (1.00)
Boron' inj ect ion into_the reactor isirequired=per E0P1, RPV Control, Ecnd the Standby-Liquid-Control System isiincapable of injecting into the RPV.- Describe basically how boron inj ection to the RPV 'is.
, secomplished under'the above circumstances. Specific procedural
.eteps,ARE NOT required. (1.0)
QUESTION 7.10 (1.00) .
' Indicate which of the following methods of operating the recirculation-
' p u m p's is more desirable during extended outages (a or b) AND state why the other method is undesirable. (1.0)
-c. Run the recirculation pumps continuously at low pres,sure.
- b. Shutdown the recirculation pumps and restart them when desired.
1
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9
~
- QUESTION 7.11'
- (2.00)
'.EP'5.3.10, Control Building Basement. Flooding,' lists;two' conditions fthatJrequire,the operators to' initiate GOP 2.1.5, Emergency Shutdown i
from' Power. ' LIST'these'two (2) conditions..
(2.0);
' QUESTION 7.12' =(2.00)
(1.0)
?b._s What two (2)'actionsvshould be performed, if time-permits, prior-to scramming the-reactor per GOP.2.1.5, . Emergency Shutdown from Power?- (1.0)
(***** END OF CATEGORY 07 *****)
1
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'az__eQd1NISIBel1VE_EBQGEQMBESt_GQNRIIl0 Nit _eUQ_LidIIeIIQN1 PAGE 15 QUESTION 8.01 (1.50)
The Shift Supervisor's duties include supervising to assure that.the plant is-operated safely and in accordance with WHAT THREE(3) documents or-groups of documents? (1.5)
QUESTION 8.02 (2.00)
-c.. What conditions require that the Shift Technical Advisor position be manned (three required)? (1.5) b '. The STA must be available to be in the Control Room within a specified length of time. What is this length of time? (0.5)
QUESTION 8.03 (1.50) rs . Who must approve a temporary change to a procedure prior to its use? (0.5)
- b. What condition must the temporary change meet before it should be approved by the above individual (s)? (0.5)
- c. A temporary procedure has been approved for use. It has not been incorporated into a permanent change yet. The procedure'must be used again. Does the use of the temporary change again require the review and approval of "a" above? (0.5)
QUESTION 8.04 (2.50)
List five (5) hazardous materials in use at CNS, excluding combustibles cnd radiation hazards, per the Hazardous Material Control procedure. (2.5) 1
(***** CATEGORY 08 CONTINUED ON NEXT PAGE *****)
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eat __6Dd1NISIB811YE_EBQGEQUBEft_GQNQ1110 net _6ND_ Lid 1I6IIQNS .PAGE -16 l QUESTION 8.05- -(3.00)-
~
s.' A piece of' equipment is-to be. worked on by maintenance. .What two_(2) conditions must be'~ met-for the' work to be performed WITHOUT1the~ use of..an-Equipment Clearance;and Release ~ Order? (2.0)
-b. What is the difference in purpose between an Equipment Clearance and Release Order and an Equipment Safety--Caution Tag Order? (1.0)'
~
- QUESTION 8.06 (2.00)
~
What are'the two ~(2) criteria-used by the Shift Supervisor to-determine ._
'the acceptability of a surveillance's results? (2.0)
~ QUESTION 8.07 (2.00)
- e. Who, at CNS, has-the-authority to order the reactor started up? ( 0. 5) ~
- b. :Who has the authority to order the plant shutdown for planned maintenance or refueling? (0. 5 3 '
- c. -Who ALWAYS has.the authority to shut the reactor down, and under what condition (s)? (1.0)
QUESTION 8.08 (2.00)
State four (4) of tha five (5) criteria that must be met in order to justify a restart of the reactor following a scram. (2.0)
(***** CATEGORY 08 CONTINUFO ON NEXT PAGE *****)
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-QUESTION '8.09 (2:50)-
f'c. .Atswhat' minimum emergency ac't io n l' eve l .. c l' ass i f ic at io n - is . p e rso nne l accountab ility ' required?. _(0.5): ,
.b. 'How soon following classification should accountability.be
^
completed? ( 0. 5 )?
c ~..LWhere do Operations Department personnel ~repor.t to forLaccounta- .
bility? (0.5)
- d. lJho determines which personnel-will remain-in the above location? (0.5):
e.: Where-are_non-essential. operations personnel dispatched to? :(0.5)
QUESTION 8.10' (2.00) -
+
What are two (2) decisions or responsibilities of the Emergency Directorithat'CANNOT BE DELEGATE 0? -
(2.0)-
QUESTION 8.11 (2.00)
The reactor is~ operating at 100% power when a spurious Group I isolation occurs. The reactor scrams. A review of post-scram data indicates that-the initiating signal for the scram was low reactor water level.
Hcs s' Fuel. Cladding Integrity' Safe,ty Limit been' exceeded? EXPLAIN. (2.0) t l
I
(***** CATEGORY 08 CONTINUED ON NEXT PAGE *****)
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4 s ' QUESTION L 8.1'2; ;.(2.00) ,
7
. . m .. . . . . ,
'Given~the;following'cooldown' data, DETERMINE'ifithe RPV cooldown' rate,
~; ' limit'has.been-exceeded.
STATE the cooldown?limitiand HOW your "datermination was-made. 'If the-limit was exceeded,' STATE:the period (s)'.
tof. timethe limit wastexceeded. .-(2.0)_
-TIME- TEMPERATURE ~CDeg-F) s
) k
'0800 ~520 0815 490 0830 460
-0845 445-0900 430'-
0915- ~
400 0930 370
. 0945 340 1000 325 1015 310 1030 275 1045 250 1100 225 1115. 205 A
J F
i
(***** END OF CATEGORY 08 *****)
(************* END OF EXAMINATION ***************)
i NRC LICENSE EXAMINATION HANDOUT EQUATIONS, CONSTANTS, AND CONVERSIONS 6=m*C*deltaT p 4=U*A*deltaT p = po*10sur*(t) p , po.,t/T SUR = 26/T T=1*/p+($-p)/Xp T=1/(p-p) T = ($-p)/Xp P = (Keff-1)/Keff = deltaKeff/Keff p = 1*/TKeff + jerf/(1+1T) .
A = In2/tg = 0.693/tg K = 0.1 seconds-1
~
I = Io*e "*
CR=S/(1-Keff) 2 R/hr = 6*CE/d feet Water. Parameters 1 gallon = 8.345 lbm = 3.87 liters 1 ft3 = 7.48 gallons Density 9 STP = 62.4 lbm/ft3 = 1 gm/cm3 Heat of vaporization = 970 Btu /lbm Heat of fusion = 144 Btu /lbm 1 atmosphere = 14.7 psia = 29.9 inches lig.
Miscellaneous Conversions 1 curie = 3.7 x 101U disintegrations per second 1 kilogram = 2.21 lbm I horsepower = 2 54 x 103 Btu /hr 1 mw = 3.41 x 10b Btu /hr 1 inch = 2.54 centimeters degrees F = 9/5 degrees C + 32 degrees C = 5/9 (degrees F - 32) 1 Stu = 778 ft-lbf
~5t__IBEQBl_QE_NUGLE68_EQWEB_EL6NI_QEEB8Il0Nt_ELu1RHt_8dD PAGE 19 IHEBdQQ1Nad10S ANSWERS -- COOPER -87/02/17-GRAVES, D.
ANSWER 5.01 (2.50)
- c. "3" is the correct answer (0.5). The highest Xenon concentration will be in the center of the core (0.25), which is the high flux region from the previous operating period (0.25). This will increase the flux'in the area of the peripheral control rods (0.25) to increase their worth (0.25).
- b. 1. TRUE (0.5)
- 2. FALSE (0.5)
REFERENCE CNS Reactor Theory, pg 6-12 K/A 292006 Kl.08 ANSWER 5.02 (3.00)
- c. Decrease (0.25). The pressure to the pump suction is a function of the height of the water above the pump suction. Less height means less pressure at the pump suction (0.75).
- c. Decrease (0.25). Raising power raises the flow rate and velocity in the suction line, thus line losses are increased (0.75).
Also accept decrease in subcooling as in part "b" as explanation.
REFERENCE GE HTFF manual, pg 7-93 through 7-96 CNS Heat Transfer and Fluid Flow, pg 6-76 through 81 K/A 293006 Kl.10 ANSWER 5.03 (2.50)
- c. MAPLHGR (0.5 each)
r N-F :5t__IBEQBl_QE_NWGLE88 EQWEB_EL8HI_QEE86I1QNt_ELUIQSt_6NQ PAGE 20.
. IBEBdQQ1Ned1GS-ANSWERS -- COOPER -87/02/17-GRAVES, D.
V REFERENCE GE-. Thermodynamics, Heat? Transfer, and Fluid Flow, Chapter 9,.pgs 100-101 K/A-293009 K1.39, K1.40; K1.41 ,
ANSWER 5.04 (3.00)
- c. Four fuel bundles and a control rod (0.5)'
- b. 25'(0.5)
- c. Fully withdrawn (0.5)
- d. All control rod movements are associated with low reactivity cells (1.0).
- o. True (0.5)
REFERENCE
. Fuel System Description,~pg 18 K292005 K1.10 ANSWER -5.05 (2.00)
- c. The operating limit at rated flow times kf (1.0).
- b. 0.01 higher than comparable two loop values (1.0).
REFERENCE CNS~ Technical Specification 3.11.C. pg 212 K/A293009 K1.23, K1.27 ANSWER 5.06 (3.00) 0.' SOM prior to the outage will be larger (0.5) due to fission product poisoning (0.75) and fuel depletion (0.75).
- b. Compliance ensures that the core can be made subcritical (0.25) in the most reactive condition during the operating cycle (0.25) with the l
strongest control rod withdrawn (0.25) and all other operable control
- rods fully inserted (0.25).
REFERENCi r LOTM-TH-4.11-0, Shutdown Margin, pg 5 CNS Reactor Theory, pg 1-35 and 36 i
L___________________________________..__________-__.-__________._______________________________
i El__IHEQBl_QElNUQLE88_EQWEB EL8NI_QEEB'8110NA_ELVIDSt_8NQ' PAGE -21 ,
cIHEBdQQ1N85103 3' .
' ANSWERS -- COOPER. -87/02/17-GRAVES,'.0.
CNS Technical Specification ~3.3.'A.1
.K/A 292002 K1.10, K1.14 ANSWER 5.07 (1.00)
- 1. .a ;
.2. e
.3.. d
- 4. b
- 5. c 3
~
(0.25 for each manipulation necessary to put the items in the correct
-order)
REFERENCE LOTM-TH-3.2-0, Modes.of Heat Transfer LOTM-TH-3.5-0, Boiling Heat Transfer CNS Heat Transfer and Fluid Flow, pg 8-5 through 8-8 '
K/A 293008 K1.18 ANSWER 5.08 (1.00) b (1.0)
REFERENCE LOTM-TH-2.5-0, 1st Law of Thermodynamics
.! LOTM-TH-2.13-0, Reactor Heat Balance CNS Heat Transfer and Fluid Flow, pg 7-4b through 7-48 K/A 293007 K1.13 P
i i
s ,- _-__- _ _ _ _ _ _-___ _ - _ - ___ __ - __- - ___ -
r7
-Si__IBEQBY_QE_UUCLEeB_EQWEB_EleUI_QEEBoIl0Ni_ELU10ft_oNQ PAGE- 22 (:
IBEBDQQ188 DIGS _
ANSWERS -- COOPER -87/02/17-GRAVES, D.
ANSWER 5.09 (3.00)
Veid fraction decreases (0.5). The void fraction is slightly smaller because the negative effects of doppler are compensated for by the void fraction decrease (0.5).
00ppler reactivity increases (0.5). As power increases, the fuel tcmperature increases. This temperature increase causes doppler to cdd more negative reactivity (0.5).
Enthalpy increases (0.5). The increased reactor power allows more oxtraction steam to be drawn off thus increasing inlet enthalpy (0.5).
REFERENCE LOTM-TH-4.18-1, Void Coefficient LOTM-TH-4.19-1, Doppler Effect LOTM14bO, Feedwater Heaters and Heater Orains CNS Reactor Theory, Chapter 4, Reactivity Coefficients CNS Heat Transfer and Fluid Flow, pgs 5-48 through 5-65 K/A 292008 K1.20 K/A 293002 K1.04 ANSWER 5.10 (1.50)
PERIOD SRM LEVEL
- c. infinite constant
- b. infinite constant
- c. positive increasing (6 at 0.25 each)
REFERENCE c CNS Reactor Theory, pg 7-7, 7-8 %
K/A 202006 K1.03, K1.05, K1.08
e l
'li__IHEQBl_QE_NUGLE88_EQWEB_EL8HI_QEEB8110Nt_ELU101&_8NQ PAGE 22
~
IBEBdQQ1Ned1G1 -
' ANSWERS -- COOPER -87/02/17-GRAVES, D.
ANSWER 5.09 .(3.00)
Void fraction decreases (0.5). The void fraction is slightly smaller because the negative effects of doppler are compensated for by-the void fraction decrease (0.5).
Doppler reactivity increases (0.5). As power' increases, the fuel
.tcmperature increases. This temperature increase causes doppler to cdd more negative reactivity (0.5).
Enthalpy increases (0.5). The increased reactor power allows more extraction steam to be drawn off thus increasing inlet enthalpy (0.5).
REFERENCE LOTM-TH-4.18-1, Void Coefficient LOTM-TH-4.19-1, Doppler Effect LOTM14b0, Feedwater Heaters and Heater Drains
'CNS Reactor Theory, Chapter 4, Reactivity Coefficients CNS Heat Transfer and Fluid Flow, pgs 5-48 through 5-65 K/A 292008 K1.20 K/A 293002 K1.04 ANSWER 5.10 (1.50)
PERIOD $RM LEVEL
- o. infinite constant
- b. infinite constant
- c. positive increasing (6 at 0.25 each)
REFERENCE CNS Reactor Theory, pg 7-7, 7-8 K/A 292008 K1.03, K1.05, K1.08
li__IBEQBl_QE_NUQLE88_EQWEB_EL8NI_QEEB8110Nt_ELulDst_88Q PAGE 23 IBEBdQQ188d103 ANSWERS -- COOPER -87/02/17-GRAVES, D.
ANSWER 5.11 (2.50)
- c. Equal to (0.5)
- b. 1. Delayed neutrons are born at lower energies than prompt neutrons and are less likely to be lost while slowing down (1.0). Therefore delayed neutrons make up a greater fraction of the total neutron population.
- 2. Since they are born at lower energies, they are less likely to cause fast fission (1.0), which accounts for a significant portion of the power production.
REFERENCE
-CNS Resotor Theory, pg 3-30 K/A 202003, K1.04
r f
r [t__EL8HI_SYSIEbS_QE1106t_GQUIBQL&_8NQ_INSIBubENI8IIQU PAGE 24 ANSWERS -- COOPER -87/02/17-GRAVES, D.
ANSWER 6.01 (2.00)
Replacement of the water in the reference leg will cause it to get hotter.
This causes the density to decrease (1.0). The decrease in density ocuses a decreased dp, which results in an increased level indication (1.0)
REFERENCE CNS Nuclear Boiler Instrumentation, pg N01-22 K/A 216000 A2.03 ANSWER 6.02 (3.00)
- c. scram
- b. both
- c. scram
- d. neither
- o. neither
- f. rod block (0.5 each)
REFERENCE APRM, og APRM-7, 10 RPS, pg RPS-15 K/A 212000 K1.01, K1.03 M1.05, K1.13, K1.14 ANSWER 6.03 (2.00)
If the upstream valve failed to reposition, the downstream valve repositioning will vent the header (1.0). If the downstream volve failed to reposition, a check valve around the valve will bypass the failed volve to vent through th operable upstream valve (1.0).
REFERENCE Control Rod Drive Hydraulics, pg 10, Figure 4 K/A 201001 K 4.04
re ht__EL8NI_SISIEDS_QESIGNt_QQUIBQL&_8NQ_INSIBudENI8IIQN PAGE 25 ANSWERS -- COOPER -87/02/17-GRAVES, D.
ANSWER 6.04 (3.00)
- c. The turbine will not start (0.5) because the governor and stop valven require oil pressure to open (0.5) which is normally supplied by the auxiliary oil pump.
- b. ,This would cause an increase in turbine speed (0.5).and would result ,
in a turbine trip (0.5).
- c. The flow controller can be taken to manual (1.0).
REFERENCE HPCI, pg HPCI-31, 33 ,,
K/A 206000 K4.11, K4.14, KS.05 ANSWER 6.05 (2.00)
- a. RPIS card pulled (0.5)
Internal logic malfunction (0.5)
- b. Control rod insertion will continue (0.5) but movement with other control rods will be prevented (0.5).
REFERENCE Roactor Manual Control System / Rod Position Information System, pg RMC-8, 15 K/A214000 K3.03 ANSWER 6.06 (3.00)
- c. - steam header pressure (0.25)
- pressure setpoint (0.25)
- bien signal (0.25) on one channel (0.25)
- b. None (1.0)
REFERENCE Turbine High Preneuro Fluid, pg EH-12, Rev 1 DEH, pg DEH-4, 29, Rev 1 Design Change 86-112 K/A 245000 K1.00, KO.00, K6.02, K6.06
hs _EL8NI_SISIEdS_DESIQNt-QQUIBQLt_8ND_INSIBudENI8IIQN PAGE 26 ANSWERS -- COOPER -87/02/17-GRAVES, D.
ANSWER 6.07 (2.50)
- o. By the use of the Dahl controller in manual (1.0),
- b. The feed pump discharge valves shut (0.5) and the startup flow control isolation valves open (0.5). The Startup Flow Controller, which is normally left in automatic, will attempt to control vessel level (0.5)
REFERENCE Fcedwater Control System, pg FCS-8, 10, 23 K/A 250002 K4.06, K4.08, A1.05 ANSWER 6.08 (2.50)
- c. - Service water effluent
- REC
- Radweste effluent (3 at 0.33 each)
- b. None (0.5) Accept alarm.
- c. The off gas timer would be initiated (0.5). After a delay of approximately 15 minutes, the off gas system isolates (0.5).
REFERENCE Rcdiation Monitoring Systems, pg RMS-8, 25, 26 K/A 272000 K1.12, K1.21, K3.05, K4.03 ANSWER 6.09 (2.50)
The critical buses are normally supplied from the station service transformer. A main generator trip will cause a loss of the station corvice transformer. If the start-up transformer remains energized, it l cill pick up the station loads. If it is not available, and the
- crergency transformer is available, it will pick up the critical
! buses. If it is not available, the E00 will pick up the buses.
(4 sources at 0.25 each, 1.5 for the order of priority, with each acnipulation to put them in the correct order worth 0.5) l l
REFERENCE AC Electrical Distribution, pg AC-33, 34 l
K/A 262001 K1.01, K3.02, K4.06, K6.03
- ht__ELANI SISIEdS_QESlQUt-QQUIBQLt_66Q_IUSIBudEUI81100 PAGE 27 ANSWERS -- COOPER -87/02/17-GRAVES, D.
ANSWER- 6.10 (2.50)
- o. If the field breaker is not shut within 15 seconds after the pump sequence is started (1.0).
- b. The recirc MG drive motor breaker trips (0.5).
- c. The recirc pumps trip (0.25) on high reactor pressure of 1120 psig (0.25). The recirc pumps discharge valves shut (0.25) if a LPCI initiation signal is present (0.125) and reactor pressure decreases to between 185 and 235 psig (0.125).
REFERENCE R0 circulation System, pg RECIRC-10, 27, 31, Table 1 K/A 202001 K1.12, K1.27, K4.07, K4.14, K6.06 L __ _ _ __ _ _ _ _. _
P Zx__EBQQEQuBER_ _NQBd8Lt_eBUQBdekt_EdEBQENQ1_8ND PAGE 28 88DIQLQQIQeL_QQUIBQL ANSWERS -- COOPER -87/02/17-GRAVES, D.
ANSWER 7.01 (2.50)
- c. The 3 GEMAC's and associated recorder on panel 9-5 (1.0).
, b. The Yarways may be monitored locally in the Reactor Building (0.5).
- c. The reactor vessel level reference legs will begin to flesh when the RPV pressure approaches saturation pressure for the drywell temperature, causing erroneous high reactor level indication (1.0).
REFERENCC CNS E0P 5.2.5.1, Loss of All Site AC Power Station Blackout, Rev 3, pg 3 K/A 216000 A2.06, System Generic 1 APE 295003 AA2.02 ANSWER 7.02 (2.00)
- c. True
- b. Falso
- c. False
- d. Truo (0.5 each)
REFERENCE 00P 2.1.15, Reactor Recirculation Pump Startup and Shutdown, Rev 18, pg 2 CNS Technical Specifications 3.3.F.
K/A 202001 System Generic 5 ANSWER 7.03 (3.00)
- c. None (0.5)
- c. E0P-3 (0.5)
- d. E0P-2 (0.5)
- o. E0P-1 (0,5)
- f. None (0.5)
REFERENCE Emergency Procedure 5.0, E0P/C, Rev 1, pg i System Wide Generic for Emergency and Abnormal Plant Evolutions, SG11
v
' Zi__EBQGEQuBES_:_NQBd8Lt_eRUQBdakt EdEBQENGl_eND PAGE 29 88010LQQIG8L GQUIBQL ANSWERS -- COOPER -87/02/17-GRAVES, O.
l ANSWER 7.04 (2.50) i
- c. Initiation during surveillantu testing OR due to accider.tal depressurization of the-instrument racks-(either at 1.03 l
- b. - Verify if HPCI is needed (0.5)
- Depress turbine trip pushbutton and hold (0.5)
- Lockout Auxiliary oil pump when the turbine is stopped (0.5)
REFERENCE AP 2.4.4.1, Inadvertent Initiation of CSCS, Rev 6 K/A 206000 A2.17 ANSWER 7.05 (1.50)
- c. 3
- b. 5 c.- 6
- d. 1
)
- o. 4 '
- f. 2 (0.25 each)
REFERENCE ;
EP 5.2.1, Shutdown from Outside the Control Room, Rev 13, pg i l APE 295016 AK2.02 l
ANSWER 7.06 (2.50)
- o. - Radiation exposure rates > 100 mrem /hr I
- Airborne radioactivity concentrations >3X 10 E-9 uCi beta /gamme except when isotopic analysis proves these concentrations < 25%
of the amounts specified in 1CCFR20.
- General contamination levels > 2200dpm/100 cm2
- Work involving industrial safety conditions which may be immediately hazardous to life. l (3 required at 0.5 each)
- b. 1 month (0.5)
- c. True (0.5) l l
l l
Zt__EBQQEQUBE1_:_NQBd6Lt_8HNQBdekt_EdEBQEUQ1_8NQ PAGE 30 B&QIQLQQIQ8L_QQNIBQL ANSWERS -- COOPER -87/02/17-ORAVES, D.
REFERENCE CNS HPP 9.1.1.4, Rev 15, pg 4, 5 Plant Wide Generics 294001 K1.03 ANSWER 7.07 (3.00)
- c. Shift Supervisor (0.5) or Control Room Supervisor (0.5)
- b. All steps within a given section must be completed before going on to the next section (0.5).
- c. - Licensed operator
- Reactor Engineering representative
- STA qualified individual (0.5 each)
REFERENCE CNS 00P 2.1.1, Cold Startup, Rev 45, pg 3 Plant Wide Generica 294001 A1.02, A1.11 ANSWER 7.08 (2.00)
Pcwer is raised at a slow, controlled (preconditioning) rate (0.5) and hold at a desired power level to soak for a specified period of time (0.5).
This allows operation with minimal constraint up to the preconditioned pcwer level (0.5). Preconditioning reduces fuel pellet-clad inter-sction (0.5), reducing the possibility of breaches in the fuel cladding.
REFERENCE CNS GOP 2.1.19, Nuclear Fuel Preconditioning, Rev 6, pg 1, 2 K/A 293009 K1.36, K1.37 ANSWER 7.09 (1.00)
Filling the RWCU domineralizers with borated water and injecting this via the RWCU synt.em (1.0).
REFERENCE Emergency Procedure 5.2.14, Alternate Means to Inject Doron to RPV, Rev 0 EFE 295037 EK2.13 l
w E
- ZA__fBQGEQMBES =_NQBd6Li_8BNQBd8L&_EMEBGENGl_aNQ- .PAGE '31
. 84Q10LQGIG8L GQNIBQL.
- ANSWERS -- C00PERL -87/02/17-GRAVES, D.- ,
L l:
, s ANSWER 7.10 '(1.00)
L b is the desired method of operation (0.5). Operation continuously at
! Icw pressure shortens'the seal: life (0.5). ,
REFERENCE ~
CNS Procedure 2.2.68, Recirculation System, Rev 25, pg 15 K/A.202001 System Generio 10 ANSWER 7.11 (2.00)
--Flood water exceeds 8" (1.0)
- If all station air compressors are. lost (1.0)
REFERENCE EP 5.3.10, Control Building Basement Flooding, Rev 5, pg 2 APE 295006 SG11 1 i
ANSWER 7.12 (2.00)
O. - Air pressure drops low enough to cause more than one control rod to insert
- Air pressure. decreases to 50 psig
- If the loss of air causes unsafe plant operating conditions ,
(0.33 each) !
- b. - Run both recirculation pumps back to minimum speed (0.5).
Transfer station service (0.5).
l-l REFERENCE ;
00P 2.1.5, Emergency Shutdown from Power, Rev 8, pg 2
! EP 5.2.8, Loss of Instrument Air, Rev 11, pg 2 !
APE 295006 AA1.04, S011 l
r~
At__6DdINISIB6IIVE_EBQQEQUBESt_QQNQlIl0Nat_8NQ_ lid 1I8I1QN2 PAGE 32 ANSWERS -- COOPER -87/02/17-GRAVES, D.
ANSWER 8.01 (1.50)
- Operating license (0.5)
- Technical Specifications (0.5)
- Approved operating procedures (0.5) -
REFERENCE CNS procedure 0.2, Introduction to CNS Operations Manual, Rev 3, pg 3 Plant Wide Generics System Generic 1 ANSWER 8.02 (2.00)
- c. - When the reactor is in the Startup Mode (0.5)
- Ouring all reactor operations (0.5) OR. any time the reactor is not in cold shutdown.
- During special tests as directed by tho DMNO (0.5)
- b. 10 minutes (0.5)
REFERENCE CNS procedure 0.2, Introduction to CNS Operations Manual, Rev 3, pg 7 Plant Wide Generics A1.03 System Generic 1 (all systems)
ANSWER 0.03 (1.50)
- c. 2 individuals holding SRO licenses (0.5)
- b. The intent of the procedure is not changed (0.5)
- c. yes (0.5)
REFERENCE CNS Technical Specifications, pg 227 CNS Procedure 0.4, Rev 7, pg 6 Plant Wide Generics
1 at__6Dd1N11IBoIIVE_EBQQEQUEElt_QQUQ1Il0H1t_68Q_ Lid 11eI1QN1 PAGE 33 ANSWERS -- COOPER -87/02/17-GRAVES, D.
ANSWER 8.04 (2.50)
Sulfuric acid
- Sodium Hydroxide
- Mercury
- Boron compounds
- Sodium hypochlorite
- High pressure gas cylinders (oxygen, nitrogen, argon, helium, air) accept any of the individual gases as satisfying the single cylinder answer.
(5 required at 0.5 each)
REFERENCE CNS Procedure 0.7, Hazardous Material Control, Rev 1,
. Plant Wide Generica 294001 Safety knowledge ANSWER 8.05 (3.00)
- c. - The system configuration is specified by a controlling document (1.0)
- Operation of the equipment or system components would not represent a hazard to personnel performing the procedure (1.0)
- b. Clearance Order is primarily concerned with personnel safety (0.5),
while the Caution Tag Order is primarily concerned with equipment operation (0.5).
REFERENCE CNS Procedure 0.9, Equipment Clearance and Release Orders, Rev 4, pg 1, 2 Plant Wide Generic K/A 294001 K1.02 ANSWER 8.06 (2.00)
- There are no unexplained discrepancies (1.0)
- All values are within the Technical Specification requirements (1.0)
REFERENCE CNS Procedure 0.26, Surveillance Program, Rev 1, pg 3, 6 System Wide Generics $02, S03, S011
At__eQUIN11IBoI1YE_EBQQEQRBEHt_QQNQ1I1QNS&_6NQ_LIMIIeI1QN3 PAGE 34 ANSWERS -- COOPER -87/02/17-GRAVES, C.
ANSWER 8.07 (2.00)
- c. DMNO (0.5) or designee
- b. DMNO (0.5) or designee G. Any licensed operator (0.5) when, in his j udgement, continued operation would jeopardize station saf ety (0.5).
REFERENCE '
CNS Procedure 2.0.1, Operations Department Policy, Rev 2, pg 1 System Generic #1 Plant Wide Generic K1.16 ANSWER 8.08 (2.00)
- The plant is in a safe condition
- The cause of the scram is understood or it is attributed to a spurious trip and is unlikely to reoccur
- Corrective action has been identified and appropriately implemented
- Proper automatic operation of plant safety related systems has been observed
- The DMNO approves the restart (or designee)
(4 of 5 required at 0.5 each)
REFERENCE CNS Procedure 2.0.6, Reactor Post-Trip Review and Restart Authorization Procedure, Rev 3, pg 6-7 Plant Wide Generics (General)
ANSWER 8.09 (2.50) ,
- c. Alert (0.5)
- b. 30 minutes (0,5)
- c. Control Room (0.5)
- d. Shift Supervisor (0.5)
- o. Electrical /I a C OSC (0,5)
l Ai__8DdIU11188IIVE_EBQQEQUBEft_QQUDIIIQNit_8ND_LidII6IIQN3 PAGE 35 ANSWERS.-- COOPER- -87/02/17-GRAVES, D.
REFERENCE CNS EPIP 5.7.10, Personnel Assembly and Accountability, Rev 7, pg 2 Plant Wide Generic A1.16 ANSWER 8.10 (2.00)
- Notification of off-site agencies (1.0)
- Recommendation'of protective actions (1.0)
REFERENCE
-CNS EPIP 5.7.28, Emergency Director, Rev 2, pg 1 of Attachment A CNS EPIP 5.7.2-5 -
Plant Wide Generics A1.16 ANSWER 8.11 (2.00)
Ycs (0.5). A closure of three or more main steam lines should i.itiate o reactor scram due to flSIV position (0.5). The safety limit is assumed to be exceeded whenever the scram does not occur due to its expected ceram signal (1.0).
REFERENCE CNS Technical Specification 1.1.C, pg 6
-System Wide Generic Statemente for Emergency and Abnormal Evolutions #3 ANSWER 8.12 (2.00)
The cooldown rate limit is < or = 100 deg F (0.25) when averaged over o one hour period (0.25). The limit was exceeded for three one hour poriods: 0845 - 0945 (105 deg F), 0900 - 1000 (105 deg F), and 1015 - 1115 (105 deg F). (3 periods at 0.5 each)
REFERENCE CNS Technical Specification 3.6.A.1, pg 132 K/A 290002 System Generics 5, 11
y .-
< V, Question Number' / Comment-
'1.03 Answer given is~ going to depend on whether the candidate; assumed that power given in the' question was sufficient to cause.significant burnout. If the candidate assumed that burnout' would occur then answer "a" would be acceptable.
If the candidate assumed that the'given power a was not-sufficient to:cause' burnout then the answer "b" is acceptable..
Recommendation: Accept either' answer "a" or'"b"
Reference:
Reactor Physics.page 6-9.
1.09 Procedure 2.1.1, Cold Startup Procedure, states that-the Banked Position Withdrawal Method for groups 3 and 4 (1 and 2 if 3 and 4 are' withdrawn first) is used to' avoid fast' period scrams. It
-does not specify that requirement of groups 1:
and 2 are fully withdrawn first. It also does not. discuss RSCS avoiding high notch worths.
Recommendation: Allow stating that Banked Rod Withdrawal Method is used with groups 3 and 4 (or 1 and 2 if 3 and 4 are withdrawn ~first) to avoid high notch worths.
Reference:
General Operating Procedure 2.1.1, page 4.
1.11 ECPs are not conducted at CNS and should not be referred to in examinations.
1.12 Core dp will not show natural circulation flow.
It only indicates minimal dp when recirc pumps are operating at minimum flow. Flow would also be indicated on the total core flow indication because it is driven by jet pump flow.
Monitoring of vessel temperatures will also indicate if natural circulation does not exist.
Recommendation: Accept total core flow indication and vessel metal temperature indication as indications that natural circulation exists.
Reference:
Heat Transfer and Fluid Flow student text page 8-56.
1.13 Total value is 1.0 pts yet answer key has a value of .5 pts for each answer for four answers.
k m,
~
2.01 LTheLbackup. scram valves are located between the' air: filters and the scram pilot air header.
-Recommendation:' Allow location as between the air filters and the scram pilot air header as an
~
acceptable answer for location of the valves..
Reference:
CRDH Student text page-19..
2.02.a If the RCIC oil pump fails after oil pressure
'has built up then-the trip throttle valve will close <nt decreasing oil pressure. - The question does not specify whether sufficient pressure has been built up enough'to_ pressurize.the oilf cylinder on the trip throttle valve or not.
- Recommendation: Accept either the~ turbine trips on low oil pressure or' trips on over speed.
Reference:
RCIC student text.page 11.
2.05 Point value given for the question'is'2.5 pts, however, the values ~given for the various parts of the answer add up to 3.0 points.
2.06.b The source of 120 V AC to the~ solenoids is RPS.
Recommendation: Allow RPS as an answer for the AC source of power to the solenoids.
~
Reference:
Main Steam Student Text page 9.
2.08.a- The RFP High Pressure Stop Valve above seat
~
drain opens on a turbine trip. A~recent Design Change shifts the Main Steam.Line Drains from the A5'and B5 heaters to the Main Condensor on a Turbine Trip.
Recommendation: Accept RFP High Pressure Stop Valve Above Seat Drains opening and MSL Drains shift as acceptable answers.
References:
Main Generator and Auxiliaries Student Handout Figure 10. System Operating Procedure 2.2.28 page 2. Design Change 86-101.
2.08.b Question is ambiguous. A number of protective devices send signals to the solenoid valve to protect the turbine generator.
Recommendation: Accept any turbine generator trip signal.
References:
Main Generator Student Text page
- 25. Main Turbine Student Text page 18 and 19.
r-2.09 and 6.09 on a turbine trip the generator will trip. On a' generator trip the Normal Station Service Transformer is lost. ;It is not"a possible source of power following a turbine trip.
Recommendation: RDo not require normal station service transformer as a required answer. Only three sources are available: _Startup Transformer, Emergency Transformer, and the Diese1' Generators.
Reference:
AC Distribution Student Text pages 33 and 34. ' Main Generator Student Text page 25.
2.10.a The valves that intertie between RHR service water and RHR are sealed closed. They are listed on the sealed valve list. The seals indicate that the valves should not be operated without Shift Supervisor apprcval. Candidates may interchangeably use sealed and locked.
Recommendation: Also accept sealed closed valves as an answer.
Reference:
Conduct of Operations Procedure 2.02 3.01.b The NBI student text states that the Fuel Zone Yarways are useless when the recirculation pumps are running. It does not specify the difference in indication between high flow and low flow.
Recommendation: Accept either the indication is useless or is pegged high.
Reference:
NBI Student Text page 5 and 21, 3.04.b A rod block will occur when the first withdrawal error occurs so it can be interpreted that the rod worth minimizer allows zero withdrawal errors.
Recommendation: Accept 0 withdrawal errors and 2 insert errors if the candidate explains that the RWM causes blocks on the first withdrawal t error and third insert error.
l I
3.05.b and 6.05.b If a RPIS inop select block occurs during rod movement then the rod will not be deselected.
until the rod is stopped. .The training material implies in one portion that a select block will-stop. motion during emergency in.
Recommendation: Due to the confusion of the training material accept either the rod will stop or the rod will continue to insert and rod movement with other-rods will be prevented.
Reference:
RMCS/RPIS Student Text page 8 and page 17.
.3.06.b and 6.06.b The Load Drop Anticipation function was removed by design change 86-112. This was just completed during the last outage.
Recommendation: Accept none for part b.
Reference:
Design Change 86-112.
3.09 a and c A Group II isolation is caused by a high drywell '
signal or a 12.5" reactor level.
Recommendation: Accept 1 (High DW Pressure) and 3 (12.5" Reactor Level) for signals that operate the Reactor building ventilation valves. Accept 6 (Group II) as a signal that operates RHR Shutdown Cooling Valves.
Reference:
Containment Student Text Table 2 4.04.a If the Control Room is evacuated to do a fire then the personnel assignments are different from assignments required for other control: room evacuations.
Recommendation: Accept Alternate Shutdown Panel.
Reference:
Emergency Procedure 5.4.3.2 4.09 A rod drift alarm will occur on an overtravel-condition.
Recommendation: Accept rod drive alarm as a
'A possible answer.
Reference:
Instrument Procedure 4.3 page 12.
s N
- e 5.7 ' Point value given for the. question is:1. point yet it requires 5 answers at .25 points each.-
6.10.c Point _value'given-for the question is l' point
.but the values given for the various parts of-the answer add up to'I.5 points.
7.06 b and c Due to the vagueness of Procedure 9.1.1.4 the answer to this question'may vary. _The administrative limitation section states that "a SWP may be in'effect'for a. total of one (1)
~
month and seven days, if work requires this SWP to-be extended, a new SWP must be issued".-
Under Section.VI.B.3 the procedure implies that ,
a SWP can be written with an expiration date of one month and seven days and the note says this can be extended for an additional seven days.
Recommendation: Accept either one month or one month plus seven days for part b.
Reference:
Health Physics Procedure 9.1.1.4' page 4 and 5.
-8.2.a This question asks _for three conditions requiring the STA position to be manned. The three answers in the answer key are correct, but CNS procedure 0.21-states a STA should be manned whenever the reactor is not in'a cold shutdown condition.
Recommendation: Also accept any time the reactor is not in cold shutdown condition.
Reference:
CNS Procedure 0.21, page 1.
8.9.c Emergency Plan Implementing Procedure 5.7.10-specifies that all On-site Operations personnel report to the control room. Operations personnel in training do not report to the control room.
Recommendation: Accept that Operations personnel in training do not have to report to the control room.
Reference:
EPIP 5.7.10
.