ML20215G452
| ML20215G452 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 06/11/1987 |
| From: | Cooley R, Graves D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20215G426 | List: |
| References | |
| 50-458-OL-87-02, 50-458-OL-87-2, NUDOCS 8706230263 | |
| Download: ML20215G452 (85) | |
Text
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- RBS-EXAMINATION REPORT No. 50-458/0L-87-02 Facility Licensee: Gu'lf. States Utilities-P. O. Box 2951-Beaumont, TX 77704
-_ Facility' Docket No.: '50-458 Facility License No'.: 'NPF Operator Licensing examinations administered at' River Bend Station ( ABS)
~ Chief Examiner:' // 6/yAo Day"1d. N. . Graves . Date' Approved By: A -
[ Ralph A. Cooley,Cnief, Operator Da'te Liceasing Section v Summary: .- -
~
Examinations were administered.to three Reactor Operator candidates and two Senior Reactor Operator candidates. One Senior Reactor Operator and two
~
Reactor Operator candidates passed.. 8706230263 870612 PDR ADDCK 05000458 V PDR 4
2' DETAILS 1 1.- ' Examination Results One. Reactor Operator candidate and two Senior Reactor Operator. candidates were administered written, simulator, and. oral operating examinations. One Reactor 0perator candidate was administered a. simulator examination only, and one Reactor Operator candidate was administered a" written examination (Section3)only. One Senior Reactor.0perator candidate and.the two Reactor Operator candidates taking partial examinations passed.
- 2. Examiners D. N. Graves, NRC Chief Examiner R. K. Miller, Sonalysts, Inc.
- 3. Examination Report Performance results for individual candidates'are not included in this report. This report is comprised of the sections listed below:
- a. Written Examination Review Comment' Resolution A copy of the facility's review comments is attached. All of the comments were accepted and incorporated into the examination answer key. This.resulted in. reducing the number of available points in Section 3 of the Reactor Operator examination from 25 to 23.
- b. ' Exit Meeting Summary-A brief exit meeting was held on May 28, 1987, to conclude the site visit. The following personnel were in present:
NRC Licensee D. N. Graves, Examiner C. A. Rohrmann R. K. Miller, Examiner R. Jackson The following observations were made to the licensee: (1) Escorted access into and out of the facility was handled smoothly. Some concern had been expressed over the time consumed gaining access during previous site visits.
r: e I 3: l(2) The Senior Reactor Candidates were considered weak on refueling procedures and knowledge of fuel handling equipment operation.. . (3) The_ simulator. performed well during the examinations. (4) The simulator operator and the instructor filling in as'the third operator on each. examination crew did an excellent. job. c.. Examination Master Copies Copies of the Reactor Operator and Senior Reactor Operator examinations and answer keys are attached. The Section 3 written examination is not included as.a separate examination. It is
' identical to the Section 3 in the complete Reactor Operator examination.
l a EXAMINATION REVIEW COMMENTS RO: 2.02b SRO: 6.01b Request the first part of the answer be changed to read: NRIIX outlet temp. or clean-up demin inlet temp. The reference LOTM-6-1 is incorrect and being revised. Included as reference for the change request is SOP-0090, Rev. 3. In the Precaution and Limitations section, Item 2.2, reference is given to the most limiting parameter during system operation.
Reference:
SOP-0090, Rev. 3, page 2 TMDR No. LOTM-87-042 RO: 2.05 b, d, e The answer to the first part of section b is incorrect per reference material The answer should be 5, not 4 as indicated. Request the second part of sections d and e answer be changed to 7 rather than
- 8. The bases for this change is incorrect reference materialin LOTM-15b-0 which shows these pressures in PSIA rather than PSIG as all other pressures are indicated. New revision is correct.
Reference:
LOTM-15b-1, page 27 1
RO: 2.06b Request that another answer be considered fully correct for the second part (why) portion of this question based on question wording. Another fully exceptable answer is as follows: "due to the loss of one of the two required permissives for the valve to remain open."
Reference:
Same as answer key RO: 3.02c Request that portion e of this question be deleted based on the fact that no bypass function exists at River Bend for flow un!t inputs to APRMs. The new revision, LOTM-IC-4-1, has no reference to the bypass function,
Reference:
LOTM-IC-4-1, page 11 RO: 3.05c SRO: 6.09c Request the answer be changed to read 8 not 20. Material references in previous revision was incorrect, new revision includes correct material.
Reference:
LOTM-IC-7-1, pages 36 and 53 RO: 3.07 Request that the second item in the answer be deleted based on the fact the interlock does not exist at River Bend. The reactor recire pump discharge valves are not interlocked open. The new revision to LOTM-IC-8-1 has deleted any reference to the interlock. 4
Reference:
LOTM-IC-8-1, pages 18 - 19 1 1
\
2
r i RO: 3.09 Request the high level 5th or 6th point heater be added as an exceptable answer to list of answers. New revision incorporates runback in text material also.
Reference:
LOTM-IC-9-0, Fig. 26-27, pages 114-115 LOTM-IC-9-1, page 79 RO: 3.11a Request that the portion about control system being in automatic be deleted from the answer in part a. The feature will activate regardless of the mode of the control system.
Reference:
LOTM-IC-10-0, page 18 GE drawing,351E 506 SRO: 8.08 Examiner requested material for answer key.
Reference:
EOP-0002-5, page 21 I l 1 t l l 1 j i t
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4 .0, 7 ) 4 v' l a i I U. S.-! NUCLEAR REGULATORY COMMISSION 4 REACTOR 0PERATOR LICENSE' EXAMINATION E FACILITY: _BlVEB_ REND _1____________.
' REACT,0R TYPE: _HWB-qed _________________
,DATE ADMINISTERE.D:_HZ4Q542k________________-
P
~ EXAMINER: ._QB6MEki_QA______________
y , CANDIDATE: _____________________L__._ 183I89011081 10_QaNDIQ8IEiD'
.Usel. separate paper;for the answers. ~ Write'.answersHonJone side only.
-Staple ~ question. sheet .on top of?the_ answer sheets. Points.for"each
.y ;questionf ere ' indicated ' in_ parentheses af ter ' the; question. _..; Thel ~ passing-grade: requires at-least;70%:in each_ category andTa final ' grade offat i
least.80%.; Examination. papers will-be'pi'cked~ up-six (6) hours after.
?the examination starts.
'I 0F
~ CATEGORY 1% OF -CANDIDATE'S CATEGORY
.__VoLME_ 1016L- ___SGQBE___, _ vel 9E__ ______________C6IESQBX_____________
'_25600__ _2520i ,___________ ________'1. PRINCIPLES OF~ NUCLEAR POWER PLANT OPERATION,_ THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW:
_2EAQQ _ ~25xW1 ___________ ________'2. PLANT DESIGN I'NCLUDING SAFET.Y g
'AND EMERGENCY SYSTE.MS
- l. .
L ; 2310D__._21100 . ________ 3. INSTRUMENTS'AND CONTROLS'
._25 AQQ__ _25t@)_ ___________ ________ 4. PROCEDURES - NORMAL, ABNORMA'L, EMERGENCY AND' RADIOLOGICAL, CONTROL L _ 2H200__ ___________ ________* TotsIs l: Final Grade
\;
'All work done on this examination is my own. I have neither given nor received aid.
- i. .!
L
- r. ___________________________________
l- Candidate's Signature o
1 NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS 1 During the administration of this examination the following rules apply: l l
- 1. Cheating on the examination means an automatic ~ denial of your application !
and could result in more severe penalties, j i
- 2. Restroom trips are to be limited and only one candidate at a time'may j leave. You must= avoid all contacts with anyoue.outside the examination !
room to avoid even the appearance or possibility of cheating. j l
- 3. Use black' ink or dark pencil 2D1y to facilitate legible reproductions. ]
1
- 4. Print your name in the blank provided on the cover sheet of the j examination. ]
- 5. Fill in the date on the cover sheet of the examination (if'necessary).
l
- 6. Use only the paper.provided for answers. '
~
- 7. Print your name in the upper right-hand corner of the first page of ga2h section of the answer sheet.- ,
t
- 8. ' Consecutively number each answer sheet,fwrite "End of Category __" as
. appropriate, start each category on a Dgw page, write gDlY 2D 2Dg sidg of the peper, and write "Last Page" on the last answer sheet. l l
- g. Number each answer as to category and number, for example, 1.4, 6.3.. i
- 10. Skip at'least ihrgg lines between each answer.
- 11. Separate answer,aheets 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 111graigrg.
- 13. The point value for each questiors is indicated in parentheses after the question and can be used as a guide for the depth of answer required.
- 14. Show all ca'1culations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or not.
- 15. Partial credit may ba 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, stk questions of the gggm1Dgn'only. !
- 17. You must sign the statement on the cover sheet that indicates that the work is your own and you have not received or been given assistance in completing the examination. This must be done after the examination has been completed.
)
'k 18.'When you complete your examination, you shall:
- a. Assemble your examination as follows:
(1) Exam questions on top. (2) Exam sids - figures, tables, etc. (3) Answer pages including figures which are part of the answer. I'
- b. Turn in your copy of the examination and all pages used to answer the examination questions,
- c. Turn in all scrap paper and the balance of the paper that you did q not use for answering the questions.
- d. 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, yout' License may be denied or revoked. 4 1 J 1 1 l l
--e , .
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14__E$1NDIELES_DE_ NUCLE 68EQWEB_EL6NI_QEEB8IIQN- t PAGE 2 IBEBUQDYNeUIQSt_BE6I_IB6NSEEB_6ND_ELUIQ_ELQW _ QUESTION 1.01 (1 '50) The' reactor is'taken to CRITICALITY from a cold condition and an 80 second POSITIVE period'is attained: l
- a. From control room' nuclear instrumentation,,how can the
~
i operator tellLwhen_the' heating range has been reached? (Rod' position and' recirculation flow are held constant)- L ( 0. 5 )'
- b. 'In which of:the following intervals was the heating range ;
entered? (1,0) s '(1)' Interval 1 - reactor, power increased by a factor ~of 6 in 143.3. seconds.-
.(2) Interval 2 - reactor power increased by a' factor of g 3 in 99.0 seconds !
(3) Interval 3- reactor power increased by a factor of 5 in 128.8 seconds. , f QUESTION 1.02 (3.00) Match each of the items in column i to the short definitions in column 27 (3.0) COLUMN 1 COLUMN 2
- s. fast neutrons 1. high energy neutrons (>1.0 MeV)
- b. activity 2. occur indirectly from fission through fission
- c. delayed neutrons fragment daughter decay
- d. reactivity 3. fractional change in neutron ,
population per generation l
- e. slow neutrons
- 4. occur directly from the
- f. prompt neutrons fission reaction
- 5. Iow energy neutrons (<0.63 eV) l
- 6. number of disintegrations per unit time of a radioisotope
(***** CATEGORY 01 CONTINUED ON NEXT PAGE *****)
le.__EBINCIELES_9E_NVGLE68_E9 WEB _EL6NI_DEEB6IIQNt PAGE 3 IBEBb90XNedlCSt_UE6I_IB6NSEEB_6ND_ELUID_ELQW QUESTION - 1. 0 3 ' (3J00) For each of.the events below,' state the. order in which the three reactivity coeffic'ients will respond (first, second, and third). . ALSO indicate. whether each coefficient-will be adding + or - reactivity during the event. Use all three coefficients for each event. (3.0)
- n. . Rod drop at power
- b. Turbine stop valve fails shut,at power
- c. One recire pump trips at power l
QUESTION 1.04 (2.00)- Indicate whether each of the following are TRUE or FALSE: (2.0)
- c. From BOL to EOL,-the axial flux peak in the core moves toward the l top due.to xenon production near the core center,
- b. Differential control rod worth is higher near the bottom of the core than it is near :the top. j
- c. The total control rod worth of the core can be determined very closely by adding.the worth of each individual control rod.
- d. The total worth of all control rods remains approximately the same throughout core life (80L to EOL).
QUESTION 1.05 (1.50) Indicate whether Samarium or Xenon will be making the largest negative reactivity contribution under each of the following conditions: (1.5) 1
- a. . 50% power, 2 days after startup following refueling
- b. 6 hours after the reactor is shutdown from 100% power
- c. 2. days after the reactor is shutdown from 100% power
) i (***** CATEGORY 01 CONTINUED ON NEXT PAGE *****) 1
It__EBIUCIELgS_DE NVGLE68_EDWEB_EleNI_9EEBoIIQNt PAGE 4 IUEBb9DXNeb1GHt_BEeI_IBeBSEEB_6ND._fLVID_EL9W j QUESTION 1.06 (3.00)
- a. Describe, including values, how the BETA of.the core can be approximately 0.007 at BOL when no fuel isotope has a BETA of that value.. . (1.0)
- b. Describe, including values, how the BETA of the core changes from BOL to EOL. ALSO include how the. fuel composition changes. (1.0)
- c. HOW is reactor control ef f ected by this change in fuel makeup and corresponding BETA change? (1.0)
( QUESTION 1.07 (1'.00) A temperature instrument with an out of date calibration sticker on.it is reading 450 deg F. A recently calibrated pressure gage sensing in the same area indicates 390 psig. Is the temperature instrument reading accurately (within + or - 2 deg F)? If not, how close is it reading to the actual temperature? Assume the system is under saturated conditions. SHOW ALL WORK. (1.0) QUESTION 1.08 (2.50)
- a. What is the relationship between MAPRAT and MAPLHGR? (1.0)
- b. The process computer prints out a MAPRAT of 1.05. Is this acceptable (YES or NO)? (0.5)
- c. What physical consequence could occur if the MAPRAT limit is exceeded and under what conditions? (1.0) i QUESTION 1.09 (2.00)
Following a reduction in power from 90% to 70% with recirculation flow, ) HOW and WHY will each of the following change (INCREASE, DECREASE, NO CHANGE)?
- a. The pressure difference between the reactor and the turbine steam chest. (1.0)
- b. Final feedwater temperature. (1.0) l
(***** CATEGORY 01 CONTINUED ON NEXT PAGE *****)
1z__EBIUCIELEH_9E_NUGLEeB 29 WEB _EkoNI_9EEB6IIQN t PAGE 5 IHEBdQQ1 Nod 1GSt_dE6I_IBoNSEEB_6HD_ELUID_ELQW L 1 QUESTION 1.10 (2.00) s.- Under WHAT TWO (2) conditions is maximum power limited to'25% rather than by MCPR (Core Thermal Safety Power Limit)? (1.0)
- b. What thermal hydraulic phenomenon does operation above the MCPR Safety Limit-prevent? (1.0)
QUESTION 1.11 (2.00) Consider two RPV conditions: low power and low flow (<10%) OR high power and high flow (>85%). ;
- o. .During which condition is REQUIRED NPSH for a recirculation pump greater? (0.5)
- b. During which condition is AVAILABLE NPSH for a recirculation pump greater? (0.5)
.c. What provides the majority of the available Net Positive Suction Head for the Recirculation System during: (1.0) i
- 1. Low speed pump operation?
- 2. High speed pump operation? l QUESTION 1.'12 (1.50)
Following an-automatic initiation of LPCI at a reactor pressure of 400 psig, reactor pressure decreases to 100 psig. For each of the paremeters listed below, determine any change (i.e. increase, decrease, or remain the same). (1.5)
- a. LPCI injection flow f
- b. LPCI pump discharge head (assume constant NPSH)
- c. LPCI pump power requirements
(***** END OF CATEGORY 01 *****)
't "2i__EleNI_ DESIGN _INCLUDINQ_SeEEIX_6ND_EdEBGENCY_1YSIEd3 PAGE 6 QUESTION 2.01 (3.00)
- m. Brief'ly describe how the two sources of scram pressure. function onia scram during-high power operation to insert the control rod. ( 1'. 0 )
- b. Describe the ability of each of the sources of pressure'tci scram the reactor-during '
- 1. plant startup at.300 psig' ( 1. 0 ) ~
- 2. high power' operations (1000 psig) (1.0)
QUESTION 2.02 (3.50)
.a. Describe the mode (flowpath)'of. operation of the RWCU system that places the maximum load on the Non-Regenerative Heat Exchanger.
HOW MUCH load is on the Regenerative Heat Exchanger during this mode (NONE, MODERATE, MAXIMUM)? (2.5)
- b. 'What is'the' limiting parameter when in the above mode and what ~ is done to prevent exceeding this limit? (1.0)
QUESTION 2.03 (3.50) Main steam flows from the four main steam lines in+<, an equalizing header. List seven-(7) uses of the steam drawn off the equalizing header. (3.5) QUESTION 2.04 (1.00) The OFFGAS TREATMENT MODE SWITCH is in AUTO. Describe what determines whether the Offgas flow is being directed through the charcoal adsorbers or around them. (1.0) (***** CATEGORY 02 CONTINUED ON NEXT PAGE *****)
i.
~2t__ELeNI_ DESIGN _ INCLUDING _S6EEIY_6NQ_ECEBGENCY_1X11Ed1 PAGE 7 QUESTION 2.05 (2.50)
Match each of:the locations (a - e) with the appropriate. temperature and pressure that would be indicative of normal Offgas System operation. (2.5) TEMPERATURE (deg F) PRESSURE (psig)'
- c. Recombiner inlet 1. -5< T< 5 6. < 0 b.' Recombiner outlet 2. 50 - 150 7. 0-5
- c. Holdup pipe outlet 3.- 100 - 150 8. 10 - 20 d.- Dryer outlet. '4. 300 - 400 9. 25 - 75
- e. Charcoal bed inlet 5, 700 - 900 10. 100 - 150
. QUESTION ~ 2.06 (2.00)
HPCS has automatically initiated and RPV water level has subsequently increased to > Level 8.'
- o. Describe the HPCS-pump f3ow path in'this condition. (1.0)
- b. The HPCS pump discharge pressure transmitter, PT-N051 fails downscale. What affect does this failure have on HPCS system operation end why? (1.0)
QUESTION 2.07 (2.50)
- a. The condensate demineralizer bypass valve, A0V119, is automatically ,
opened when WHAT TWO (2) conditione exist? (1.0) !
- b. When does it automatically close? (0.5) c .. Why is the auto open feature necessary? (1.0) l QUESTION 2.08 (2.50)
{ Describe the interlock (s) on the A (or B) RHR pump that ensures a suction I path is available for pump operation. (2.5) l (***** CATEGORY 02 CONTINUED ON NEXT PAGE *****) j
o
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2t__EL6NI_DESION_INCLUDIND_18EEIX_6ND_EdEBQENGX_SYSIEd!- :PAGE 8 9 I
- i QUESTION 2.09 (2.00) >
- a. The.RCIC flow transmitter has failed low (0 gpm). Select the answer-below that best' describes how the.RCIC turbine will respond upon ,
receipt of an initiation signal. (1.0) '
- 1. The system will not start (F045 Steam Supply remains closed) l
- 2. fine turbine will trip on overspeed
- 3. The turbine will run continuously at minimum speed
- 4. The turbine-will run continuously at approximately 4500 rpm
- b. The RCIC oil pump has failed (unknown to the operator). Select the q answer below which best describes how the RCIC system.will respond upon receipt'of an initiation signal. (1.0)
- 1. The system will'not start (F045 Steam Supply remains' closed)
- 2. The turbine will trip on overspeed
- 3. The turbine w.41 run continuously at minimum speed until the turbine bearings fail
- 4. The turbine will run continuously at approximately 4500 rpm until the turbine bearings fail QUESTION 2.10 [2.50)
- a. What two (2) conditions will cause the standby RPCCW pump to star'?
Setpoints are not required. (1.9)
- b. Which RPCCW loads are ISOLATED from the RPCCW system if RPCCW pressure decreases to less than 56 psig? (1.0)
- c. Name one other action that is designed to cause the above isolation (in addition to the low RPCCW pressure). (0.5)
(***** END OF CATEGORY 02 *****) L
4, i I i i' i 4 . 7 :;.
.s-i2t__INSIBUMENI1_6ND_CDNIBQLS +- PAGE O
; QUESTION 3.01' (2.00)
D fa. A rod: withdrawal. block ' :is initiated~E when; an11RM ~ detector 11s in'the
'.'wr o ng pos i t io n" . When isf an IRM; detector in the " wrong position'.' as i
Lfaruas theLrod block circuitry is; concerned? (1; 0).
.bn 'In: addition toithe ROD / BLOCK. annunciator. what;will.be:the'only.
-indication available to'the operator.thatithe" detector'is 1 in'the
" wrong' position?"' '(1.'0)
, f.QU E ST I ON '. 3. 0 2. (1.'00)
- a. How1many, Recirculation Flow Units are,there to' provide input to the APRM's? -(0,5).
b <b.. .One off the above flos units f ails UPSCALE. What" automatic a'etion(s) is(are) generated.by this failure?' C0.5)
. QUESTION ~ 3.03- (2.00)
The' core is designedito be symmet'rical, that'is each quadrant of the core
-willibe a mirror. image ~of'the.others with respect to1 fuel and control rod position. .Why are the LPRM detectors locatedLin positions that do not-result in this sameitype symmetry.and'how'does this provide adequate neutron monitoring of'the' core? (2.0)
QUESTION 3.04 (2.00)
"An I & CTTechnician gets authorization to work on a level transmitter.
He/she opens.the transmitter equalizing valve, then shuts the high'and low _ pressure sensing lines' isolation valves. La . - How does the level' indication change and why? Assume it was on-scale prior to commencing work. (1.0) b.- What-error did the technician make and what negative consequence (s), generally. speaking, may result from his/her action?- (1.0) (***** CATEGORY 03 CONTINUED ON NEXT PAGE *****)
4t__INSIBUDENIS_6BD_GQUIB961 PAGE 10
' QUESTION 3.05 (3.00) l I
- c. A CRD has one, reed switch for one channel of'RPIS that has failed. J shut. How will the operator'know that the switch has failed j (2 required)?. (0.5)
.b. What should be done to allow rod motion to continue past~the failed-reed switch? (0.5) c ._ How many rods can be bypassed from the Rod Action Control Cabinets (electrically or physically, not~administrstively)? ( 0. 5 ).
- d. How many HCU's can be bypassed from the Rod Gang Drive Cabinet (electrically or physically, not administrative 1y)? (0.5)
- e. How does bypassing a rod at the Rod Gang Drive Cabinet differ from '
bypassing a rod at the Rod Action Control Cabinet with regard to allowing rod movement? ( 1. 0 ) - QUESTION 3.06 (1.50) The reactor is' operating at 100% power when one reactor feed pump trips. Describe how the Recirc Flow Control System responds to this event. (1.5)' QUESTION 3.07 (1.00) How does the Recirculation Flow Control System, in conjunction with the Recirculation System, aid in RPV depressurization in the event of a large break in the recirculation piping? .(1.0) QUESTION 3.08 (2.00) l The reactor is operating at 8% power, starting up the turbine generator, i when a main condenser pressure switch associated with the Steam Bypass l Valves fails to O psig. Describe how the plant responds to this [ failure. (2.0) (***** CATEGORY 03 CONTINUE 0 ON NEXT PAGE *****)
! 2t__INHIBudENIS_6MD_99 NIB 9LS PAGE 11 QUESTION 3.09 (2.00) What cre.the four (41 conditions that will r es u l't in a turbine " runback", or_ repositioning of the load set motor operated potentiometer to reduce the load reference signal to.the speed / load summer? Explanation of the runback
<or setpoints is NOT required. (2.0) 1 i
QUESTION 3.10 (2.00). Feedwater Level Contrcl-is usir.g Narrow Range Channel A for reactor vessel
' level control. The reactor is operating at 100% power. A leak occurs in the variable sensing line to the A level transmitter (shared by the C level . transmitter) which.results in a reduced pressure la that - line. Describe 'how the Feedwatar Control System will respond with no operator action AND WHY. . INCLUisE how and why this event affects continued reactor operation.
i QUESTION ~ '3.11 (2.00)
- n. What condit ions' will' ir.itiate the SETPOINT SETDOWN feature of the Feedwater Level Control System? (0.5)
- b. Describe the functioning of the SETPOINT SETDOWN control feature.(1.5)
QUESTION 3.12 (2.50) .
- a. What conditions must be met to satisfy the logic for automatic ADS initiation? Setpoints not required. (2.0)
- b. What condition must be met to satisfy the logic for manual ADS initiation? Setpoints not required. (0.5)
(***** END OF CATEGORY 03 *****) j
I t , di__EB9CEDVBES_:_NQBdekt_6BN9BdeL&_EUEBGENCY_eNQ PAGE 12
-BeDIDL991966_GQNIB96-l.
f' QUESTION. 4.01 (2.00) Th'e Operator "At - the - Controls" will manually initiate a reactor scram i whenever one of.WHAT TWO GENERAL-CONDITIONS occurs? (2.0) l l QUESTION 4.02 (1.00). Indicate whether the following statements are TRUE or. FALSE: (1.0)
- a. An OPERATOR license is. required for an. operator.to perform-a core-i alteration. l
- b. During Operational Condition 4 or. 5, an-individual with a valid OPERATOR's license may,be designated to. assume the' control room command function during an absence of the Shift-Supervisor from.
the control room. QUESTION 4.03 (3.00) j
- c. During a plant startup, at approximately what power level is Main Steam lined up to-the Moisture Separator Rehesters?. (0.5)
.b. Operation of'the Steam Supply Valves to the MSR's-(1 MSS-MOV111/112) must be closely coordinated between.the "at the controls" operator and the " BOP" operator. What negative consequences (2) may arise from operating the steam supply valves too rapidly at low reactor power with the generator at low load? (2.0)
- c. At approximately what power are the heater drain pumps placed in service? (0.5) l QUESTION 4.04 (2.00)
- n. If all three Instrument Air Compressors are available, HOW MANY should be running and WHY? (1.0) i
- b. A loaded Instrument Air Compressor tripped due to high discharge air temperature. When can it be restarted (by procedure) and why the restriction? (1.0) J l
(***** CATEGORY 04 CONTINUED ON NEXT PAGE *****)
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3., , r L i _y :V . I, . w idt_iEBQCEDUBES__NDBdekt_ABNfBdekt_EdEBGENGX_eND- PAGE 13 P .LB8DIDLDDICAL_QDNIBDL ,'
% i QUESTION 1 4.05' (2.00)'
' ~ , Dur.ing Cold [ Shutdown conditions with-the RPV head'in place, what are1TWO. CONDITIONS that shall be met to minimize temperature 1 stratification-which may cause.coolantitemperatures:to exceed 212 deg F.and inadvertent RPV
. pressurization? >
-(2.0)
. QUESTION. 4.06. -(2.50)
Per the E0P's, list'five. (5)-specific. conditions that require EMERGENCY RPV. DEPRESSURIZATION.1 . (2.5) QUESTION!'4.07 1 (2.00) Under what1 set of conditions is'A0P-0020, " Alternate Shutdown Cooling,"'
. initiated-and performed? (2.0)
LQUESTION' 4.08: (2.00) A scram signal is-received'with.the reactor at power, but the control rods do notrfully insert (several remain in:the full out position). What immediate operator actions are required per AOP-0021," Anticipated. Transient Without Scram?" Use the conditional statements'below in your answer. Eachfpart below may-have more than one substep. (2.0) a.: IF'the main turbine is on line, THEN ...
~
Lb .- IF reactor power is above 5% or cannot'be determined, THEN ...
- c. . IF all control-rods cannot be inserted beyond 04 BEFORE ...
QUESTION L4.09 (1.50) What are three modes of failure , with regard to the feedwater heating 1 system,.that can result in cooler feedwater reaching the RPV. Assume power ,y ' operation. (1.5) (***** CATEGORY 04 CONTINUED ON NEXT PAGE *****)
- p. ; 7 ,,,
f Vj; 4%i Tj' ; , y, s. .. D:. ry Ol
'o' -at__EBRIf0!/8ES_ _N98 Lie' t_6BNDBd6Lt_EM680 L ENC 1_6UQ PAGE 14 1 B6010600196L_C9 NIB 9L )
a ? ,4 , s i )
, 8 .
, QUESTICt4! 4.10 I
( 2. 50 )' d ;24 yecr old individual, with ailifetime exposure of 23' REM through the isut quarter, will be wo'rtting 14 a 200 MREM /hr gamma field.- In addition i to the; lifetime dose, the individual has received 850. MREM this quarter. j
- o. How long may this indiviciusl wor k in this. area before he/she eaches a radiation exposure limit? (1.0)
- b. Whose recommendation (%i and approval (ol'cre nueded to allow the 1
' individual.to exceos ?.his limit? (1.0) ;
~
- c. If,the radiation field had been bata instead of gamma, how would the !
El 'a m i t in p'urt "a" have changed (state the limit)? (0.5) l
)
i U' h;p 4 QUESTION 4.11 (2.50) i
- n. If an individual performing _an activity cannot or believes he/she ,
should not f ril low the procothre goveening that activity, what ! two (2) actions should be taken? (1,0) j L# b. What two (2) methods'of resolving'the procedural discrepancy ~ are available? (0.5) {
- c. A safety-relathd valve position checklist is being performed L with the initial performer and Independent verifier performing their functions = simultaneously,' Is this satisfactory? EXPLAIN. (1.0)
QUESTION 4.12 (2.00) 3
- a. The loss of one RPS bus requires system isolations to be' reset.
which system tuolation must be *uset within a very short period of time tc preclude' requiring further operator action? (0.5)
- b. What length of time is a "very short period of time" per AOP-0010,
'%oss of One RPS Bus?"' [0.5)
- c. What action must be taken if the isolation mentioned in part "a" above io not reset within the specified time? (1.0) f.
'r$
I l t (***** END OF CATEGORY 04 *****) (************8 EMD OF EXAMINATION ***************)
NRC LICENSE EXAMINATION HANDOUT EQUATIONS, CONSTANTS, AND CONVERSIONS i 6=m*C*deltaT p 6=U*A*deltaT P = Po*10sur*(t) p , p ,,t/T SUR = 26/T T=1*/p+($-p)/Xp T=1/(p-$) T = ($-p)/X p p = (Keff-1)/Keff = deltaKeff/Keff p = 1*/TKeff + jeff/(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 Hg. Miscellaneous Conversions I curie = 3.7 x 104v 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 Stu = 778 ft-lbf
)
i It__EBINCIELES_QE_ NUCLE 68_EQWEB_EL6NI_DEEBoIIQNt PAGE 15 IBEBdDDINedIGSt_BE6I_IB6NSEEB_6ND_ELVID_ELQW j ANSWERS'-- RIVER BEND 1 -87/05/26-GRAVES, D. 1 . ANSWER 1.01 (1.50)
- n. . Operator can notice that period has become longer (0,25) and that power. change on IRMs, SRMs is leveling off(0.25). d
- b. 2 (1.00) (From P = Poe(t/T) --> T = t/In (P/Po), in Interval 2 the period has lengthened from 80 seconds. The other intervals have 80 second periods)
REFERENCE River Bend LOTM-TH-4.15-1, pg 1 LOTM-TH-4.17-1, pg 1 - K/A292008 K1.12 3.6/3.7 292008K112 ...(KA'S) ANSWER 1.02 (3.00)
- n. 1, 4
- b. 6
- c. 2
- d. 3
- e. 5 f, 4 Ca- f at 0.5 each)
REFERENCE I River Bend LOTM-TH-4.3-0, pg 3 LOTM-TH-4.7-0, pg 4, 5 LOTM-TH-4.11, pg i K/A 292001 K1.01 2.0*/2.1* K1.02 3.0/3.1 K/A 292002 K1.11 3.2/3.3 ; 292001K101 292001K102 292002K111 ...(KA'S) 4
It__EBINCIELES_9E_NUGLEeB.EDWEB_ELeNI_QEEBoIIQNt PAGE 16 IUEBUQDINedICS t_BEeI_IBeNSEEB_eND_ELUID_ELQW ANSWERS -- RIVER BEND 1 -87/05/26-GRAVES, D. ANSWER 1.03 (3.00)
- c. Doppler (-), .MTC C-), Void (-)
- b. Void ( + ), Doppler (-), MTC (- ) '
- c. Void (-), Doppler (+), MTC (+)
(0 25 for each + or - and 0.25 for the order) REFERENCE River Bend LOTM-TH-4.16-0 through 4.19-0 K/A-292004 K1.01.3.2/3.2 K1.05 2.9/2.9
'K1.10'3.2/3.2 292004K101 292004K105- 292004K110 ...(KA'S)
ANSWER 1.04 (2.00) O. FALSE
- b. TRUE
- c. FALSE <
- d. TRUE (0.5 each)
REFERENCE River Bend LOTM-TH-4.20-1, pg 4, 5 K/A 292005 K1.07 2.4/2.6 K1.09 2.5*/2.6 292005K107 292005K109 ...(KA'S) ANSWER 1.05 (1.50)
- n. Xenon (0.5)
- b. Xenon (0.5)
- c. Samarium (0.5)
REFERENCE River Bend LOTM-TH-4.21-1 LOTM-TH-4.22-1 K/A 292006 K1.02 3.1/3.1 K1.15 2.1*/2.1* 292006K102 292006K115 ...(KA'S) c
4 .
, s
} ?
/
h.' '
]
L - 11__EBINCIELES_QE_NUCLEeB_EQWEBLELeNI_QEEB6IIQNt PAGE 17c LIBEBdDDINedICSt_HEeI_IB8NSEEB_eND_ELUIQ_ELQW k ANSWERSc ,- RIVER BEND 1 -87/05/26-GRAVES, D.- . L' q ANSWER.' 1".06 (3.00).
'a. . (U235 0.93 X1.0064)e+ (U238 0.07 X .0157) = CORE BETA
'(
.0070 miCORE BETALat BOL (0.1 for each' isotope, . 0.2'for each B, 0.2 for.each %)
Accept indicated' values + or - 10% b.- '(U235 0.55-X. 0064) + (U238'O.07 X .0157) + (Pu239 0.38 X 0021) =.
' CORE BETA EFFECTIVE ='.0054.at EOC (0.1'~each_for. isotopes,.%'s, B's,cTotal'B)
- c. For?a given positive reactivity change,'the-nuclear' response will be. f aster - (shorter- period) (1.0).
REFERENCE.. River Bend LOTM-TH-4.14-1,-pgs 5-7 K/A 292003^K1.04 2.5/2.5 K1.06:3.7/3.7 292003K104 292003K106 ...(KA'S) , i ANSWER - 1.07 (1.00)
. '390.psig +:14.7 psig = 404.7 psia (0.25)
Saturation. temperature for 404.7 psia: (456.28 deg F _ 444.6 deg F)(4.7/50) + 444.6~deg F = 445.7-deg F (0,5) The temperature. instrument is reading 4.3 deg too high (0.25) REFERENCE , l Steam Tables 293003-K1.23 2.8*/3.1* 293003K123 ...(KA'S) e
p
.t
'It__EEIUCIELES_DE_NUGLE68_EDWEB_EL6NI_9EE86IIQNt PAGE 18 IHEBdQDXU6 DIDST _BE6I_IB6NSEEB_6HD_ELWID_EL9W ANSWERS ~-- RIVER. BEND 1 -87/05/26-GRAVES, D.
ANSWER 1.08 (2.50) ,
- c. MAPRAT = MAPLHGR (actual) / MAPLHGR (limit) (1.0) b No (0.5)
- c. The clad temperature could excae'd 2200 deg F.(0.5) during a LOCA.
or core uncovery (0.5). REFERENCE River Bend LOTM-TH-3.10-0 pg 2 ! 293009 K1.11 2.8/3.6, K1.13 3.1/3.6 4 293009K111 293009K113. ...(KA'S) 1 ANSWER 1.09 -(2.00) a.- Decreases (0.5). With less steam flow there is less pressure drop in the steam lines (0.5) and steam chest pressure is. closer to reactor pressure.
- b. Decreases (0.5). Less extraction steam from the turbine to heat ,
the feedwater (0.5). -! REFERENCE l River Bend..LOTM-IC-9-0, pg 4, Figure i BWR Transients-239001 A1.01 3.6/3.6 259001 A1.02 3.2/3.3 ANSWER 1.10 (2.00) a.. Reactor vessel dome pressure <785 psig (0.5) OR. core flow <10t of rated flow (0.5).
- b. Transition boiling (1.0).
REFERENCE River Bend Technical Specifications 293009 K1.20 3.1/3.6 System Generic #8 3.7/4.3* 293009G008 293009K120 ...(KA'S) i
y
.it__EBING1ELES_DE_NUGLE68_EQWEB_EL6NI_9EEB611QNt PAGE 19 IBEBdD01NedICSt_UEeI_IB6NSEEB_6ND_ELUID_EL9W ANSWERS -- RIVER BEND 1 -87/05/26-GRAVES, D.
ANSWER 1.11. (2.00)
- a. High flow high power (0,5)
- b. High flow high power (0.5)
- c. . 1. Height of water in the reactor vessel (0,5)
- 2. Subcooling effect of the incoming feedwater-(0.5)
REFERENCE General Electric _ Thermodynamics Heat Transfer and Fluid Flow, , Ch. 7, PP. 92-97 i River ~ Bend LOTM-TH-1.4-0, pg 3 General Electric - BWR.6 Technology i ANSWER 1.12 (1.50)
- a. Increase (0.5)
- b. Decrease (0.5)
- c. Increase (0.5)
REFERENCE G.E. Heat Transfer and Fluid Flow, Ch. 6 pg. 6-95 & 6-96. SLO 6-10. River Bend LOTM-TH-1.4-0, pg 4-5 KA 291004-K1.05-2.8/2.9 291004K105 ...(KA'S)
'l 2t__EL6NI_DESION_INCLUDIN9_S6EEIX_6ND_EMEBGENCX_HYSIEd3 PAGE 20' 1 . ANSWERS - RIVER BEND 1 -87/05/26-GRAVES, D. ;
ANSWER ~2.01 (3.00)
- e. HCU accumulator pressure provides the pressure for the initial insertion (0.5). As the accumulator discharges to < reactor. pressure, I accumulator pressure is blocked and reactor pressure is applied to the
. drive,to complete'the scram (0.5).
- b. 1. Reactor pressure will not scram the rod (0.5).
Accumulator pressure scrams the rod (0.5).
- 2. Reactor pressure alone will completely insert the rod-(0.5).
Accumulator pressure alone.will completely insert the rod (0.5). REFERENCE River Bend LOTM-3-1, pg 20-21
.K/A 201001 K4.05 3.8/3.8 201001K405 ...(KA'S)-
ANSWER 2.02 (3.50)
- a. RWCU flow will be taken from the.RR. loops and RPV (0.25), through the RWCU puraps (0.25), through the RHX (0.25), through'the NRHX (0.25) i through the filter /demin (0.25), through the flow control valve (0.25) to either the condenser (0.25) or radweste (0.25). The RHX is under !
no load (0.5). A less detailed flow path was accepted. RHX may be under moderate load if not all flow is being rejected. H l
- b. NRHX RPCCW outlet temperature (0.5)
Restrict the RCS flow rate to prevent exceeding (0.5) REFERENCE River Bend LOTM-6-1, pg 12 ! K/A 204000 K1.01 3.1/3.3 l K1.02 2.9/3.0 K1.06 2.8/2.8 K1.07 2.6/2.7 A2.12 2.7/2.8 204000K107. 204000K106 204000K102 204000K101 204000A212
...(KA'S) l l
2t__EL6NI_DESION_INGLUDIN9_S6EFIX_6ND_EdEBGENGl_SYSIEdf PAGE 21 ANSWERS -- RIVER BEND 1 -87/05/26-GRAVES, D. ANSWER 2.03 (3.50)
- steam seal evaporator (gland seal) - Rad Weste aux steam
_ SJAE
- Offges preheater - MSR's - BPV's - Main turbine (0.5 each)
REFERENCE' River Bend LOTM-8-1, Figure 1 K/A 239001 t.1.03 3.4/3.4 K1.05 2.8/2.8 K1.06 3.4/3.4 K1.07 3.1/3.1 K1.08 2.9/3.1 K1.09 2.7/2.8 239001K108 239001K107 239001K106 239001K105 239001K103
...(KA'S) ,
ANSWER 2.04 (1.00) If the post treatment rad monitor (either channel) has a high radiation clarm, the adsorbers are in service and the BPV will be closed (1.0). REFERENCE River Bend LOTM-15b-0, pg 8 K/A 271000 A2.04 3.7/4.1 A3.07 3.4/3.6 271000A307 271000A204 ...(KA'S) I
1
, i 1
I
~2t__EL6NI_QESIEN_INCLUDIND_26EEIY_6NQ_EMEBGENCX_SYSIEd3 PAGE 22
. ANSWERS - RIVER BEND 1 -87/05/26-GRAVES, D.
'i ANSWER. 2.05 (2.50)
- n. 4, 7 b.. 5, ' 7 ,,
- c. 3, 7
- d. 2, 7.
- e. 1, 7 (10 at 0.25 each)
REFERENCE River Bend LOTM-15b-0, pg 30 K/A 271000-A1.03 2.24/2.3 A1.04 2.2*/2.4 A1.09 2.1*/2.4' j System Generic 15 3.8/4.1 271000G015 271000A109 271000A104 271000A103 ...(KA'S) ANSWER 2.06. (2.00)
- s. From the CST'(0.25), through the pump (0.25), through the minimum flow valve (0.25), to the suppression pool (0.25).
- b. The minimum flow valve will shut (0.5) and HPCS pump damage could- ;
result if no-flow is established with the pump running (0.5). Also accepted: min flow valve will' shut-(0.5) because of the loss of
~
one^of the two permissives required for the valve to open (0.5). REFERENCE River Bend LOTM-18-0, pg 8, 30 K/A 209002 K4.03 2.3*/2.4 A2.08 3.1/3.2 209002K403 209002A208 ...(KA'S) 1. l
w k f 2t__EL6dI_ DESIGN _ INCLUDING _26EEIY_eUQ_EdEBQENQ1_$1 HIED 3 PAGE 23 ANSWERS'_- RIVER' BEND 1 -87/05/26-GRAVES,'O.
- ANSWER .2.07 (2.50) c.. generator load >.or =.70% C0.5) turbine tripped ( 0. 5 )" j
- b. 60 seconds-after opening, following a turbine trip (0.5)
- c. Prevent feedwater pumps from tripping (0.5) on low suction pressure during actuation of setpoint setdown (0.5).
REFERENCE River Bend LOTM-12-1, pg 15, 33, 34 K/A 259002 K4.01 3.0/3.1 i K/A 256000 K2.10 3.1/3.1 259002K401 256000K210 ...(KA'S) ANSWER. 2.00 (2.50) The.RHR pump.will trip [0.1] if the Shutdown Cooling Inboard Isolation l Valve.(F009) [0.3], Shutdown Cooling Outboard Isolation ValveLCF008) [0.3), 1 OR [0.1] Shutdown Cooling Suction Valve (F006) [0.3] not fully open [0.3], k AND [0.1) Suppression Pool Suction Valve (F004) [0.3] AND [0.1] Upper Containment Pool Suction Valve (F066) [0.3] are not fully open {0.3]. REFERENCE River Bend LOTM-20-0, pg 3 K/A 2C5000 K4.04 2.6/2.6 l
.205000K404 ...(KA'S) l l ANSWER 2'.09 (2.00) f
- a. 4 (1.0)
- b. 2 (1.0)
REFERENCE River Bend LOTM-21-0 GE BWR-6 Technology j K/A 217000 A2.07 3.1/3.1 A2.10 3.1/3.1 f 217000A210 217000A207 ...(KA'S) { l l 1 i e
.m 2x__EL6NI_ DESIGN _ INCLUDING _S6EEII_6ND_EMEBGENGY_SISIEd3 -PAGE. 24 ANSWERS __ RIVER BEND 1 -87/05/26-GRAVES, D.
' ANSWER 2.10. -(2.50) a.. Llow .RPCCW pressure (0.5):< 100 psig
' Trip of'one of the operating RPCCW pumps (0.5)
- b. Fuel pool coolerc ALand B RHR pumps A'and B ,
CR0 pumps A and.B ( '3 at 0.33 each) ,
- c. Manuel initiation of SSW (0.5)
REFERENCE River Bend LOTM-23-D pg-5, 6, Figures'1 and 2 ; K/A'223002 K1.19.2.7/2.G { 223002K119 ...(KA'S): i l i I I l
4 2t__INSIBudENIS_6ND_C9 NIB 0LS PAGE 25
' ANSWERS -- RIVER- BEND 1 -87/05/26-GRAVES, D.
ANSWER. -3.01 (2.00)
- c. The' detector is not full in (0.5) and the MODE SWITCH is not in the RUN position (0.5). l
- b. The absence of an IN light on the affected IRN Drive select' matrix with drive power.available ( 1. 0 ) . . ]
REFERENCE River Bend LOTM-IC-2, pg 15 ; K/A 215003 K4.01 3.7/3.7 215003K401 ...(KA'SJ ANSWER 3.02 (1.00)
- n. 4 (0.5)
'b. - rod block (0.5)
REFERENCE River Bend LOTM-IC-4-0, pg 4, 12, Figure 2 .
.K/A 215005'K1.09 3.6/3.6 K1.16 3.3/3.4 215005K116 215005K109 ...(KA'S) )
ll l ANSWER 3.03 (2.00) j 1 Each location without a LPRM string has a representative string in one of j
.the other quadrants (1.0) such that mirror image and rotational symmetry of j power level monitoring exists across the core as long as the control rod and fuel symmetry' remains (1.0).
REFERENCE River Bend LOTM-IC-3-0, pg 3 K/A 215005 K1.04 3.6/3.6 215005K104 ...(KA'S) l l l i i l i
k v at__IU2189dENIS_6ND_QQNIBQL3 PAGE 26 ANSWERS -- RIVER BEND 1 -87/05/26-GRAVES, D. 1 I
-ANSWER 3.04' (2.00) I l
- a. The level indication would go to the maximum level reading or off-scale high (0.5). Equalizing across the detector causes a0 i differential pressure which means the variable' leg level is as high as )
the reference leg level _(0.5), which would be max level. l b.. The technician opened the equalizing valve pr'ior to isolating the detector-(0,5). Other instruments sharing that reference or variable sensing.line may be partially or. fully equalized causing. improper indications or unexpected trip signals (0.5). ! REFERENCE i River. Bend LOTM-IC-6-1, pg 4 K/A 216000 A1.02 2.9*/3.1* 4
.216000A102 ...(KA'S) l l
ANSWER 3.05 ~C3.00)
- a. A rod block will be received (0.25) along with a CHANNEL DISAGREE light (0.25) on the Rod Motion Matrix.
- b. Substitute' data from the channel of RPIS that is functioning (0.5).
- c. 8 (0.5)
- d. 1 (0.5)
- e. Bypassing a rod at the RGDC prevents the drive signal from the RGDC j from'being sent to that HCU, therefore rod motion is prevented (0.5).
I Bypassing a rod from the RACC makes it invisible to the Rod Pattern Controller, but will still move in the normal fashion (0.5). [ I l REFERENCE } River Bend LOTM-IC-7-0, pg 31-33, 40, 47, 48
.K/A 201005 K1.05 3.6/3.6 K1.06 3.3/3.3 K6 02 3.2/3.2 201005K602 201005K106 201005K105 ...(KA'S)
e / i 4 . I 2t__INSIB9dENIH_6NQ_GQNIBQLS PAGE 27
. ANSWERS.- -RIVER BEND 1 -87/05/26-GRAVES, D.
h E ANSWER 3.06 (1.50) ' h- 'When reactor . level decreases to level 4 (0.5),.the Flow; Control Valve !
- will run back to 48% flow (0.5) and the flow contPollers will trip to-manual (0.5).
REFERENCE River Bend LOTM-IC-8-0, pg 16 K/A 202002 K6.04 3.5/3.5 20*iOO2K604 ...CKA'S) l ( ANSWER 3.07 (1.00) The-FCV's lock in the " motion inhibit" mode (1.0) REFERENCE
. River Bend LOTM-IC-8-0, pg 16
- K/A 202001 A2.02 3.7/3.9 K/A 202002 A2.08 3.3/3.3 302002A208 202001A202 ...(KA'S) t ANSWER 3.08 (2.00)
The bypass valves trip shut (0,5). Reactor pressure will increase due to lack of steam loads.CO.5) which in turn will cause reactor power to ' increase (0,5) and the reactor will scram on either high flux or high pressure (0.5). , i REFERENCE River Bend LOTM-IC-9-0, pg 6 ! K/A 241000 K6.05 3.4/3.4 214000K605 ...(KA'S) l 1
2t_ INSIBudENIS_6HD_C9BIBQLS PAGE. 28 ANSWERS ~-- RIVER BEND 1 -87/05/26-GRAVES, O. q' t ANSWER. 3.09 (2.00) 1
- 1800' RPM not selected on the SPEED SET portion of the Turbine Control l Penel
- If the load' limit pot is greater than 4% below the-load set j
- Power / Load Unbalance
- Loss of stator. cooling
- High level in the'Sth or 6th point heater (4 required at 0.5 each) 1 REFERENCE River Bend-LOTM-IC-9-0, pg 78, 79 ,
K/A'241000 K4.07 3.2/3.5 214000d407 ...(KA'S) AMSWER 3.10 (2.00) The transmitter will sense a lower level'in the reactor-due=to the reduced pressure in the variable' leg (6.5.). Channels A and C'will indicate low. The FWCS sees a need for increased. flow (0.5) and opens the FWCV'more to increase flow and raise level (0,5). Level continues to increase until.the reactor scrams on high level (0,5). REFERENCE River Ber,d LOTM-IC-10-1, pg 20, Figure 2 K/A 259002 K1.03 3.8/3.9 K6.05 3.5/3.5 259002K605 259002K103 ...(KA'S) i
2t__INSIBLJdENIf_oND_CONIB9L$ ' P GE 29 ANSWERS -- RIVER BEND 1- -87/05/26-GRAVES, D. ANSWER 3.11 (2.00)
- c. Reactor Water Level < Level.3 (0.5) with the. control system in automatic.
- b. When initiated,'the mester level controller raises the level demand- !
signal by'18", to 54" (0.5). This demand remains for 10 seconds (0.5) after whichgthe master. controller reduces the level demand signal to 18" (0.5) which remains in effect until the logic is reset. REFERENCE Hiver Bend LOTM-IC-10-1, pg 17 K/A 259002 K4.04 2.9/2.9 259002K404 ...(KA'S) AN3UER 3.12 (2.50)
- n. - Low reactor water l e v e l .C O '. 4 ) l
- Confirmatory low water level (0.4)
- High drywell pressure'OR (0.2)
Low' reactor level for 5 minutes (0.2) Time delay (105 see with above conditions met) (0.4)
- One low pressure ECCS pump running per division (0.4)
- b. - The-low pressure pump must be running to manually initiate (0.5)
REFERENCE Rivor Bend LOTM-IC-14-0, pg 3, 5 i K/A 218000 K4.02 3.8/4.0 K4.03 3.8/4.0 218000K403 218000K402 ...(KA*S)
di__EB9CEDUBES_=_80Bdelt_8BNDBdekt_EdEB0ENCY_6NQ PAGE 30 B6D10L90106L_G9 NIB 9L ANSVERS'-- RIVER BEND 1- -87/05/26-GRAVES, D. ANSWER 4.01 (2.00) h
- A scram setpoint is exceeded and an automatic scram'did not occur (1.0) - Plant conditions'are approaching an unsafe condition and a manual' reactor scram will mitigate.the consequences of this condition (1.0) l REFERENCE River Bend A0P'0001, Reactor Scram, Rev 3, pg 2 K/A 295005 Generic 11 4.3*/4.5*
295006G011 ...(KA'S) t ANSWER 4.02 (1.00)
- n. False (0.5)
- b. True (0.5)
REFERENCE River Bend Technical Specifications 6.2.2 K/A 294001 A1.11 3.3/4.3* A1.12 3.5/4.2 294001A111 294001A112 ...(KA'S) ANSWER 4.03 (3.00)
- a. 15% (accept 10 - 20%) or 100 - 200 MWe (0.5)
- b. Rapid opening of the steam supply valves at low reactor power can interfere with heatup rate and reactor power level control which may result in a reactor thermal f~1ux scram (1.0). At low generator loads, opening the valves too fast may result in a large load deci' esse and subsequent reverse power trip of the generator (1.0),
- c. 50% (accept 40 - 60%) (0,5)
REFERENCE , River Bend SOP-0010, MSR and FW Heaters Extraction Steam and Drains, Rev 2 Pg 10, 10a, 11 K/A 239001 K1.03 3.4/3.4 K1.05 2.8/2.8 K/A 259001 K1.17 2.4/2.4 239001K103 239001K105 259001K117 ...(KA*S)
+ ,
at__EB9CEQMBES_:_UDBd6Lt_6HU9806Lt_EdEBGE691.6NQ PAGE' 31 i B6DIQLDSIG6L_GQUIBQL ANSWERS -- RIVER'BENO 1 -87/05/26-GRAVES, D. j ANSWER 4.04 (2.00)
- a. 3 (0,5) to prevent the internals from beceding galled while the ccmpressor is'left idle (0.5).
- b. It can be restarted after it has cooled'to ambient temperature (0.5).
Introducing' cool water to the hot cylinder walls may crack them (0.5). REFERENCE River Bend 90P-0022, Instrument Air System, kev 1, pg 2, 2a K/A 295019 Generic 7 295019G007 ...(KA'S)-
, -g ANSWER 4.05 (2.00) i
- 1. At least one shutdown cooling loop should be in operation.
- 2. RPV water level shall be maintained greater than 75" (using Shutdown Level Instrumentation when RR pumps are secured).
- 3. In the event forced circulation is unavail8ble-(RR pumps'off) and i water level is'at or below the Minimum Natural Circulation Level for j any reason, then periodic monitoring of vsssel metal temperatures j above and below the intended water level ~should be initiated.
(2 required.at 1.0 each) REFERENCE River Bend SOP-0031, RHR, Rev 3, pg 4a K/A 205000 K5.03 2.8/3.1 K6.03 3.1/3.2 K6.04 3.6/3.6 205000K503 205000K603 205000K604 ...[KA*S) l l I
w. I 3x__EB00EQUBES : NDBUoLt_6HNDBd6Lt_EdEBGENC1_6NQ PAGE 32: { 2 ( < B6010LQQIQek-QQUIB0L l ANSWERS.-- RIVER BEND 1 -87/05/26-GRAVES, D. }i L ANSWER 4.06 (2,50) RPV flooding is required and < 7 SRV's are open.
- Suppression pool temperature and RPV pressure'cannot be~ restored and maintained below the Hest Capacity Temperature limit.
Orywell temperature cannot be maintained < 330.deg=F.
- Suppression Pool water' level cat' snot be maintained above the Heat Capacity Level limit or below.the Suppression Pool load limit, i
- Secondary containment temperature, radiation levels, or water levels in more than one area exceed the Maximum Safe Operating Limits'and a primary system is discharging into a Secondary Containment Area.
- RPV pressure is too high to permit available injection systems,-
subsystems, or alternate inj ection subsystems to inj ect adequate flow l into the RPV. l
- Containment temperatures cannot be maintairied below 185 deg'F.
- Containment pressure reaches 19.7 psia. 1
-(5 required at G.5 each)
REFERENCE
' River Bend E0P-0001, RPV Control, Rev 6, pg 14 -]
K/A.218000 Generic 15 4.2*/4.4* l K/A 295025 Generic 11 4.2*/4.3* 2180000015 295025G011 ...(KA'S) ANSWER 4.07 (2.00) RHR shutdown cooling mode cannot be established (0.5) and the RPV can no longer be cooled down by depressurization (0.5) and RPV temperature must be reduced CD.5).and/or the RPV must be maintained in a cold shutdown condition (0.5). REFERENCE River Bend AOP-0020, Alternate Shutdown Cooling, Rev 1, pg 2 K/A 295021 Generic 11 3.6/3.8 295021G011 ..,(KA'S)
at__EB9CEDUBES_: NDBdeLt_6BNDBdelt_EMEBGENGl_6NQ PAGE '33 B6DIDLQDIG6L_G9NIBQL ANSWERS -- RIVER BEND 1- -87/05/26-GRAVES, D. ANSWER 4.08 (2.00)
- n. ... rapidly reduce reactor recirculation flow by transferring the'RR l pumps to slow speed (0.5) b.- ...-trip the RR pumps (0.5)
- c. . . . - suppression pool temperature 1 reaches 110 deg F (0.25), THEN inject boron with SLC C0.25').
- 1. Prevent automatic initiation of ADS (0.125).
- 2. ,Use one SLC pump (0.125).
3.. Inj ec t the entire tank-contents, THEN shutdown the SLC_ pumps (when. indicated level reaches O gallons) (0 125).
- 4. Confirm auto isolation or manually isolate RWCU (0.125).
REFERENCE , River Bend A0P-0021, Anticipated Transient Without Scram, Rev 0,.pg 3 K/A 295015 Generic.10 295015G010 ...(KA'S) ANSWER 4 09 (1.50)
- Closing of an extraction steam isolation valve to the heater (0.5) - Heater string isolation (0,5) - Heater string bypassed (0.5)
REFERENCE River Bend AOP-0007, Loss of Feedwater Heating, Rev 2, pg 2 , K/A 295014 AA2.03 4.0/4.3*
'295014A203 ...(KA'S)
< i cat __EB00EDUBgS_ _NDBd6Lt_6BNDBd6Lt_EdEBQENQX_6ND. PAGE 34 86DIDLQQIG6L_CONIB0L ANSWERS -- RIVER BEND 1 -87/05/26-GRAVES, D. i l
' ANSWER 4.10- (2.50)
- a. 1000 MREM - 850' MREM = 150 MREM i
150 MREM / (200 MREM /hr) = 0.75 hr or 45 minutes (0.5 pt for the limit, 0.5 for the stay time)
- b. Assistant Plant Manager recommendation (0.5)
Supervisor-Radiological Programs approval (0.5) c.. The limit would be 5 REM instead of 1 REM (0.5) REFERENCE GET II-1, pg 4 . K/A 294001 K1.03 3.3/3.8-294001K103 ...(KA'S)- ANSWER 4.11 (2.50)
- n. - Place the system / component in a stable and safe condition (0.5)
- Inform the responsible supervisor (0.5)
- b. - Determining the method by which the activity can be performed using the procedure as written (O'.2G)
- Submitting a procedure' change (0.25)
- c. No (0.25). The independent verification will be performed separately without visual or audible contact with the first performer (0.75).
REFERENCE River Bend ADM 0022, Conduct of Operations, Rev 8, pgH21, 22 K/A 294001 K1.01 3.7/3.7 l A1.02 4.2*/4.2* j 294001A102 294001K101 ...[KA'S) 4
1 4t__EBQGEDUBER_:_NDBdeLi_6HN9Bdekt_EdEBGENGl_6ND PAGE: 35 B6D10LOGIQeL_CONIBQL' ,
, jl ANSWERS - RIVER BENO 1 -87/05/26-GRAVES, D. l 1
l 1
.1 ANSWER 4.12' ' ( 2. 00 3' :.
- a. RPCCW (0.5)
- b. . One minute (0,5)
Ec. Trip both recirculation pumps '(1.0)
.l REFERENCE River Bend AOP 0010, Loss of One RPS Bus, Rev 2, pg 2,4 K/A 295020 AK1.01 3.7/3.9 Generic 10.3.6*/3.5*
2950200010 295020K101 ...(KA'S) , l l 6 i i k
U. S. NUCLEAR REGULATORY-COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION FACILITY: _BIVEB_ BEND _1____________ s REACTOR TYPE: _QVB-QEh_________________ DATE ADMINISTERED: _QZlDE42h________________ EXAMINER:- _QB6VEEt_Qt______________ CANDIDATE: _________________________ .
- , 4 I' .
1 INEIBUDIIDNE_ID_DeNQ1DalEl Use separate paper _for the answers. Write answers on one side only. Staple question sheet on top'of the answer sheets. Points for each question are indicated'in parentheses af ter: the question. The passing grade requires at.least 70% in each. category and a final grade of at least 80%. Examination papers will be picked up six (6) hours after the examination starts.-
% OF ;
CATEGORY % OF CANDIDATE'S CATEGORY i __VaLUE_c_IDI6L ___EDDBE___. _VaLUE__ ______________D8IEQDBY
- _2EADD__ _25100 ___________ .________ 5. THEORY OF NUCLEAR POWER.. PLANT OPERATION, FLUIOS, AND THERMODYNAMICS
_ 2EADD__ 25tDD ___________ ________ 6. PLANT SYSTEMS DESIGN, C ON T R O L', AND INSTRUMENTATION _2EADD__ _254DD ___________ ________ 7. PROCEDURES - NORMAL, ABNORMAL, j EMERGENCY AND RADIOLOGICAL i CONTROL l _25 ADD __ 2EADD ___________ ________ 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS 100tDQ__ ___________ ________* Totals Final Grade '
'All work done on this examination is my own. I have neither given ;
I nor received aid. Candidate's Signature { l l l
s
.NRCLRULES AND' GUIDELINES FOR LICENSE EXAMINATIONS -l During.the' administration of this examination the following rulestapply:
- 1. - Cheating on the examination means an automatic denial of your application ,
and 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 ink or dark pencil 2D1y 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 paper provided for answers.
1
.7. Print 1your name in.the. upper.right-hand corner of the first page of gggb section of the answer. sheet. i 'B.- ' Consecutively number,each answer sheet, wr it e "End of Cat egory __"' es i l Tappropriate,. start each. category on a Dgg page, write 2D1% 2D 209 11d2 of the paper,.and write "Last-Page" on the last answer' sheet.
- 9. ' Numberfeach answer as to category and number, for example, 1.4, 6.3. i 30.; Skip at-least ibtgg lines between each answer.
L
- 11. Separate answerLeheets.from pad and place finished answer sheets face down on your desk or table.
'1g; Use abbreviations only if'they are commonly used in facility JJigggiung.
- 13. The point value for each question is indicated in parentheses af ter 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 l to mathematical problems whether indicated in the question or not.
l
- 15. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLANK.
I l
- 16. If parts of the examination are not clear as to intent, ask questions of the eggmingt only.
.17. You must sign the. statement on the cover sheet that indicates that the work is your own and you have not received or been given assistance in completing the examination. This must be done after the examination has been' completed.
i j l i
- 18. When you complete your examination, you shall: l
- a. Assemble your examination as follows:
L (1) Exam questions on top. (23- Exam aids - figures, tables, etc. (3) Answer pages including figures which are part.of the answer.
- b. Turn in your copy of-the examination and all pages used to answer the examination questions.
- c. Turn in all scrap paper and the balance of the paper that you did i not use for answering the questions..
- d. Leave the examination area, as defined by the examiner. If after leaving, you are found in this area while tt.e examination is still in progress, your license may be denied or revoked.
I
p w j i s 52__IVEDBY_DE_ NUCLE 6B_EDWEB EL6HI_DEE86110Nt_ELUIDS&_6NQ' PADE 2 IUEBdDDINedICA-
\
I l t QUESTION 5.01 (1.00) Which of the following post accident containment hydrogen' contributors is dependent on the. radiation field intensity-inside containment for the amount of hydrogen released? (1.0). (
- o. Zr + 2H2O -> Zr02 + 2H2 l
- b. 2H2O -> 2H2 + O2 ,
- c. 2Al + 3H2O -> Al203 + 3H2
- d. Fe + H2O -> Fe0 + H2 QUESTION S.02 (2.00) s
- c. Describe HOW and WHY the core AXIAL flux profile changes from BOL. . l to EOL. (1.0)
- b. HOW does the.above shift in flux affect differential control rod worth in the core? (1.0)
QUESTION 5.03 (3.00) . i Match each of the items in column 1 to the short definitions in ! column 2? (3.0) COLUMN 1 COLUMN 2 l
- a. fast neutrons 1. high energy neut rons . ( >1. D MeV) !
b, activity 2. occur indirectly from fission through fission
- c. delayed neutrons fragment daughter decay
- d. reactivity 3. fractional change in neutron-population per: generation
- o. slow neutrons
- 4. occur directly from the
- f. prompt neutrons fission reaction
- 5. low energy neutrons (<0.63 eV)
- 6. number of disintegrations per unit time of a radioisotope
(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)
pq g - *
- 3 ,
c (gj' % w .1 %[ .. $ 6 1 . f 4 351..IBEDBY_DE_ NUCLE 68_EDWEB_EL6NI_DEEB6I1ONt_ELVIDSt _6ND PAGE 3 '- of LIBEBdQDINedICS: f-'., y; s, QUESTION' 5 04_, . [3.00) Forl eachof the Avents' below, - state 'the or der in which the three; reactivity
*? ! codffic.ients:will-respond (first, second, and. third). . ALSO indicate p~
whetheroesch. coefficient'will.be adding + or:- reactivity during the ~ event. Use allithreeJcoefficients for each' event. (3.0) fo r Rod. drop at, power "i b'. -Turbine"stop valve fails shut at power'
'c. One:recirc pump trips at power LQUE'S TION 5.05: ~-(3.00) .
- a. . Describe,oincluding1 values,;how the BETA of the core can be approximately 0.007 st BOL when no fuel isotope has m. BETA of thats value.' (1.0) b' . Descr'ibe, including values, how the BETA of 'he. core changes from BOL to.EOL. ALSO-include how the fuel composition changes. ( 1. 0 ) .
- c. Which-has aLhighers probability of causing fission: PROMPT or DELAYED.
neutrons? WHY? ( 1. 0 )- f I .4 oQUESTION" -5.06; (1.50) Indicate whether each of the following events would be expected to result in a reactor scram. If so, state'which signal would be the most likely to have initiated the scram.- (1.5)
- a. Inadvertent HPCS initiation at power
'b. Both recirculation pumps trip at 100% power
- c. One MSIV shuts at 90% power
, .d. Main turbine trips at 28% reactor' power 1 .(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)
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7 a
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. - b St _IHE981.9E_ NUCLE 68_E0 WEB _EL6NI_9EEBoIIONt_ELUIDSt_6ND PAGE 4 -{
IBEBdQQXU6UICS- I 1 i o 0 l
-)
QUESTION 5.07 (2.50)
- c. What is the relationship between MAPRAT and MAPLHGR7 (1.0)
-l f
- b. The process computer prints out a MAPRAT of 1.05. ,Is this j acceptable (YES or N0)? .(0,5)
- c. What physical consequence could occur if1the MAPRAT limit is exceeded and under what conditions? (1.0)
QUESTION 5.08 .(2.00) Following a reduction in power from 90%'to 70% with recirculation flow,:
~
HOW and WHY will each of the following change (INCREASE, DECREASE, NO l CHANGE)?
- a. The pressure difference between the reactor and the turbine steam chest. (1.0)
- b. Final feedwater temperature, C'1.0)
QUESTION 5.09 (3.00) The reactor ic operating at 100% power when one SRV fails open.- Describe the response of'esch of the parameters listed below. Include the initial ! change, the trend for that parameter over the next five minutes, and the reason (s).for the response. (3.0) j 1
- c. Indicated Steam Flow (total) f I
- b. Turbine Steam Flow l
- c. Reactor Power l'
QUESTION 5.10 (2.00) A LOCA has occurred along with a loss of offsite power. The diesel generators have started and tied on to th61r appropriate buses. All ECCS pumps.have started. Reactor Pressure is 500 psig. Describe HOW and WHY diesel generator load will very as reactor pressure decreases to 100 psig. (2.0) (***** CATEGORY 05 CON 17NUED ON NEXT PAGE *****) a
St__IUEQBY_DE_UUCLE68_EDWEB_EL6NI_QEE86IlQNt_ELQ1Q$t_6NQ PAGE 5 IBEBdQDYNodICS QUESTION 5.11 (2.00)
\_______/
FLOW ----> 1 2 3 ___________/ \___________
- o. Describe the relationship (>, <, or =) between points 1, 2, and 3 on the above venturi flow element for the following parameters (assume the fluid is incompressible, constant temperature, and no friction loss occurs): (1.5)
- 1. Mass flow rate
- 2. Pressure
- 3. Fluid velocity
- b. How would the above change if fluid friction is considered (as in an actual system)? WHAT HAPPENED to the energy (eccount for the energy change)? (0.5)
(***** END OF CATEGORY 05 *****)
6t__EL6NI_SX1IEdS_QESIGNt_CDUIB9Lt_6ND_INSIBudENI611gN PAGE 6 QUESTION 6.01 (3.50)~ G. . Describe the.flowpath during operation of the RWCU system that places the maximum laad on the_Non-Regenerative Heat Exchanger. HOW MUCH load is on the Regenerative Heat Exchanger.during this-mode (NONE, MODERATE, MAXIMUM)? (2.5) b.- Whatis the limiting parameter when in the above mode and what is done to orevent exceeding this limit? (1. 0 ) - QUESTION 6.02' (1.003-i What temperature problem has been experienced in the.Feedwater System while l operating in the'long cycle cleanup mode during plant startup? Include the cause of the problem. (1.0) QUESTION 6.03 (1.00) { l What are two (2) reasons why dilution of the Offgas stream is important? j J l i QUESTION 6.04 (1.00) ! The OFFGAS TREATMENT MODE SWITCH is in AUTO. Describe what determines whether the Offgas flow is being directed through the charcoal adsorbers or around them. (1.0) ; i 9 1 i l l j i i I i l 1 I I 1 l (***** CATEGORY 06 CONTINUED ON NEXT PAGE *****)
[' .,. . y L 4t__EL6NI_SXSIEdS_DESIGNt_GQNIB9Lt_6ND_INSIBudENI6IIQN PAGE- .7
,LQUESTION. 6.05 (3.00)
- Indic afe wh'etheri es'ch t of l the following are TRUE or. FALSE. If-FALSE,"
explain WHY it;is. false.- (3.0)
.a. Once a LPCI initiation. signal is received, LPCI inj ect ion into thelRPV begins'as soon as-the; injection valves openL(assume proper system operation).
b.. One loop of'RHR may[be placed in' suppression pool cooling any time following-s:LPCI. initiation signal'. c.- ~Alth'ough either' loop'(A or B) of RHR.may be'used for shutdown coolings. B;is the preferred loop. .
- d. With RHR;in Shutdown Cooling,cthere are no interlocks that prevent opening.the RHR.pumpf test. return to the suppression pool valve [F024)'
' and pumping reactor.2 water- to the suppression pool.'[ assume , normal' Shutdown Cooling. lineup initially).
. QUESTION. 6.06' (2.50) a.. How does the design of the CST ensure that approximately 125,000 gallons of dedicated volume'is available'for RCIC/HPCS use? (1.0)
.b. What will cause the-RCIC suction to shift automatically,to its alternate source. TWO (2) conditions required. Setpoints are NOT required. ' INCLUDE any applicab'le time delays or restrictions on valve movements. (1.5).
QUESTION 6.07 (2.50)
- a. What-three (3) conditions will align the control room air conditioning system for charcoal filtration? (1.0)
- b. List five automatic actions.that occur as a recult of reaching one of the'above conditions. (1.5)
(***** CATEGORY 06 CONTINUED ON NEXT PAGE *****)
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' L i Ti__EkeNI_SYSIEdS_DESIGNE_'GQNIB0Lt_eND_INSIBUdgNI611QN PAGE 8=
.f
' QUESTION 6'08'
. (2.00) 4 i
The core,is' designed.to be symmetrical, that is each quadrant of-the core will.be a mirror. image ofLthe others with respect to. fuel and control' rod position.: Why~a're the LPRM; detectors located'in positions 1that do-not
' result.in this same type 1 symmetry and'how'does this. provide adequate
. neutron monitoring 1of.the. core? (2.0):
QUESTION 6.09, , (3.'00) ! s . c.. A CRD has one reed switch for one channel of RPIS that has' failed shut.. How will the operator'know.that the switch has failed 'l (2 required)?. (0.5)
'b. What should:beEdone to allow rod motion to continue'past'the-failed reed switch? (0.5)
- c. How many' rods can be bypassed from the Rod Action Control Cabinets ~
Celectrically or physically, not. administrative 1y.)? (0.5)
' 'd. HowLmany HCU's can beibypassed from the Rod Gong Drive' Cabinet (electrically or physically, notJadministratively)?; (0.5)
- e. How does bypass ing' a -rod at the Rod Gang Drive Cabinet differefrom bypassing a rod at the Rod Action Control Cabinet with regard-to allowing rod movement? (1.0)
QUESTION 6.10 (1.50) The reactor is operating at 100% power when one reactor _ feed pump trips. Describe how the Recire Flow Control System responds to this event. (1.5) fQUESTION 6.11- (2.00) The1 reactor-is operating at 8% power, starting up the.t.urbine generator, when a main condenser pressure switch associated with the Steam Bypass ValvesLfails to O psig. Describe how the plant responds to this failure. (2.0) (***** CATEGORY 06 CONTINUED ON NEXT PAGE *****)
.. . 2- ---__ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ - _ _ _ - _ _ - _ - _ _ - _ _ _____
f
ht__EL6NI_212IEdS_DESIGNt_DQUIBQLt_6ND_INSIBDMENI61198 PAGE 9 QUESTION 6.'12 (2.00) Feedwater Level Control is using Narrow Range Channel A for reactor vessel level control. The reactor is operating at.100% power. A leak occurs in the vcriable sensing line to the A level transmitter (shared by the C level transmitter) which results in a reduced pressure in.that line, Describe how the Feedwater control System will respond with no operator action AND WHY. INCLUDE how and why this event affects continued reactor operation. i
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l ( (***** END OF CATEGORY 06 *****) I
?i__EBOCE09BES_ _NQBd6Lt_6HN9Bdekt_EUEBGEN91_8NQ PAGE 10 BoDIDL9EIG6L_C9 NIB 9L QUESTION 7.01 (2.00)- The Operator "At _ the - Controls" will manually initiate a reactor scram whenever one of WHAT TWO GENERAL CONDITIONS occurs? (2.0) QUESTION 7.02 (3.00) { l
.a. During n plant startup, at approximately what power level is Main ,
Steam lined up to the Moisture Separator Reheaters?- (,0. 5 ) L I
- b. Operation'of the Steam Supply Valves to the MSR's (1 MSS-MOV111/112) must be, closely coordinated between the "at the coritrols" operator and the " BOP" operator. What negative consequences (2) may arise from operating the steam supply valves too rapidly at low reactor power with the generator at low load? _ (2.0)
- c. At approximately what power are the heater drain pumps placed in service? (0.5)
QUESTION 7.03 (2.00)
- n. If all three Instrument Air Compressors are available, HOW MANY should i be running'and WHY? (1.0)
- b. A loaded Instrument Air Compressor tripped due to high discharge air temperature. When can it be restarted (by procedure) and why the restriction? (1.0) l QUESTION 7.04 (2.00)
During Cold Shutdown conditions with the RPV head in place, what are TWO j CONDITIONS that shall be met to minimize temperature stratificatisn which may-cause coolant temperatures to exceed 212 deg F and inadvertent RPV pressurization? (2.0) i 1 j (***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)
% 7.3 .
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','t .. \ .k3 ~c -
Of .Zi__EBQ9EDUBES_=_N98d6Lia8BNDBd6L1_EMEBGENGX_8NDL PAGE. 11.
- 88DIDLQQIC8L_GQNIBQL ,
1 e J" .' ; QUESTION 7,05" .( 2. 50 )- Perithe'EOP's, list.five ' (5)' specific. conditions.that require EMERGENCY RPV DEPRESSURIZATION. -(2.5) r
- QUESTION' 7.06- ' - ( 2 . 0 0 ) s.
s ! Under!what setoof. conditions..is'AOPLOO20, " Alternate Shutdown Cooling,"'
;;initiatedLand: performed? .( 2. 0 )'
'Y;.
1
- QUESTION: 7.07. : (2.00) +
IA scram signal'is received with the reactor at1 power, but-the. control' rods
'do not fully insert;.(several remain.in.theJfull out position).
What
'immediate operator actions are requireds per.AOP-0021," Anticipated Transient ~
<Without Scram?" Useithe! conditional statements below in_your answer.
<'Esch part below may have more than one.subster. (2.0)
- a. IF the main turbine is on line,fTHEN . . .
- b. IF reactor power'-is~above 5% or cannot be-determined, THEN ...
- c. IF all control l rods cannot be inserted beyond 04 BEFORE ...
QUESTION- 7.08 (1.50)
~
What are-three modes of failure, with-regard to the feedwater heating system, that can result in. cooler feedwater reaching the RPV. Assume power operation. ( 1. 5 ) 5 (***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)
.l. 'Zt__EBOCEDUBES_:_NQBd8Lt_8aNQBd8Lt_EUEBGENCY_8ND PAGE 12 88DIDLQQIQ8L_CQNIBQL l ' QUESTION 7.09 (2.50)
- e. What personnel precaution should be taken any time a control' rod is to be withdrawn from a control cell in which there is fuel? (0.5)
- b. What personnel precaution should be taken on the refueling floor prior to demonstrating shutdown margin?- (0,5)
- c. What action should be taken IMMEDIATELY if a large gas bubble is observed coming to the fuel pool surface during refueling. operation and WHY? (1.5)
I QUESTION 7.10 (2.00)
- s. The loss of one RPS bus requires system.isolations to be reset, which system isolation must be reset within a very short period.
of time to preclu'de requiring further operator action? (0.5)
- b. What length of. time is a "very short period of time" per A0P-0010,
" Loss of One RPS Bus?" (0.5)
- c. What action must be taken if the isolation mentioned in part a above is not reset within the specified time? (1.0)
QUESTION. 7.11 (1.00) What two (2)-conditions must be met so that an'IMMEDIATE reactor scram is NOT required during a loss of Normal Service Water? (1.0)
' QUESTION 7.12 (2.50)
- n. With the facility at power,-what actions should be taken prior to evacuating the control room? (2.0) b.- Where should the control room personnel assemble following the evacuation? (0.5)
(***** END OF CATEGORY 07 *****) { _
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- St__eDd1NIAIBoIIVE_EB00EDUBESt_00NDIIIDNSt_6ND_ Lid 1I6I1QN3 :
PAGE_ 13' QUESTION '8.01' (1.50)- ,
=During preparation 1 f or s' reactor ~ plant startup~from Operationalt Condition 3, the. Shift Supervisor'(SS) is informed that LPCI' pump A has failed a surveillance test, but it is probable that the problem can be: corrected within'36 hour's. ; Based upon this in-
- formation, the SS' determines that evenfif repairs takeLlonger he still has17. days.before'he exceeds the time requirement in the Action statement. He also dec' ides to continue the-reactoristertup. . Is
'this decision. correct? Justify your pos it ion.. ( 1.~ 5 )
L e
- QUESTION. 8.02 (1!00)
, Where would an operator 1 find the interpretation on.a Technical 1Specifica-tion requirement.that had required previous interpretation?! - ( 1. 0 ) .
. QUESTION 8.03 '(2.00)
Answer the following with regard to Temporary Change NoticesL(TCNs):
'a. What isLt'he maximum number of TCNs that can be -active' againstT a single procedure? (0.5)
- b. How would the next TCN be written.against a procedure that already had-the maximum number'of TCNs allowed written against it? (1.0) c .- How long are "One Time Only" TCNs effective (maximum)?. (0.5) x
. QUESTION 8.04 (1.50)
-What:are the three (3) levels of management at River _ Bend that may issue ,
"Special Orders"? -(1.5) !
l QUESTION 8.05 (3.00)
- a. What five (5) personnel, by position, are specifically EXCLUDED from ;
being on the Fire Brigade tesm? (2.5)
- b. How does one determine who is on the Fire Brigade for a particular
. shift? C 0. 5) .
.(***** CATEGORY 08 CONTINUED ON NEXT PAGE *****)
, 1
pt__6DdIU1118611Mg_EBQQgQUBg1t_QQNDIIION$t_6ND_ Lid 1I6IlQUE PAGE 14 l QUESTION 8.06 (1.00) Under what conditions, with regard to shift crew composition, may the STA function be performed by one of the other required shift positions? (1.0) QUESTION 8.07 (2.00) An NE0 desires to demonstrate to a trainee how to take local manual control of a motor operated valve. He selects the RHR Heat Exchanger Bypass Valve. The C0F gives permission to the NE0 to take the valve to 1ccal manual and operate it locally. The valve is very difficult to operate manually so the NEO uses a valve " persuader" to assist in operating the valve. The evolu-tion is completed and the C0F is told by the NEO that the valve has been returned to its normal, operable status,
- c. What error was made in valve operation by the NEO and WHY was it improper?' ( 1. 0 ) .
- b. Is the valve in its normal, op gr ab le status? EXPLAIN. (1.0)
QUESTION 8.08 (1.50) The E0Ps and/or AOPs require the use of temporary devices (jumpers, mechanical blocks, etc.) in certain instances. '
- a. Who contr> -s accecs to these j umpers? (0,5)
- b. Where are they kept? (0.5)
- c. When, other than when called for in the applicable procedure, may these temporary devices be used (if at all)? (0.5) l l
1 QUESTION 8.09 (3.00) l
- a. Under what conditions may the Shift Supervisor release a clearance held by a mechanic? (1.0)
- b. What are the six (6) employee classifications designated as Tagging l Officials? (2.0)
(***** CATEGORY 08 CONTINUED ON NEXT PAGE *****)
- - ~
, a , N.
^
j' f I D , ;Di _8DMINISIB6IIVE;EB00EDUBESi_GQNDIIIONS&_6ND_LIMIIoI19NS
, PAGE. 15
- p
-(2'.00)'
! QUESTION 8.10 List fourL(4) of the five. criteria.that the= Emergency Director uses to.
,[ , frecommend! terminating:a1 Site' Area or GeneraliEmergency.. (2.0)
, 4 QUESTION 8.li- 'C'3.00)
- a. Who hasJthe'responsLibility forlmakin'g protective action recommende ' l tionsJto theLlocal authorities l-following anLevent?.:(Include both- ';'
Linitially'and laterLin therevent as'other, functions ~are manned.)_:(1;0)
- b. :
WhatLauthority,do1 River Bend Station pe'rsonnelf(Gulf . States:
~
Utilities) have with' regard to imposing' protective actions >on River Bend: Station ~orithe: surrounding area?' (1.0) LAt-whatoprofected Sh' ole body.ihtegrated: dose Cor' thyroid integrated; c.. dose)71s the minimum recommended' action to:- 4 l '. - shelter the public? , (0.5)
.2. evacuate the area?! C0.5). J NOTE: > Indicate which integrated dose,'whole; body or thyroid, you-are answering.
> QUESTION 8.11 '(1.50) ')
- n. At what-emergency classification level are the OSC.and TSC required to be activated? C0,5)
- b. ' Who has'respons'ib'ility for OSC activation and'also acts as OSC y 1
Coordinator?- :(0.5)
- c. : Where does the Shift Supervisor report to or; remain following. relief .j from Emergency Director responsibilities? (0.5). !
I i
.j c
I (***** CATEGORY.08 CONTINUE 0 ON NEXT PAGE *****) ] I 4
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Dt__6DdINISIBoIIVE_E80GEDUBESt_00NDIIIONSt_6ND_LIMII6IIONE PAGE 16 j 1 I
~ QUESTION 8.13 'C2.00)
- e. What are three (3)Lreactor coolant system 1 leakage detection systems {
that_are required to be operable when operating in Mode 17 ( 1. 5 )-
- b. Can unrestricted reactor ~ operation continue with known UNIDENTIFIED LEAKAGE? Explain. (0.5) f 1
f 1 l i h i t-l l [ l (***** END OF CATEGORY 08 *****) (************* END OF EXAMINATION ***************) .
C
.. ]
NRC LICENSE EXAMIRATION HAND 0lli ; ,L f EQUATIONS, C0ttSTANTS, AND CONVERSIONS 6 = m*Cp *deltaT 6=U*A*deltaT P=Po*10sur*(t) p , p ,e t/T .SUR = 26/T T=1*/p+(p-p)/Kp T=1/(p-p) T = ($-p)/X p p = (Keff-1)/Keff = deltaKeff/Keff p = 1*/TKeff + feff/(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 gajlon = 8.345 lbm = 3.87 liters 1 ft = 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 Hg. Miscellaneous Conversions t I curie = 3.7 x 10tu disintegrations per second 1 kilogram = 2.21 lba 1 horsepower = 2 54 x 103 Btu /hr 1 mw = 3.41 x 105 Btu /hr 1 inch = 2.54 centimeters degrees F o 9/5 degrees C + 32 degrees C = 5/9 (degrees F - 32) 1 Btu = 778 ft-lbf
52__INEDBY_DE_NUGLE68_EDWEB_EL6NI_DEEBoIIONt_ ELD. IQSt_6NQ PAGE' 17' 18E8000168d103 ANSWERS.-- RIVER'8END.1 -87/05/26-GRAVEE, D. i k ANSWER 5.01 (1.00) l b (1.0) REFERENCE River Bend Mitigating Core Damage, pg 6-5 through 6-10 ANSWER 5.02 (2.00) , i
- n. The flux shape changes such that the peak flux moves lower (0.5) in the core. As fuel is burned out, control rods are withdrawn, exposing more fuel, and lowering the flux peak toward the new fuel (0.5).
- b. Differential rod worth ~ increases in the bottom of the core (1.0). '
(DRW decreases in the top portion) REFERENCE River Bend LOTM-TH-4-20-1, pg 4 K/A 292005 K1.09 2.5*/2.6 292005K109 ...(KA'S) ANSWER 5.03 (3.00)
- a. 1, 4
- b. 6
- c. 2 ;
- d. 3 i
- e. 5 l
- f. 4 l Ca- f at 0.5 each)
REFERENCE River Bend LOTM-TH-4.3-0, pg 3 J LOTM-TH-4.7-0, pg 4, 5 i LOTM-TH-4.11, pg 'l I K/A 292001 K1.01 2.,0*/2.1* K1 02 3.0/3.1 K/A 292002 K1.11 3.2/3.3 292001K101 292001K102 292002K111 ...(KA'S) ]
n-a 4
, I i
- S t_ _ Ig g gB r_ Q E_NU C L E 88. E 9 W E B _E L 6NI_9 E E B oII O Nt _f.L UID S t _8 NQ PAGE 18 q
? IBEBdDDYNGUIGH' t ANSWERS -- RIVER BEND 1 -87/05/26-GRAVES, D. i j i l ANSWER 5.04 -(3.00)
'n. Doppler-(-), MTC (- ) , Void C-) !
- b. Void.C+), Doppler C-),.MTC (-)
- c. Void C-),. Doppler C+), MTC C+)
(0.25 for each + or - and 0.25 for the order) I REFERENCE River Bend LOTM-TH-4.16-0 through 4.19-0 K/A 292004'K1.01 3.2/3.2 K1.05L2.9/2.9 K1.10 3.2/3.2 292004K101 292004K105 292004K110' . . . (KA'S)- ANSWER 5.05 (3.00)
- 8. (U235 0.93 X .0064) + (U238 0.07 X .0157) = ~ CORE BETA
.0070 = CORE BETA at BOL 'l (0,1 forneach isotope, 0.2 for each 8, 0.2 for each %)
Accept indicated = values + or - 10%
- b. (U235.0.55 X .0064) + (U238 0.07 X .0157) + (Pu239 0.38 X .0021) =
-CORE BETA EFFECTIVE = .0054 at E00 l I
(0.1 each for isotopes, %'s, e's, Total 8)
- c. Prompt (0.5) because prompt neutrons are more likely to cause FAST fission than delayed neutrone (0,5). !
I REFERENCE' River Bond LOTM-TH-4.14-1, pgs 5-7 K/A 292003 K1.04 2.5/2.5 292003K104 ...(KA'S) 1 m-
i "" . . . . . { St__IBEQBY_9E_ NUCLE 68_E0HsB_ELeNI_QEEB6IION,_EL9101t_eUQ PAGE 19 l IBEBdQRINedICS i ANSWERS --- RIVER BEND.1 ' -87/05/26-GRAVES, D. l ANSWER S 06 (1.50)
~
- a. no.(0.25)'
- b. no (0.26)
- c. yes (0.25) high flux ~ [0.25).
- d. yes ( C'.'2 5 ) high pressure-(0.25)
REFERENCE
. River Bend Operational Transients i 3
River Bend BWR-6 Transients ANSWER 5.07 (2.50)' e .- MAPRAT = MAPLHGR (actual') / MAPL'GR H (limit) (1.0) b, No-(0.5) i c.- The clad temperature could exceed 2200 deg F (0.5) during a LOCA l or core uncovery (0,5). REFERENCE River Bend LOTM-TH-3.10-0 pg 2 293009 K1.11 2.8/3.6, K1.13 3.1/3.6 293009K111 293009K113 ...(KA's) ANSWER 5.08 (2.00).
- a. Decreases (0.5). With less steam flow there is less pressure drop in the steam lines (0,5) and steam chest pressure is closer to reactor pressure.
- b. Decreases (0.5). Less extraction steam from the turbine to heat :
the feedwater (0,5). 4 REFERENCE j River Bend LOTM-IC-9-0, pg 4, Figure 1 i BWR Transients 239001 A1.01 3.6/3.6 259001 A1.02 3.2/3.3 239001A101 259001A102 .,..(KA'S) e
l 5t__IBE98Y_DE_N99LEeB_EDWEB_ELoNI_QEEB6I19Nt_ELU1QSt_6NQ PAGE 20' l IBEBd201Nad19A ANSWERS -_ RIVER BEND 1 -87/05/26-GRAVES, D. l ANSWER 5.09 (3.00) Indicated steam flow' initially increases'(0.3) due to the SRV drawing more steam off the reactor (0.3). As reactor pressure decreases, the turbine control valves close down to' control _ pressure (0.3) resulting in reduced turbine steam flow (0.3). Reactor power initially decreases (0.3) due to the depressurization~CO.3). Turbine steam flow decreasing causes a slight decrease in FW temperature (0.3) causing reactor power to begin increasing , cgain (0.3)'which causes-the pressure control system to increase turbine ; and total steam flow (0.3). Final' conditions will be slightly_ higher ] reactor power with the steam flow shared between the turbine and the SRV OR the reactor will scram on high power (0.3). REFERENCE
' River Bend BWR-6 Transient Index 292000 K1.22 3.5/3.6 239002 A1.06 3.7/3.8 A1.07 2.9/3.0 A1.09 3.1/3.3 239002A106 239002A107 239002A109 292008K122 ...(KA'S) . ANSWER 5.10 (2.00) l' At 500 psig, the low pressure inj ection systems are not inj ect ing any l 1 l water, so flow is at a minimum. With flow at a minimum, the pumps will be requiring a minimum amount of current from the EDG (1.0). As pressure decreases, the flow will increase, requiring more load from the EDG's (1.0)
REFERENCE River Bend LOTM-TH-1.4-0 i LOTM-19-1 l LOTM-20-0 l 291004 K1.05 2.8/2.9 291004K105 ...(KA'S)
.Sz__IMEQBY_QE_NUCLESR_EQWEB_EL8NI_QEE36Il0Nt_ELV101t_6NQ PAGE 21 18E80D01N6d192-
~
-ANSWERS -- RIVER BEND.1 -87/05/26-GRAVES, 0.
l ANSWER 5.11 (2.00) l
- c. 1. 1 = 2 = 3_(0.5) l
- 2. 1 > 2< 3 (0.5)- '
- 3. 1< 2 > 3 (0.5)
- b. The pressure at 3<~1 (0.25). The difference in pressure is accounted for by the generation of heat (0.25) due to fluid friction.
REFERENCE River Bend LOTM-TH-1.1-0, pg.16 LOTM-TH-1.2-0, pg 8 ) d 291002 K1.01'2.4/2.5 291002K101 ...[KA'S)' 1 l 1 i
41__ELoNI SYSIEUS_DEEIGNt_00BIBQLt_o80_INSIBUDENI6IlQN PAGE 22 ANSWERS -- RIVER BEND 1 -87/05/26-GRAVES, D. ANSWER '6.01 (3.50)
- a. 'RWCU. flow will be taken from the RR loops and RPV [0.25), through the RWCU pumps (0.25), through the RHX (0.25), through the NRHX (0.25) '
through the filter /demin (0.25), through the-flow-control valve (0.25) to either.the condenser (0.25) or radwaste (0.25). The RHX is under no load ( 0. 5 ) . - Accepted a less detailed flow path. The RHX may be under moderated load if not all flow is being ~ rejected.
- b. NRHX RPCCW outlet temperature (0.5)
Nestrict the RCS flow rate to prevent exceeding (0.5) REFERENCE River' Bend LOTM<6-1, pg 12 K/A 204000 K1.01 3.1/3.3 K).02 2.9/3.0 '
.K1.06 2.8/2.8 K1.07 2.6/2.7 A2.12 2.7/2.8 204000K10'/ 204000K106 204000K102 204000K101 204000A212 ...(KA'S)
ANSWER 6.02 (1.00) Thermal stratification in the feedwater line (0.5) due to RWCU backflow 9 rom the mixing tee back to the condenser (0.5). REFERENCE River Bend LOTM-13-1, pg 7 K/A 259001, K1.03 2.7/2.9 ; 259001K103 ...(KA'S) ANSWER 6.03 (1.00)
- Prevent combustion (0,5) - Reduces Maximum r ecomb iner 'tempe r at ur e (0.5)
REFERENCE River Bend LOTM-15b-0, pg 4 K/A 271000 K4.04 3.3/3.6 271000K404 ...(KA'S)
6t__ELeNI_SISIEdS_QESIONt_CONIB0Lt_oND_INSIBudENIoIIQN PAGE 23
. ANSWERS -- RIVER BEND L -87/05/26-GRAVES, D.
ANSWER 6.04 (1.00) If~the post treatment rad monitor (either channel) has'a high radiation clarm, the adso'rbers are in service and the BPV will be closed (1<0). REFERENCE River Bond.LOTM-15b-0, pg 8 K/A 271000 A2.04 3.7/4.1 A3.07 3.4/3.6 ; 271000A307 271000A204 ...(KA'S) ANSWER 6.05 (3.00)
- c. True (0.5)
- b. False (0.5). RHR heat exchanger bypass valve cannot be shut for 10 minutes following the initiation signal (0.5). {
- c. False (0.5). -A is the preferred loop because of its connection to the RCIC head spray line (0.5).
- d. True (0.5).
REFERENCE River Bend LOTM-20-0, pg 8 through 11 K/A 205000 K1.01 3.6/3.6 A2.10 2.9/2.9 K4.05 3.6/3.7 K/A 219000 K4.03 3.8/3.8 219000K403 205000K405 205000K101 205000A210 ...(KA'S) ANSWER 6.06 (2.50)
- a. All other systems supplied by the CST take a suction at a higher level in the CST than do RCIC and HPCS (1.0),
- b. CST low level (0.5) ;
Suppression pool high level (0.5) if no RCIC isolation present (0.2) l Occurs after a 2 second time delay (0.2) l CST supply valve shuts when the suppression pool suction reaches the I full open position (0.13 ] REFERENCE River Bend LOTM-21-0 pg 4, 19 K/A 217000 K1.01 3.5/3.5 1
t L ' '6t__EL6UI_SYSIEUS_DESIGNt_00NIBQLi_6ND_INSIBudENI6IIQU PAGE 24
-ANSWERS -- RIVER-BEND 1 -87/05/26-GRAVES, D.
L 217000K101 ...(KA'S)
]
4 ANSWER 6.07 .(2.50) a.- -- LOCA signal ,
- High Radiati'on on.the air inlet
- Manual; initiation ;
(3 required at 0.33 each) ., {
- b. - Dampers from local outside air to charcoal filters open
- One or both charcoal filter units start .)
- Outside air inlet to' Air Handling Units close 1
- Control-Room purge. exhaust dampers close ;
- Exhaust damper from kitchen closes
- Exhaust damper from toilet closes (5 required at 0.3 each)
REFERENCE River Bend LOTM-31d-0, pg 14, 15 K/A 288000 K1.05 3.3/3.6 A2.03 3.5/3.7 288000K105 288000A203 ...(KA'S) ANSWER 6.08 (2.00) Each location without a LPRM. string has a representative string in one of. ; I the other quadrants (1.0) such that mirror image.and rotational symmetry of power. level monitoring exists across the core as long as the control rod and fuel symmetry remains (1.0). REFERENCE River Bend LOTM-IC-3-0, pg 3 K/A 215005 K1.04 3.6/3.6 1 215005K104 ...(KA'S)
Et__EL6NI_SYSIEUS DESIONt_C9 NIB 9Lt_6ND_INSIBudENI6IION PAGE 25 ANSWERS -- PIVER BEND 1 -87/05/26-GRAVES, D. I ANSWER 6.09 (3.00)
- a. A rod block will be received (0.25) aleng with a CHANNEL DISAGREE light (0.25) on the Rod Motion Matrix.
- b. Substitute data from the channel of RPIS that is functioning (0.5).
- c. 8 (0,5)
- d. 1 (0.5)
- e. Bypassing a rod at the RGDC prevents the drive signal from the RGDC from being sent to that HCU, therefore rod motion is prevented (0.5).
Bypassing a rod from the RACC makes it invisible to the Rod Pattern Controller, but will still move in the norma) fashion (0.5). 1 REFERENCE River Bend LOTM-IC-7-0, pg 31-33, 40, 47, 48 K/A 201005 K1.05 3.6/3.6 K1.06 3.3/3.3 K6.02 3.2/3.2 201005K602 201005K106 201005K105 ...(KA'S) ANSWER 6.10 (1.S0) When reactor level decreases to level 4 (0.5), the Flow Control Valve will run back to 48% flow (0.5) and the flow controllers will trip to manual (0,5). REFERENCE River Bend LOTM-IC-8-0, pg 16 K/A 202002 K6.04 3.5/3.5 202002K604 ...(KA'S) ANSWER 6.11- (2.00) l The bypass valves trip shut (0.5). Reactor pressure will increase due to lack of steam loads (0.5) which in turn will cause reactor power to increase (0.5) and the reactor will scram on either high flux or high pressure (0.5). REFERENCE I River Bend LOTM-IC-9-0, pg 6 K/A 241000 K6.05 3.4/3.4 214000K605 ...(KA'S)
I i 61__EL6HI_SYSIEdS_DESIGNt_GONIBQLt_6HD_INSIBudENI6IION PAGE .26 ANSWERS -- RIVER BEND 1 -87/05/26-GRAVES, D. 1 ANSWER 6.12 (2.00) The transmitter will sense a lower level in the reactor due to the reduced pressure in'the variable leg (0,5). Channels A and C will indicate low. The FWCS sees'a need for increased flow (0.5) and opens the FWCV more to increase flow and raise level (0.5). Level continues to increase until the reactor scrams on high level (0.5). REFERENCE i 1 River Bend'LOTM-IC-10-1, pg 20, Figure 2 .K/A 259002 K1.03 3.8/3.9 K6.05 3.5/3.5 259002K605 259002K103 ...(KA'S) 2
3 Zi__EEDGEDUBES_:_NDBdekt_6BNDBdekt_EUEB9ENCY_6NQ PAGE 27 3 1 86DIDLQQ10eL_90NIBQL ANSWERS'-- RIVER BEND 1- -87/05/26-GRAVES, D. I i ANSWER 7.01- (2.00) '
- A scrom setpoint is exceeded and an automatic scram did not occur (1.0)
. Plant conditions are approaching an. unsafe condition and a manuel reactor scram will mitigate the consequences of this condition (1.0) i
. REFERENCE.
River Bend AOP 0001, Reactor Scram, Rev 3, pg 2 K/A'295005 Generic 11 4.3*/4.5* 295006G011 ...(KA'S) , n ANSWER 7.02 (3.00)
- n. 15% (accept 10 - 20%) or 100 - 200 MWe (0.5)
- b. Rapid opening of the steam supply valves at low reactor power can interfere with hestup rate and reactor power level control which may result in a reactor thermal flux scram (1.0). At low generator loads, opening the valves too fast may result in a large load decrease and subsequent reverse power trip of the generator (1.0).
- c. 50% (accept 40 - 60%) (0.5)
REFERENCE River Bend SOP-0010, MSR and FW Heaters Extraction Steam and Orsins, Rev 2 Pg 10, 10 a , 11 K/A 239001 K1.03 3.4/3.4 K1.05 2.8/2.8 K/A 259001 K1.17 2.4/2.4 239001K103 239001K105 259001k117 ...(KA'S) ANSWER 7.03 (2.00)
- c. . 3 (0.5) to prevent the internals from becoming galled while the compressor is left idle (0.5).
- b. It can be' restarted after it has cooled to ambient temperature (0,5).
Introducing cool water to the hot cylinder walls may crack them (0.5). REFERENCE River Bend SOP-0022,- Instrument Air System, Rev 2, pg 2, 2a K/A 295019 Generic 7
vc I l Zl__EB9GED9BES_ _NQBuelt_6BNDBdekt_EdEBGENCX_oND PAGE 28 BoDIQL901 col _G9NIBQL i - 1 ANSWERS -- RIVER GEND 1 -87/05/26-GRAVES, D. l 1
-295019G007 ...(KA'S) i ANSWER- 7.04 (2.00) ] ;
- 1. - At least one shutdown cooling loop should be in operation, j
~
l
- 2. RPV water level shall be maintained greater than 75" (using Shutdown Level . Instrumentation when RR pumps are secured).
- 3. 'In the event' forced circulation is unavailable (RR pumps off) and j
-water level.is at.or below the Minimum Natural Circulation Level for any reason, then periodic monitoring of vessel metal temperatures above and below the intended water level should be initiated.
(2 required at 1.0 each) REFERENCE. River Bend SOP-0031, RHR, Rev 3, pg 4a K/A 205000 KS.03 2.8/3.1 K6.03 3.1/3.2-K6.04 3.6/3.6 205000K503 205000K603 205000K604 ...(KA'S)
i s
~
Zt- EB9CED9BES_ _NDBdebt BBN9Bdebt EMEBGENGY_8NQ PAGE 29
-86DIQLQQIC8L_GQNIB0L ANSWERS -- RIVER BEND 1 -87/05/26-GRAVES, 0. -
l
. ANSWER 7.05 .(2.50)
- RPV flooding is required,and < 7 SRV's are open.
~
. Suppression poo1 temperature and RPV pressure cannot be restored and s ,'
maintained below the Heat Capacity Temperature limit.- ,
- Orywell temperature cannot be' maintained < 330 deg F. . i
- Suppression Pool water level cannot'be maintained above the. Heat Capacity 1 Level limit or-below the Suppression Pool load limit.
- Secondary containment temperature, radiation levels, or water leve'Is in more than one eres exceed the. Maximum Safe Operating Limits and a primary system.is' discharging into a Secondary Containment 1 Area.
- RPV pressure is.too high to permit available injection systems, subsystems, or alternate inj ect ion- subsystems to inject adequate flow into the.RPV. j
- Containment temperatures cannot be maintained below 185~deg F. ,
- Containment pressure reaches 19.7 psia.
(5 required at 0.5 each) REFERENCE i River Bend E0P-0001, RPV Control, Rev 6, pg 14 K/A 218000 Generic 15 4.2*/4.4* K/A 295025 Generic 11 4.2*/4.3* 218000G015 295025G011 ...(KA'S) ANSWER 7.06 (2.00) { l RHR shutdown cooling mode cannot be established (0.5) and the RPV can no ' longer be cooled down by depressurization (0.5) and RPV temperature must be' reduced (0,5) and/or the RPV must be maintained in a cold shutdown condition (0.5). REFERENCE l River Bend AOP-0020, Alternate Shutdown Cooling, Rev 1, pg 2 ; K/A 295021 Generic 11 3.6/3.8 ; 295021G011 ...(KA'S) { i i i i l 1 l l J
bi . 5 s, F i : 't .[* . 7
.o ZiL_EBQQEDVBEl_:_NQBd6Li_6BNQBd8Lt_EMEBQENQY_6NQ' PAGE- 30
%t. du , . xB8Q10LQQ1Q8L_QQNIh0L m
"* -87/ 0 5 / 26-G R AVES , . D'. '
/ANSWERSi-- RIVER BEND.1 -
r
~ ' '
p' ' ANSWER. 7.07 (2.00) by ~ L' .a. .... japidly reduce' reactor recirculation flow'by transferring.the RRl pumpsLto.. slow speed.(0.5):
- b .L ... trip the RR pumps.(0.5).
*.,"s :c . ..'..=. suppression pool: temperature reaches 110 deg'F'(0.25), THEN inj ect.
~
.bor.on'with SLC1(0.2S).
- a. Prevent.automst'ic1 initiation of ADS (0.125).
1.. 2 .1 Use one SLC pumpg(O'.'125). 3R Inject the entire tank. contents, THEN shutdcwn the SLC pumps
-(when i nd i'c at e d level reaches O gallons)-(0.125).
~4.' ' Confirm auto isolation br manually isolate 1RWCU:(0.125).
lREFERENCEL River Bend A0P-0021, Anticipated' Transient Without Scram, Rev 0, pg-3 K/A 295015- Generic:10'
,' 295015G010. ...(KA'S):
TANSWER', 17.081 (1.50)
. Closing of'an. extraction, steam isolation valve to the heater (0.5) c-- Hester string iso lat i'on ~ ( 0. 5 )
- Hester string bypassed (0.5).
' REFERENCE
' River Bend AOP-0007,-Loss of Feedwater Heating, Rev 2, pg 2 K/A'295014 AA2.03 4.0/4.3*
295014A203 ,...(KA!S) s l h
f
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L Zt__EBQQEQVBg3_ _NQBd6Li_6BNQBd6Lt_gdgBQgNQX_6NQ PAGE 31 B6DIDLQQ196L_CQNIBQL 1 4 s. ANSWERS -- RIVERJBEND 1 -87/05/26-GRAVES, D. i } v 4 j.
.] .
, ANSWER 7.09 (2.50) j J
'a. Ev'acuate the :eactor line of sight (0.5).
b.- Evacuate the refueling floor-(0.5).
.c. Evacuate lthe area'(0.5). The gas' bubble could be-fission product gases released'from a damaged fuel assembly (1.0).
REFERENCE River-Bend FHP-0001,' Control of Refueling Operations, Rev 2, pg 3, 4 q K/A 234000 Generic 1 3.4/3.8 Generic 10 2.9/3.5 234000G001 234000G010 ...(KA'S) a ANSWER 7.10 (2.00) l
- e. RPCCW (0.5) l
- b. .One' minute (0.5) c .- Trip both recirculation pumps (1.0) !
REFERENCE f'l River Bend AOP 0010, Loss of One RPS Bus, Rev 2, pg 2,4 K/A 295020 AK1.01 3.7/3.9 Generic 10 3.6*/3.5* 295020G010 295020K101 ...(KA'S) ANSWER 7.11 (1.00)
- The main turbine is NOT on the line (0.5).
- Turbine BPV are NOT being used to control reactor pressure (0.5).
REFERENCE River. Bend'AOP 0009, Loss of Normal Service Water, Rev 2, pg 4 V/A 245000 Generic 15 3.4/3.7 245000G015 ...(KA'S)
~- Z A __EB Q C E Q U B E 2_: _N D B d a k t _ o B N D B b 8 L t_ E N E B Q E N Q X _6N Q PAGE 32 p B6019690106L_G9 NIB 96 ANSWERS -- RIVER' BEND 1. -87/05/26-GRAVES, D.
ANSWER 7.12- (2.50)_ e- 1. Arm and depress all four manual scram buttons.
- 2. Mode Switch to SHUTOOWN.
- 3. Verify control rods fully inserted.
- 4. Initiate HPCS, LPCS, and RCIC.
- 5. Close the-MSIV's (5 at 0.4 each)
- b. Division I Remote Shutdown Panel (0.5)-
REFERENCE , AOP-0031, Shutdown from Outside the Control Room, Rev 3, pg 6 i' K/A 295016 GENERIC 10 3.8*/3.6* 295016G010 ...(KA'S) , l
p?: at__6DdINISIB6IIVE_EBQCEDUBEHt_GQNDIIIONSt_6N9_LIdII6IIONS PAGE 33
' ANSWERS -- RIVER BEND 1 -87/05/26-GRAVES, D.
ANSWER. 8.01 (1.50) No (0.5). Entry into en Operational Condition or other specified condition shall not be made unless the conditions for the LCO are met without reliance on provisions. contained in the ACTION require-- ments (1.0).
-REFERENCE River Bend Technical Specifications, 3.0.4 and 3.5.1, K/A 203000 Generic 11 3.6/4.5*
203000G011 ...(KA'S) ANSWERJ 8.02 (1.00) There are interpretation letters included in front of the Technical' Specifications (1.0). REFERENCE River Bend Technical Specifications K/A 294001 A1.03 2.7/3.7-294001A103_ ...(KA'S) ANSWER 8.03 (2.00)
- n. 3 (0.5)
- b. The next TCN would have.to supersede one of the previous'TCNs in its f entirety or it would not be allowed (1.0).
- c. 14 days (0.5)
REFERENCE River Bend ADM-0003, Development, Control, and Use of Procedures, Rev 11, pgs 10, 12 K/A 294001 A1.01 2.9/3.4 294001A101 ...(KA'S)
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'at__8DdINISIB6IIVE_EBQQEQUEESt_QQNDIIIQNSt_eUQ_LIMIIeIIQNS PAGE' 34 i 1
' ANSWERS - . RIVER BEND 1 -87/05/26-GRAVES, D. I l
1 ANSWER- 8.04 (1.50) l Plant Manager, Assistant Plant Managers, Section Supervisors (0.5 each) REFERENCE River Bend'ADM-0003, Development, Control, and Use of Procedures, Rev 11,. pg'18 K/A 294001'A1.03 294001A103 ...(KA'S) ANSWER 8.05 - (3.00)
- n. SS, C0F, STA, At the Controls (ATC) Operator, 1 NEO C5 at 0.5 each) b '. Members are designated each shift in the Control Room Log Book-(0.5)
REFERENCE
' River Bend ADM-0022, Conduct of Operations, Rev'8, pg 11 294001A103 ...(KA'S)
ANSWER 8.06 (1.00) t The SS or an on-shift SRO may fill the STA's role if 5 licensed operators are on shift (0.5) and the individual meets the STA' qualifications per the Technical Specifications (0,5). f REFERENCE River Bend Technical Specification Table 6.2.2-1 K/A 294001, A1.03 2.7/3.7 294001A103 ...(KA'S) I
At__8DdINISIBoIIVE_EB9CEDVBESt_CQNDIII9NSt_6ND_ lid 1I6110N3 PAGE 35 l
' ANSWERS.- , RIVER BEND 1 -87/05/26-GRAVES, D.
I, i ANSWER 8.07 (2.00)
- c. The use of valve persuaders ~will be restricted to manually operated valves only. They shall not be used to manually position motor operated valves. (1.0) i
- b. Local manual operation of. Safety Related motor operated valves will i cause the valve to be declared inoperable (0.5) until operability can be proven by stroke testing (0.5).
REFERENCE River Bend ADM-0022, Conduct of Operations, Rev 8, pg 14 K/A 291001 K1.00 3.4/3.5 K1.09.2.7/2.7 291001K108 291001K109' ...(KA'S) 4 l' ANSWER 8.08 (1.50) i o. SS'(0.5)
- b. Locked storage in the control room emergency locker (0.5). ;
- c. They shall not be used for anything other than their intended function in the applicable AOP/EOP (0.5).
REFERENCE River Bend ADM-0022, Conduct of Operations, Rev 8, pg 18 K/A 294001 A1.11 3.3/4.3* l 294001A111 ...(KA'S)
, ANSWER 8.09 (3.00)
- a. In emergencies (0.2) where the individual holding the clearance is not available (0.4) nor is his supervisor available (0.4).
< b. - Operations Supervisor !. - Assistant Operations Supervisor
- Shift Supervisor
- Control Operating Foreman
- Nuclear Control Operator
- RO/SRO certified Senior Nuclear Equipment Operator (6 at 0.333 each)
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- ~
- - ',
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1
- .~-:, .
s' , Bi_ioDdINISIB8IIYE_EB9CEDUBESt-QQNQ1IIDNSi_8ND_ lib 1I8IIQNH PAGE' 36 ANSWERS -- RIVER._ BEND.1 -87/05/26-GRAVES,.D. (
' REFERENCE- '
- River Bend:ADM-0027,'Rev 4, pg-3, -
8
'K/A,294001 Kit,02 3.9/4.5*-
/294001K102- ..;(KA'S).'
i
. ANSWER- 8.10: -(2.00) 4
-The reacto,# is.in cold, shutdown, is in a s' table, safe configuration; and- j adequateLeore co'oling istavailable.
< <- Excessive. releases of~' radioactivity to the. environment.have been H
{ terminated -and Eno f urther ' potentiali f oc _ significant radiation releases exists ~ i Radioactive contamination in-the atrosphere"or in1 waterways is at or near
'
- background , levels which~are acceptable to state. guidelines.
-ETerminating the'em'ergency.will not impact any offsite protective actions? l which1maysbe in progress..
- The: state.of Louisiana,Lthe. local'-' parishes, and the'NRC concur in !
terminating =the emergency.: l (4 required _at2 0.5-each) REFERENCE ~
-RiversBend'EIP-2-005, Genera 1' Emergency, Rev 3, pg 8 K/AL294001'A1.16 2.9*/4'.7*
294001A116. ...(KA*S)' t
=
. I q
5
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.a t _ _6 D dINI S I B 6II VE _ E B O C E D U B E S t _ C O N D III Q NS t _6N D _ L IMII 6IID N A - PAGE. 37 ANSWERS - ' RIVER BEN 0'1 -87/05/26-GRAVES, D.
ANSWER '8.11 (3.00) c .; initially - Emergency Director (0.5) Inter - Recovery Manager (0.5) b.. GSU hae.no authority beyond the boundaries of the River Bend eite with regard to imposing protective. actions (1.0).
- p. c. . -1. Whole body >:1.to < 5. Rem Thyroid > 5 to < 25 Rem (either at 0.5)
- 2. Whole body > 5 Rem !
Thyroid > 25 Rem (either at 0.5) REFERENCE River Bend EIP-2-007, Protective Action Recommendation Guidelines, Rev 5, l pg'3 K/A 294001 A1.16 2.9*/4.7* 294001A116 ...(KA*S) ANSWER B.12 (1.50)
- n. Alert (0,5) i
- b. Mechanical Maintenance Supervisor ( 0. 5 ) .
- c. Control Room (0.5)
REFERENCE River Bend EIP-2-016, Operations Support Center Activation, Rev 2, pg 2 EIP-2-018, Technical Support Center Activation, Rev 3, pg 3 K/A 294001 A1.16 2.9*/4.7* 294001A117 ...(KA'S) 1 L'
( k l
. i St-_6DdlNISIBollyg_P8QQgQQBgSt_QQUQlllQN$t_6NQ_LidlI6IlQU$ PAGE' 38 :
\
ANSWERS -- RIVER BEND 1 -87/05/26-GRAVES, D. I I l ANSWER 8.13- (2.00) {
- c. - Drywell Atmospheric Particulate
- Drywell and Pedestal floor sump ~ drain flow- .]
- Either the Drywell air cooler condensate. flow rate' monitoring system J or the drywell atmosphere gaseous radioactivity monitoring system 1 (3 at 0.5 each)
- b. Yes (0.25) if it is less t.han the allowable limit of'5 gpm (0.25).
REFERENCE River Bend Technical Specifications 3.4.3.1, 3.4.3.2 K/A 22300*. Generic 5 3.3/4.1 Generic 11 3.3/4.2* 223001G005 223001G011 ...(KA'S) l 1 l
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