IR 05000395/1997300
| ML20199B314 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 01/14/1998 |
| From: | Munro J, Peebles T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20199B302 | List: |
| References | |
| 50-395-97-300, NUDOCS 9801280230 | |
| Download: ML20199B314 (170) | |
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LU, S.- NUCLEAR REGULATORY--COMMISSIO : REGION II-Docket No,-: 50-395-License No.: . NPF-12 , i
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- Report Nos.: 50-395/97-300-l Licensee: South Carolina Electric & Gas Company
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Facility: Virgil C Summer Nuclear Station >
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Location: Jenkinsville SC Dates: Operating Tests' December 1 - 5, 199 Written Examination December 12,1997 "
, Examiners: Y e dda ////[ff~
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JohnMunro, Chief %1censeExaminer-Richard S, Baldwin, License Examiner , Ronald F. Aiello, License Examiner Stephen L. McCrory. License Examiner (RIV) Larry Mellen, Reactor. Inspector
- Approved by: /-// f f ..
Thomas A. Peebles, Chief, , Operator Licensing and-Human " Performance Branch Division of Reactor Safety .
s Enclosure'l 9901290230-990114 T . 4 POR ADOcK 05000395 +
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. l EXECUTIVE SUMMARY Virgil C. Summer Nuclear Station NRC Examination Report Nos. 50-395/97 300 During the period December 1 - 5. 1997 NRC examiners conducted an announced operator licensing initial examination in accordance with the guidance of Examiner Standards. NUREG-1021. Interim Revision 8. This examination implemented the operator licensing requirements of 10 CFR S55.41 and S55.4 Doerations
* Control room activities were observed during the examination validation week and examination administration week. The operators were found to be attentive and professional in their duties (Section 01.1).
' Eight Reactor Operator (RO) candidates received written examinations and operating tests. The licensee administered the written examination on December 12. and the NRC administered the operating tests December 1 - 5, 1997 (Section 05.1).
- In general, the examiners found that the as-submitted examination was roarginally acceptable. The examiners ic'entified the following areas as requirine staff attention or improvement: plausibility of written question distractors, sample plan development, and problem solving character.stics for simulator scenario events (Section 05.2).
- Candidate Pass / Fail R0 Total Percent Pass 8 8 100%
Fail 0 0 0%
= The ex6 miners identified potential generic knowledge weaknesses in the following areas: automatic protective actions for LOCA. method for tripping the reactor from outside the control room. Service Water sj am operation. SI logic operation. Reactor Building cooling operation, and E0P actions and bases (Section 05.3).
- The examiners identified opecating test performance weaknesses in the following areas: TS bases, dase limits, calculation of reactor vessel head venting time, corrective action response for failure of system and component automatic actions, diagnosis of plant conditions based on plant indications. and crew communications (Section 05.3).
Enclosure 1
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. The examiners identified a generic strength in the operators implementation of the facility licensee's STAR program (Section 05.'). . No violations or deviations were identifie \
Enclosure 1
. Reoort Details Summary of Plant Status During the period of the. examinations the Unit was at approximately 100 percent power.- 1. Doerations 01 Conduct of Operations 01.1 Control Room Observation During validation and administration of the examination, the examiners observed the conduct of the operators in the control room. The R0s were attentive to evolutions in progress. The SR0s limited personnel access for official busir.ess only, which contributed to a quiet professional atmospher Communicatico standards were adhered to and the operators appeared attentive to evolutions in progres Operator Training and Qualifications 05.1 General Comments NRC examiners conducted regular, announced operator licensing initial examinations during the period December 1 - 5. 1997. NRC examiners administered examinations developed by members of the Virgil C. Summer training staff, under the requirements of an NRC security agreement, in accordance with the guidelines of the Examiner Standards (ES). NUREG-1021. Interiir. Revision 8. Eight R0 license applicants received written examinations and operating test Eight candidates passed the examination. Five of the eight candidates passed the examination but exhibited weaknesses. Four of these five candidates demonstrated weaknesses on the written examination. One of these four candidates also demonstrated weakness on the JPM portion of the operatina test. The remaining candidate of the five also demonstrated weakness on the JPM portion of the operating tes Candidates were considered to have passed but exhibited weakness if they received an unsatisfactory grade on any one administrative topic area, completed only 80 percent of the JPMs successfully, or received a grade of 1.8 to 2.0 on any one competency during the dynamic simulator examinations. Candidates were considered to have passed the written examination but exhibited weakness if they receive a grade of 80 - 82 percent. Detailed candidate performance comments have been transmitted under separate cover for management review and to allow for appropriate candidate remediatio Enclosure 1
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05.2 Pre-Examination Activities a. Scope The NRC reviewed the licensee's examination submittal using tne criteria specified for examination development contained in NUREG-1021. Interim Revision 8. This examination represented the licensee's first attempt at developing written examinations and operating tests for the NRC's initial operator licensing proces . b. Observations and Findinas The licensee developed the written examination, one JPM set, and four dynamic simulator scenarios, including one back-up scenario, for use during this examination. All materials with the exception of the operating test outline were submitted to the NRC on time. NRC examiners reviewed, modified, and approved the examination pria to administration. The NRC conducted an on-site preparation visit during the week of November 17, 1997, to review and validate the examination materials and familiarize themselves with the details required for examination administration. Although the training staff was very responsive to the examiners' comments, significant effort was required to modify the examination materials to meet the criteria set forth in NUREG-1021 Interim Revision (1) Written Examination Development The knowledges and abilities (K/As) selected for testing on the initial sample plan submittal were not evenly distributed as required by NUREG-1021. Three K/A category tier totals for plant systems recommended sampling no topic areas. Also, although the facility training departme.t representatives indicated the sample plan topics were chosen systematically, NRC review of the licensee's selection methodology could-not confirm all aspects of the process. In the future, the process for licensee development of the sample plan needs to be more clear and scrutable in this regard.
, The NRC examiners reviewed and validated the written examination in a period of approximately five weeks including parts of the preparation and examination week Although the examiners found many question subject areas were of high quality, the examination contained numerous deficiencies that were similar in scope and nature to the deficiencies that have been noted at other facilities on the first attempt at developing the NRC licensing examinations. These deficiencies resulted in changes to approximately 79 questions with 51 of these-changes categorized as significant. The following is a partial listing of some of the problems note Enclosure 1
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(a) Approximately forty-five questions were' found to contat'1 distractors classified as' ~ specific determiners." Specific determiners-include: options which can be judged correct or incorrect without referencing the stem implausible distractors, or a correct option that differs from the distractors in style or terminolog (b) Eight questions contained distractors which were potential additionally correct answers. Four questions as written had potentially no correct answe (c) Three questions were replaced for low discriminatory value or significant overlap with other examination test item (d) Technical errors were noted in four question (e) Approximately 29 questions were reclassified from "significantly modified" to " bank" question (2) Operating Test Development The NRC reviewed and validated all portions of the operating test November 17'- 22, 1997. using the Virgil C. Summer Nuclear Station simulator and walking down inplant JPMs. In general, the JPMs were considered acceptable for evaluation of the candidates' system-related knowledge and abilities, and at an appropriate level of di fficulty. One JPM was substantially revised due to the inaccessibility of its in-plant location (high radiation area) and minor changes were made to five other JPMs to increase their discriminatory value. However, approximately 30 percent (8 of 28) of the Category A and B pre-scripted questions were inappropriate direct look-up or simple memory questions. The examiners considered the revised questions, rewritten by the fdcility's examination team, to be very good test items for evaluation of the candidates' -understanding of the systems' referenced K/A The examiners considered the facility proposed simulator scenarios marginal in discriminatory value. Although the scenarios exercised the candidates on the minimum number of required evolutions, failures and transients as prescribed on form ES-301-5. " Transient and Event Checklist." the examiners considered the scenarios deficient with regard to analysis and problem solving events. -Adequate scenario coverage for all competencies and rating factors per Form ES-301- " Competencies Checklist." such that an unsatisfactory rating. factor evaluation would result if the candidates performed poorly, was not - -apparent. In a number of instances, coverage for the six competencies and associated 20 rating factors was improperly credited to a singular event. For example, event FW19-2 of-proposed scenario #3 credits the BOP operator candidate with performance on all six Enclosure 1
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competency areas. While coverage for three competency areas - Understand and Interpret Annunciators and Alarms. Comply With and Use Procedures, and Operate Control Boards - is apparent, coverage for the remaining competencies is doubtful should the candidate properly
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implement the appropriate procedure actions. The licensee worked diligently with the NRC examiners during the preparation week to resolve these concerns and produce an excellent quality product exhibiting a nigh level of discriminatory valu c. Conclusion The NRC concluded that the facility licensee's first effort at " developing NRC initial operator licensing examinations was a valuable but difficult and resource intensive learning experience. The examiners noted the fa * Ity training staff for their professionalism and unflagging work efforts in correcting and improving the licensing examinations. However, the quality of the examination submittal needs to be improved for future examinations consistent with the overall quality reflected in the as-given examinations. Greater emphasis needs
'o be placcd on the credibility and plausibility of written examination .
question distractors, and the analysis and problem solving attributes of the simulator scenarios * events. Due to the scope and-number of changes needed on the written examination, the facility and the NRC mutually agreed to postpone the administration of the written examination until December 12, 1997, to allow for an additional review and a revalidatio .3 Examination Results and Related Findinas. Observations. and Conclusions a. Scope - The examiners reviewed the result of the written examination and evaluated the candidates' compliance with and use of plant procedures during simulator scenarios and JPMs. The guidelines of NUREG-102 Forms ES-303-3 and ES-303 /. " Competency Grading Worksheets for Integrated Plant Operations." were used as a basis for the operating test evaluation b. Observations and Findinas-Written Examination The written examination was administered by the facility licensee on December 12, 1997, transmitted to the NRC in Rockville. Md., the next week and received December 16, 1997. The facility had no post-examination review comments but recommended that one question (#17,
#5324) be deleted from the examination. In response to a candidate's inquiry regarding this question, the proctor identified an error common to the question's stem and all answer choices. The marked-up, revised copy of the questien provided to the candidates contained the answer Enclosure 1
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since it was inadvertently derived from the master examination that . included the-answers. This error was immediately identified by a candidate and was then reported by the proctor to the NRC in Region I The NRC's post-examination review of the written examination results identified nine_ questions that 50 percent or more of the candidates answered incorrectly. These are considered potential generic weaknesses , and are being provided to the training staff for consideration and implementation into their Systematic Approach to Training based program: Question Number Knowledae Weakness Area 01 (5303) Protective action sequence for a large steam line break in the Turbine Buildin (5101) The preferred method for tripping the reactor following a control room evacuatio (5207) Operation of the "A" Service Water System Train following a loss of offsite power to emergency bus IDA with the "A" Diesel Generator responding as designe (5345) Status of the block / reset circuitry for the safety injection and phase A containment isolation logic systems following a manual safety injection with one reactor trip breaker close (5326) Status of the operating systems providing cooling to the Reactor Building with a Loss of Coolant Accident and several emergency system failure (5214) Reason for E0P-15.0. Response to Loss of Secondary Heat Sink, directing operator placement of the Feedwater Isolation Valve Switches in the Bypass positio (5346) Preferred method for refilling the pressurizer per E0P-4.2, SGTR with Loss of Reactor Coolant: Subcooled Recovery Desired, with a concurrent grid disturbance and loss of all three Reactor Coolant Pump (5356) Method for refilling the pressurizer per E0P-2.1, Post-LOCA Cooldown and Depressurizatio Enclosure 1
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58 (5131) Required operator actions for failure to achieve criticality by the desired estimated critical position during a reactor startu Oneratina Test The operating test was administered during the period of December 1 - . Based on post-examination review and discussion with the facility training staff. the !!RC determined JPM steps #515 and #S26 were not critical for accomplishment of the task standards in JPMs #JPPF-144 and
#JPSF-171. respectively. The examiners' post -examination review of the operating tests identified the following generic strength and weaknesses: * All of the candidates routinely adhered to and practiced the principles of the STAR program during the performance of operator tasks and action * Five candidates did not know the bases for the Minimum Temperature for Criticality (question #ADMA1B).
. Four candidates could not correctly determine the dose limit and stay time from EPP-20 to protect valuable property (question
#ADMA38).
. Three candidates could not correctly calculate the Reactor Vessel Head Venting time for given plant conditions following a SBLOCA (question #JPF-144A1).
. Three candidates properly identified isolation valve failures for two different JPMs but did not act to close the valves (JPM
#JPSF-137 & #JPSF-057). The wording of E0P -1.0. Alternative "
Action step #15 (b) " Verify Phase B isolation by ensurina
- may have contributed to one candidate's failure to close the failed isolation valve. Additionally, in several other instances, the candidates recognized degraded system and component operation and reported the status and indications to the SR0 but failed to take or recommend any action to addiess the problem. For example, in scenario #6A. one candidate recognized the failure of the DG governor, reported to the SRO. and directed local operators to observe the DG locally. However, although the DG load oscillations increased in magnitude over a period of five minutes, the candidate took no further action nor made any recommendation for action to the SRO. The DG automatically tripped on overspee . In several instances during the dynamic simulator and control room systems operating examinations, the candidates demonstrated a lack of awareness of plant conditions and available control Enclosure 1
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room indications which delayed the event diagnosis process. For example, in scenario #6A. event MS21-2. one candidate failed to recognize that there was indicated steam flow on the 'B' main steam line with the MSIV closed. This impeded the identification of the safety valve failure. In two other instances, the candidates failed to identify a second dropped rod and as a result did not trip the reactor as required (JPM #JPS-168).
- Candidate communicat. ions during the dynamic simulator examinations were considered marginal. The candidates riid not always complete the third leg of the 3-way communications process and in several instances did not always report communications received from outside the control room via the radio to the SR Also, in some cases only one of the R0 candidates would acknowledge the SR0's announcement of an E0P transition, c. [ An.c] psi g n The examiners concluded that candidate performance on the written examination and operating tests was satisfactory but the number of weaknesses was considered somewhat higher than averag V. Manaaement Meetinos X1, Exit Meeting Summary At the conclusion of the site visit, the examiners met with representatives of the plant staff listed on the following page to discuss the results of the examinations. The licensee's management representatives prcijded no dissenting comments, flo proprietary information was identifie Enclosure 1
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8-PARTIAL LIST.0F PERSONS CONTACTED . Licensee Byrne. General Manager. Nuclear Plant Operations Fabry. Training Specialist-
-R, Fowlkes. Manager. Operations M Johnson, Control Room Supervisor, Operations Lavigne, General-Manager, Nuclear Support Services Koon. Supervisor, Nuclear Operations Trainin Matlosz. Manager, Training Rice.; Manager, Nuclear Licensing and Operating Experience Quick. Senior Training Instructor ;
UEC: , Bonser. Senior Resident Inspector ITEMS OPENED, CLOSED, AND DISCUSSED Ooened NONE Closed NONE Discussed
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LIST OF ACRONYMS USED BOP Balance of Plant - DG Diesel Generator CFR Code of Federal Regulations E0P- Emergency Operating Procedure EPP Emergency Plan Procedure
'ES Examiner Standards (NUREG-1021)
FW Feedwater JPH Job Performance Meisure " K/A Knowledge and Ability-LOCA Loss of Coolant Accident MS Main Steam MSIV Main Steam Isolation Valve NRC Nuclear Regulatory Commission R0 Reactor Operator SSLOCA Small Break Loss of Coolant Accident SG Steam Generator SGTR Steam Generator Tube Rupture SI Safety Injection SRO Senior Reactor Operator STAR Stop Think Act Review TS Technical Specifications Enclosure 1- ,
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SIMULATION FACILITY REPORT Facility Licensee: Virgil C. Summer Nuclear Station Facility Docket No.: 50-395 Operating Tests Administered on: December 1-5. 1997 This form is to be used only to report observations. These observations do not constitute audit or inspection findings and are not, without further verification and review, indicative of noncompliance with 10 CFR 55.45(b).
These observations do not affect NRC certification or approval of the simulation facility other than to provide information that may be used in ' future evaluations. No licensee action is required in response to these observation While conducting the simulator portion of the operating tests, the following deficiencies were observed (if none, so state):
* During performance of scenario #1 (no 3A). radiation monitor alarms were spuriously received. These alarms were not related to the scenari . During the second run of scenario #1 (no. 3A), the simulator computer locked-u Enc ~;sure 2
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, V.C. SUMMER NUCLEAR STATION . ANSWER KEY LORT*RO-96-01-FINAL (NRC)
LICENSING EXAM FOR RO-96-01 Total Points: 100 h
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#5303 QUESTION: POINT VALUE: .LO)_Q Given the following: -
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#50951 - QUESTION: POINT VALUE: 1.00
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l " The controlling pressurizer level chsnnel falls low and subsequently the "RCP A . , i (B)(C) SL INJ FLO LO" alarms annunciate. How are these events related? - Assume -
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#5101 - QUESTION: POINT VALUE: 1.00
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.
A plant startu,o per GOP-4, Power Operation (MODE 1), is in
-
.
-
progress after a refueling outag y a p ,t y
.
.
-
.n a* ;g. .m,V%
React op
.
y .
--
.. . .
.
.
^ i /, powetis
-. a at 54 5 pu rfy bep
..
-
. ,
l' .s
, Tp'eThlft Supervisor has orriered sn im^me,diafe qvacuation of the ontrol Room due to a Bomb Threa '
,
F *,e s-
*g*j
,
' d, \
,
- .
~
* -
All AOP-600.1, Control Room Evacuation, actions,mus be done
- .
Q . ' locall gg #- ' khk QG$$YM&e$lMgY _ _ ,
-
t ?/
' ' k'/ - Securif9 inal36Ess/i@ ann 6unced # that all. card rea[dd
' i6lf-}IDeIto. sabotage.$9$My# tyk
'
Q1.?aCET=1n %kn V. ine?w%%s p The 'pfeferred (approved)]pieth n
(%
b,
+ - .n ' NA (& rip the;Ms&jto trip the reactonWou Qh *
df JhShin#uMiiie hrddf:ftk &5$N5lh
' 1$0 #
b' b.h. k 'kMMN8f$iAhy9%f 6l$ fioin tETEfonUStandard.-
[J gpDeenergize ' Buses 11 A, I1 B,[and"1 [hK7 b -\ "
r C+7%5g*[&;.s and
'
q e ; rw Ni AAN>}
' ' ~ '
< . -
% -
Deenergize bu,se,s:p.qBih JC1)J /-
- ;,.,. - ,
V
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h).
- 5101 jV') / ANSWER: yD
/ W.\
. %
"Y (1.00) y
.. ~ , . %.x '
'#5101- ' COMMENTS:
y- _y.\L-
., c .;
-
.
' NEW QUESTION
' . Correct; If not trip from CRDM SWGR Room, then trip Turb' in _
. Will trip reactor, but also lose all secondary plant equipmen ..
,
.,i , '
e*
.
5 g
. *
_- .. . 43S
' Will trip reactor, but will lose all normal PZR Spray capability, .n .
d' Will deenergize CRDM MG sets, but also lose power to other
. equipment. " Normal" ATWS method would be to tnp the - . . -
individual MG setbreakers. Tripping entire' bus is NOT an .
.
approved attemative actio .
.
f
. * , , *
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,
eg^y (Du .
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f ,, a' ths.m._%* C P %g'$,C%%s
.
QWP m W $ Ye- 4 i $, $ %.N,(l$.
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b V. Y p? > ml ~ h.. .C h,( &m
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-
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.
-
+
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,
Question ~ Number: '
.
l
#5223 'QUESTIONi
'
'
POINT VALUE: 1.00 L ,
- -
. < .. .
. -. .
.
?
While at 100% power, the DAST Flow Control valv_es failed closed and could not be i . )
.
reopened, resultin'g in a reactor trip. Due to EFW pump problema, EOP-15.0, , Response.;to. Loss of Secondary Heat Sink, is implemente >
..
- blee v~ d-fe83cU!!nglhad to be implemented because:;
' Based on the'above a3,tions, n -
-
.
,*
*p
.
L k.+ 3 p %#s ., .
.
' '
*
,
% ,
, .
. (assurne all EFW ip4:6avallaN .)- (,// -.-
'
'
.
. yV .,
*
-
.
"
'
%%s2 s . .
.
Interlock has prevented a Condensate pu,mp+from being , l
-
,
,
-starte . -
, ..
i- l
- '
-
. A+ FWBPR$5$$fh$l$i
.
could not beNastartep[?lg4h f
/
." T ME cotIlb Mwith Low Tm".%
v m n,r ikNW5h k,not e be reset'rluetto +-aq
, * - [% - N. ~nq
. Thet Condensatelpump ke. pt thpp@NNk ngtoniDAST hl leve. g ,
-, . #5223, f ANSWER 8 ' NE y ( ,
)W$RhN$gdy g li y (j.,=j j
,. -- e%.:,p~.
.. :
i k, . muq
+ y <
h i
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.
_ %[k02m , ~
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id W r
#[' #5223*- WCOMNJENTS ejl ! D L-Y NW NQXffff)P -
Le
*
Nt
- \M OEST j) <,; CQ,
- b Actioh
+ -
(REF TWR TG10894) UaQ
,
. \g- a.[,. Risk-1mportant 05erator(w -).is inco
,- ..
.
.
'
starte ~/D bf . km) is correct because FWBPs are unable to startduesto'DAST low I ' level, t . \
,- ' [ . .
c.
,
'
-
: Tavg sh6~uld exist fott,fiese con {ditions, MFP signal, is~lncorrect.because the DAST has a low level.-
o -
'. :: ,
.
:
e f . . e . . 3 e *
, M 5
.2 > ,- m, .-m,. , . , , - - - - - - - - , - , . , ,
.
) Question Number: 6
'
#5103 QUESTION: POINT VALUE: 1.00
.
'
Which ONE (1) of the following identifies the personnel required to proceed directly to the scene of a fire at the 338 Auxiliary Duildin . Aux Building Lower Ope'rator and the Aux Building Upper
'
O ,8f9
.
. rator L+ r t .
}$ "FeIopt ;-
pg' ~* p j4 '2 rf /
' - Control;Buildir g Operator and tiie' AupB0ilding Lower Operator -
.
.. a
.r; - u .e L
'M%
. c
.
cd .% , p%%. / ontrol Building Operator and/the t s.Roving Op'erator
% . - Aux Building Lower Operator and the Roving Opetat6r, &
A,A e- tc.e-ene u.;m M-
/ C] cC53.L.= m. #6:mnt.., ye .
,-
"f.;4 e% .K NXild42.en&.cf .
. f f- [ /.
. h umow4
=
#5103s/./ ANSWERb..4,A, C@'
'
A e~" f N
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t m1 W c -
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,. ' = I p 9:4( ;24 . .. . .
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#5103.,g e ,,
COMMENTSiq@~g:p,g/ a we wn (w} ~ ? g ?? h5 -b ([) W * & .Y $ N O
*
4 .r% Significantly m(AfYT' +.h?$m ,nx mw.odifiid.AChans.h **w~7
. -
w.., u %sy gy e;
. .g ,- ~
s c,hoicese r w. c* YpH"'f /4s,;.4 - four;W;w w W s)r >% uv gin % -r1 (ks 0 :% . new '"*:n (a
. #-
s ., EPP-0131reqdirestContro.ll asiocated.;.a,:r: . lidirig'Op.eratiiria u; %' re n ; .rfd Building y Operat a s -
\\yJ where fire..m . e U'
u;r, m : v Dim(b y ;;(x/ .' e t% [.r."[-
-
tsr 6:k x: ('i v[;jii, ~:m ~: y *g
.
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_ . . _ _ _ _ , _ _ . _ . . . . _ _ _ _ . . _ . ._ _ . . _ . _ . _ . _ _ . -
. .
. ..
.
.
.
'
HQ) Question Number: .... '
- #5105 QUESTION:1 '
POINT VALUE: 1.00 i
~
'
. .
-.
-
.. =
.. l
. ' The unit is' operating in a steady state, at-power condition. Which of the following is ! the most accurate measurement of core thermal power?
- -
, . ..
,
'a. . A heat baiance basedm, on S/G heat transfer rate TubinejoahnchI dica ^
-,-
..
"
. .
'
-
Q pa . byIfi[hslah M [p essure.' .
.
' -
,
!
!
.dAjficiency calculation based on'mairisgengatgr electrical - -
;
- c.\,J outpu IAf , .o
- T An average of the THREE (3)' Loop AT calibrations' -
'
, .
,,- -
f jf* , hNh b f,.ff '
#5105~
%> ~ I$E% %*i f@IEB?dP a17
'
n4g:g'y!W
-
'
,: m a
ANSWERvww. ;b.m , %- :,$ Q%l$&W Y 4 ggga$ay
-
*)e j,(j]@ $
ww h A r/ $ ,h hj& y 9~$' j L , s 4 -t
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#5 5 SI -
i
-
- $$) #) D[COMfflENTS $"Eph4k.ph s$$$f [,;.d ' [ - M "'-* yiresequencin{giall b orce374Rbplacidsdi'stractor d.
,
{*- h dhk
%Qt.ddbh W f ~~ WM ^br-wvacuum, e
%: ,, Does'noticonsi er.effic;e% nc copdelis
\"\ turbine sid,am
* gp m foASE'sj ,, o} '.\y Ja7s f /e/
%
,
-
. . . . . \ # *.e .
Efficiency affected y 'of FW heaters in service, etcf)
'
- 6/ t AT readings don't intrinsically reflect thermal powero
~3.,h
-
. "f f kA D,a
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j '* z*.
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,...,
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.
o .
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. - . - - . . - - - - . .
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.
-
.
'
%; .) ~ . Question Number: 8 ~ !
'
:#5107f QUESTION: '
POINT VALUE: 1.00
-
. .
.
A reactor startup is in progress per GOP-3 with critical rod height expected at Bank _D ~
-- 132 steps. After a rod pull, the 1/M plot and SUR shows that K,, is less than 1.0.- . -
Under these conditions, what should the NR,OATC expect to see on SR count. rate
.
J (N31/32)? ?,
- -
n
-
,i
-
" ' ntinue.toinclease Co?h st<4 h .e a for$D?m>andbort then time,.-
'
.
$'
* '
.
'
?-
1stahgphate should gradually t d$cPeasef o,zero.piat l).
' '
'
* ' '
, %, ,,J.'f y . _
.
'
.b>g Continue to increase, but at a slower rate. The,4tartup rate . -
,
*
shculd decrease to zero at the POAH. . .
.
( * tartij p rate'
. sSto increasing 3_dsdre,55sif6]Sr stagjliz
,
,
uld4immediat%I & 68# # - vg
~
,
e m n " (
> Begligo decreas}edo,;zero;from e a_q,, gattvilvaluerde,c l
. Y 75? g[geg$WyB p& %kfN { *
Q
~
,
, #5107- ANSgR: -
..
) AiFikJMA %we
$
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?
A b=ss&?. " ys a v
.
c
% A Ej 1 %
,
#51b7d COM$lE W BA S
kf[ $)d Y
{' i f Y Significantly modified <($ nrv
,*
r m- ~
-
,, order pf choicest. anI' Chan,ge 'I Ym.and distractor
.
b)%- Requires evaluation of criticality condition of reactor base 3%ri'MCB sifEiications e (NR45). Qw/ j %, 'Indorrect since this would indicate criticality.and reactor is critical
. . 'hsf6re thef0A . %A '
T'b ' _L _
/T
"
' Incorrect 3ince indrease~d ' ~' time to^ stabilize counts when close to
,
critica '
.
_ Incorrect since SUR should not be negativ .
, , b ,
.
- .
s
- ea w y-:+ i' <
-- . -- - . - . - _ - . . - . - - - -. --
.
.--
y) Question Number: 9 +
#5300 QUESTION: POlN' VALUE: 1.00 . .
Given the'following: '
.
.
'
* TWO (2) sets of backup heaters are energized to promote mixing i . .
'
between the RCS and the PZ ' I' b
*
The, plMt Ipo,.at:100%'. Elperating,k .C r%
.
*
' 3 I* *
"1 Q)/
< *
.
,
. \ k,., y ' loss of the Reactor
+ .
. t/
Building Instrum , Which ONEs(3));Ghe following resulting component failures will im' pact ~f3CS' pressure control withi'nahe first few miriutes of the loss of alr? \/ .
~ //7 Zi&PORVs vnwa 9 fsilIn%h3~%wNE ~
g g.c4c4N ,%
/ %'s Wrrsh J LCV-459 and 460 LTON LINE'ISolz,laillnh close .A w v <
i 5 % %g p m (*)- _ USlling PZR sp%vamyQ' .y ;rayyalves 5 fa%m
%..- d. auxiliary spray valvd; PVT-L j :!)145?unqc canrioi b ~w t' 1 - "n? .; /
m - Q d; - p ope w w?' ed:dukt6 0 il 5;e.ab61ng. failed closed,
b/
-r h%,I d.$%ZR s;.QWy:ivestfailin[;#:yyb r49Na j' E16heddand~pausil PV ?' A657 #
5;T145)fallinf6)@ien.$ bb d l !bkk L 8 @kb c/h .
[] Y
&&E5 h $$5.!$hl
-
, ,
#5300k'-
'
, ANSWERb:h h// h PI 9h f ,q,q ,Q v- .
,, s ,. .
'
fc (1.00) N' D/ NV
'
#5300 COMMENTS: 'tA w4 , , N
/% .> * f
.
SignifiU~ a ntly modified - Revised stem and distractors b. & * Tk ~x .l4 The first bullet 9as added',to{ihe ster 5'because the original question (316) was no longer relevant, since the plant is no longer operated with a second set of B/U heaters energized and spray valves cracked ope is lacorrect since PORVs fail closed and since there are accumulators to allow limited operation .
.
.
$
.
< , - . - , - , - ~--
- ._ . - . - - --.. _ _ - _ - . _ . - -- -, -- - - . - _ - . - - -
-
.
. . ,
.
t
.
43 Y . ',8
- Incorrect becaure this will have minimal affect on RCS pre'ssur [
. .
-
:
. With a simple loss of RB l.A. and with normal charging in service
*
-
via FC%122, the auxiliary spray valve will fall closed. Requires
-
. examinee to determine that with second set of B/U heaters '
-
en6rgized, spray valves will be cracked ope ,
'
. . .
.
.i ,
.d .
Irgtrept slpyd Le7~PF-8j145 l airs plose ,
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.
4) ' Question Number: 10
'
#5308 QUESTION: POINT VALUE: 1.00
*
t
'
The following conditions have occurred or currently exist: .
' -
All' controls are in automati ,
.
. A . .,_ .
-
fu PT. 55 PZi3 p,_,e}sure,transgntter, actionspf OPr401.4 thaw been+taKen
,r had previously failed and all . .
r 9e r -
* a~ ,/ %<r '
-
'
,
: *
, $. '44 falls hig . %, ,g q
,
*
i
. f s '. ,
A
'
Y . The PZR PCS operates as designed after this-fallure.%)
,
Which (1) of the following describes
-
v w -wth resppnseof the PZR PCR , or this event ssume [LQ eratorw actio~ndg~Wwiw, #
-
.y; r r;;cQ n gnb_9, 6.w:::
.
y
- I PCVWAB'o% ,n%i sig b* deerEhdind$ i"ibb*f I Sif pens, the W closes.at1985)M' actu #m M.k,.48 v sM Fuv A Q@$,.M >P () %,., . <.
lw ' then . falls'n ,toicloss'ati.1985 psig actual PZR
@S *
4 PCVMWcE,epy' sin'g%8%%4 press 0j"e?8Ecrea *# c.k[% d. $ @$ WPCV,44,5B .
. .
a@nd,
. 4.4B I opens,-then,, CM.$ [$bk closes g ,s Mh$N (
at 1985 :sig,T,.,etual
-
yjf 2R-ptqssete? ocreasing
, *T 3 , q# #
M 5 h ?h7 N ' s. 3 d . N h y/A .3 9
} PCW4458~and2CV-44 B openy,/ ..
V actual 9-PZRx;;-hYtw prdssd'r'el' e(cr; easing.$tfjen' L
~G f 4-
.
. s, v '
(fi
. #5308:g $ ANSWER: '
phet
- " ,i <*
sa. ) (1.00) - s
/ s #5308 ' COMMENTS- %
s\ 3
, V , _
f ,j...
*
NEW QUESTIONb 4 St
.. sj .c3 q mc - Require.s examinee;to analyze that PT-444 opens only one PORV when presmre is 100# greater than nominal. (nominal = 2235#).
Also requires examinee to determine the P-11 (1985#) interlock will auto close any PORV. 455 failing will not prevent P-11'from shutting the PORVs, since this interlock only requires 2/3 transmitters,
.
.
, 13
.
. 4
-
,: l
.
I
.
.
a
.
.
4Q Question Number: 11-
'
#5207 QUESTION: FOINT VALUE: 1.00
'
Given the following: *
. ,
The plant is at powe '
. - , ; ' .
TIt g,
C Service htO 1 Water 1C Syifdm"Fi(~.a, J" j normal alig '
' Of ite' power is lost to Bus 1DA. [f.,f f . . .
* * .
* .
.. .
.3 - ; ,3 .
-
fie "A" D/G responds to the event as des'idi)'edhi -
,
#
* h.N'
1 Offsite power is now available. to Bus 1D "Y
;M)
.
.
' ~ '
Which , (1) of the f6110 win bter
.
Syste ain after theq u fo,ss,w g de_n._e7.,[b7pp,'Ei$bS$g_hdN, pf;_ power ~ htz g ft
+ '
S y n%,m.?q . w
'
y us n .?c,.e
;;gy:n% f* . ThefAfsW! Pump,$~ke,r 'brea willinpf the "A" SWP and "A'l ths,.,
N i can
[d 4ySWBPMillIstift oncEthTD/G Mjj% fids%d c6iithe b .
b st an%y;iirneg%ww I
,
;;y;;:.g; i e s660Iedjxu Sg tv. g% c 4 iC
"
(,f)\ b. ≥:;p:.4 The "A urnpgea'SWJ>wyqQbq.,@;g% e ill:NOT"tr'ip;g L
,.A.(SWP restarts'o'nce .M. q
,
hiidjthe6A',SWBPjvill star t
*
T$ifisjD/G
' p$ M hf M ;$ tieYdiitolthe;b*uE'nedithe SWBPjcan befehYredio
$ M N ;I U;) N i h M f M
.
cP a The~"A'fS willin,pptbe J
"A" SWP and thD'A" tb\'$ SWBP w'iliistaPUnip6djtbreakdg/G,tiEN on D 6'nto the bus. Th - .
v-
. . \,-I,, . be securdd ovvwh@en'5ds'@1DRisidit6ted w
to
.
g . ,f[ '
,d The "A" SW Pump breaker will NOT trip and the [A"4WBP will /,') start. The SWBP can be secured when offsite power is paralleled / to Bus 1D @~- #52.07 'Y ANSWER: 4i v
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' (f.'00) 'M Y (#5207 COMMENTS:
NEW QUESTION SWBP cannot be secured entil the DG breaker is opened and
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Output 3 of ESFLS is reset via Block Auto Start Rese ...
-
.
:
; Incorrect since A SWP will be tripped by Output 1 of ESFL ,
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. . ' - Requires examinee to comparo given conditions to know8 idge of -
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-
.
SW pump trip ano activation signal :
! .
d, . Incorrect since the pager is< restor,ed. S . P. c..a,nnot be secured immed
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Question Number: 12 l
- #3345 QUEGTION
- POINT VALUE: LQQ !
,
i 4em t}$ allowing: -
,
*
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'
o + Reactor trip breaker "A" falls to open when a manual safety
- ..
, injection. is initiged durJDg Q/G tube ruptur >
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Tri breaker 'B2 Iridicates opert,and$ rods indicate on botto . . ;
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. .
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h., V/ ' pressure is 1800 psig and decreasing,:pnd [e
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decreasing normall '
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-
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The decis' ion is made to leave RTB "A" closed f rd .
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TheiNBd stesets k!d3[$$"RBSE,a _p.lt1 SI q 9 RAIN A(B) Swit ,T. Fe's, , j- ,, s ?n$$ecMR etp
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+
Next. 'e:NROATC'dep es,ses $6tkRESET PHASE A TRAIN A(B) ' .
%~ CNTkltl500fpushbbit{osIWpFMEjs 'i ,
Ob Un hese condi $ns, w
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$[ll t describes the st iu of
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the'.blo k/rcset dN2nthJ ~ 6h5MOSN2[&@@8' UN
.
a. y%k MM"or;'& i 'E2 Sliwill reset b,ot strain "A" and "B:" : '
/ JNeithbrJrainl'A +
W iPhasiePXwlllNsNth;p$"@L p$
"'D m~ ig g, s ,9;V % -
a en /~fy . both Train "A" and "B" Phase A
,(,,, Both Tralrii"A" arid B'a 'Sp ap'W
.
- . ,. . .
sp,,-.
..will reset,% dt .
h /
.
tf Only Train "B". Train Sl will reset, and only Train B"' hase A will
/> rese %=
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j 'O$lv Trai n "B" Sl will reset; )_o_th Train "A" and "B" Phase A will 4i ' Te' se '
-
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- #5345 ANSWER:'l kg P ' ,,
d ,- - (1,00) . , _ .
. #5345: COMMENTS: ,,
Modified by resequencing distractor , p,; .
,
16 .;
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Requires examinee te detennint. that the corresponding train Si cannot j be reset w/o P-4. . : i
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Question Number: 13 M.-
' #5321 QUESTION: '
POINT VALUE: 1.QQ
'
,
.- .
Given the following: .
'
.
.Thd plant was initially at 100% power when a Reactor Trip occurred,
'
-
'.
'
. .
. -
A h Q . I5" C m . T(.e 'CBS Iraplemented DOE 1.D and"theplROATC & ARO beg "
-
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<fo pgbrr# ihcir immediate Opelsiof. A6 ion '
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-
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- -
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. .
ring the event, the NROATC reports that ong PZR PORV ,
. . opened and that RCG pressure dropped to 1825 .
'
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. The NROATC then Espd the,openh0RV.if
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NkNSErp$p&N khb} W{f{fNrdo this poln N Plant conditions ar,einEw ,as foilowssy;f"
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- Chsf flowTriIli.12fii'55 F
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. -
a NOT initla't d an :NOThequired. The crew shouldTansition to y'[ " 4- .
- - - 'EOP 1.1 to stabiliis hie" plan ~ (./.
y~ A. . Automatically initiated but is NOT require The c(re\ r w should s manually initiate Si and continue in EOP-1.0 f!ntillSI can be N
]erq11nate , ' Automatiddlly initiated and is rejbirerf. Th'e crew should manually initiate Sl'a'nd coritinu(in EOP-1: * NOT initiated but is required. The crew should manually initiate
Si and continue in EOP 1.0. .
#5321- ANSWER:
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-
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#5321 COMMENTS:
.
.
.
. .
- *
NEW QUESTION
'
Correct. Normal charging and letdown fbws show that Si has not
' - '
occurred. SI should have actuated at 1850 psig. Examinee must de prm,lhe th,atT'manVil..S[is required since it failed to
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Question Number: 14
.
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, #5209 POINT VALUE: 1 00 !
QUESTION:- .'
'
Which ONE (1) of the following protection or control actions is expected go.g is . .I designed to help prevent a signific' ant reduction, or loss, of shutdown margin following ! a spurious reactor trip? t
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Closure of extraction non-return valve ' . k ; -
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b_\' NEW QUsSTION**"/4 i
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V . a.. Requires'tfie to.detsr&11ne nee that,$;\'idT if turbine did' mot trip, 4-- '.,- c6uld Yp[. ' impact
' / the RCS SDM. could co6fapplication Also requires 'd6#n excessivelyof knowledpe t and this, in tur'p[
g p9 trip occurs oil a reactor tri y ,
' / Rm . ' . ,Msin Steam Isolation signal based on High. Steam Flow with Lo- , , *L.6'Tavg 18, designed to prevent excessive,C/D of the RCS but is not exps6ted on a spurious tripN * .
3 :, 7 y-
,
. ^l Controlled blowdow;n of the MSRs is designed to prevent turbine overspee *
: , Auto closure of extraction non-return valves is designed to ,
prevent water induction into the turbin .O,. . ,
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-- -- --
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"'e) Question Number: 15
'
#5012 OUESTION: ,
POINT VALUE: 1.00 Given the following: .
" +
The plant is at 100% power when a loss of power of the 1.15KV
. . Parr Lin.e causes 'A' D/G to star * .o ynpd m%: %~.,r% ; ' *
As th(.sDG initially; starts to4ollfapp,roxjmately 50 RPM), a ,
' ' ' circuitry.fa ure causes the Low Speed'R6lay to generate a false-dsign'il of D/G speed greater than 115 RPM,.j - , \ /h ,
h,J A The IB Operator reports to(.the Control Roo than 50 RPM and slowing dow .
. . -
Tk ~ . . - - .- To ifj stag l.AfDG, W the IB; Operator r e mustloca)l93,@hpro r/ e y ,if%.M ~.,rx U? A uw a
/,?c",id #
--
{ ,' Override the' Governor .
' 'f Me.GM MP i [, a 'C' (R b
T Over'r ids 16ellain AII5ta'rtNalv6.? M "
.l)J 4 %dN4;w,W. . T ",~ !;It t c. dg, lace 1,h'e;LOCA6 REMOTE /,MAINT, Sw h), 2e EMERG;S. TART.pushbutton Qb momentarilyk%$ ^
press the
{ f E (&.c ' .lib-Q &( RESET A %QQg)
%? Depress the GEN RELAYS RESET andiffid EXCITER
#M # '
t.- fpiisiibillionNtheh'0e~proks'ihe ENdlSE' SHUT DOWN RESET pUiESUit # ,
- , #5012b \ f, ANSWER: -
t +v!s.-hw T
-
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4,,, . q,) (1.00) /T,
' / fb,) &J #5012 COMMENTS:
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,.
. Significahtly modified. Changed conditions of stem and reformatte Changed one distractor and esequended choice .
l,
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' Governor cannot be adjusted until diesel tied to the bus, Examinee must recognize that effect is the same as a loss of
. power to the air start solenoids. Main air start valves must be
.
4
.
.
. - , -
, _
. _ _ . __ -- _ _ _ _ ___
_ _ . _ __ . _ .
. _
.
.
.
m m'..i)
. manually repositioned to supply air to roll DG. Main air sta'rt valves were. repositioned (vent path) after the solenoid air start valves were deenergized. Guidance for manual start is found in .
EOP-6.0l Attachment .
. .
.
c. and ' Incorrect. Neither' pushbutton will correct failure of Low '
-
Speed Relay which prevents air from rolling the diese +
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Question Number: 16 l
#5233 QUESTION: -
FOINT VALUE: 1DQ l
+
. . .
'
Given the following: -
. . l
-
/ .
. i
' * '
-
'
+
The plant is at 75% power, and the NROATC and the BOP are
.
. . coordinating the next oad increas !
' '
-
ANUr6Ine loadbeing a ad[ R TC dei:ldes to allow rod
, , -m$ti,opo c*ompensate for changes ,.
,
*
I'- i
% ,.8 9
' *
. - - <
- A
,
)e fore rod ' motion, the following Bank C rod poptions exi '
, ' - %4N - DRPl: 186 steps -
..
-
-
, ,
l
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' . .
f Gg l
# Ad'/ -f[$iin?h(SW^$%uhNe
-
kIIf s Group'2: Step Counter: 21851skepGt
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AfteritH' klMI d loa $$f kd }llowing:khh$$'nk b D tod positio
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e
$$@&increaserthefo Tj Ba l (".1
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C l , . a Based'on,these indications ONLY,@h ww[vnu51 Glot/ 5p DN awh$893fe of the following explainstw@t * , .
.
occurr'e,tfin,the Rod Control ahd Ro'd' , [sjtio .
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ibiIion Systems?
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.
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/ should have actuated. Rods actually rpoved @w# and a "CMPTR RO: '
/ p .
i' Edds actually moved and no annunciator-should have actuate ., 'V" , , $4
- Rods did?NOT move and a "CMPTR ROD DEV" annunciator should hTis actuated [ Y ,
,
. Rods did NOT move and no annunciator should have actuate .
#5233 ANSWER: ,
,,
, (1.00)
-
.
2
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. .
.
. .
-
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#5233: COMMENTS: ; "CMPTR RbD DEV' annunciator doesn't actuate until DRPI
~
.
deviates from demand by > 12 step . . .
.
.
.
- . Requires examinee to ap' ply knowledge that DRPI is based on .
r scrising actual rod position, and the step counters are only
. . . demand. Also,,re. quireppplic,,ation.of knowledge of alarm
set.polnis. 'rJ s
-
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_ _ _ _ . _ _ _
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'
Question Number: 17
#5 4 QUESTIONS: POINT VALUE:
' i Given t following: .
-
,
'
- .
Bus 1DA experienced an undervoltage, and the D/G utomatically :
'
.,
. started a. nd ass,umed loa.. u ,, .
.o .s ,4 z., wi .
-
* The rl 1d lyottage con Itfo %has bleste '
,J~g}d.un / *] (.,)/ .
'
:' *
,
je# A" Reactor Operator has been directe jo (upply Bus 1DA (.
,
l oi XTF-3 t ,, , , , y . j%
-
1 No pro .ctive functions have actuated or "A" D/Gs .
' ' .
f
. huma,t ARd'e~o ,A/ / , SbPis.30 yy ;
.
."T"[dEt{siid)"$sYIlta
#M U
, a g.ga
^ e1En s;y A - . m e; s Whi$'DNE (1) of the follonliig[ dss 16es t e' actions 3ie'c'e'ss~ary to synchronlEE)
acrt ~ 'ind close the "A'UD/6brshi: ?f*SDT ) ,? %' 14 3 % cb t ' qs"'Ihla.j.f,gggjy$gg;; ) ST Swi 6 to)GT RT; place the(*DG A I
" 'a MomeY)t "
h a.,h. 9,sC SsDSWif
.
,
B N the'rFciosed el.1D/G breaker [ c'N Q g "%d b. \! Depress the,EME iS [@WC7/pM'libutton, i 6RT>OVRRIDEFys p m hM ' Splac'e't fEST it5h5 ' RTdM'ifthec DG A SYND JSEL
\ '), SWitEh! N'ORifiheWc1 h5 D/G
",
'f y {\$\Q.) (/$' fb'reake (5'$'
- Momentah y, a,ce' t REST pitch to START; place'the DG A
&- ' . - / . ' SYNC SEL/5 witch'tifEfAERG; f n close the D/G brI6$k$ /'i j 'd Depres,s the EldERG START OVRRIDE (:. Pushbutton ..
place /he TEST Switch to START: ripce the DG A' SYNC SEL
'SWi
#5324
..
^#jch to ,EMERG; then close the D/G breaker.\
ANSWER:'!., _
'
. . b.* '
e. ,
. . ;4; . a ,
-
pq - s (1.00)
'#5324 COMMENTS:
Sig ficantly modified from 568. Changed stem and all 4 distractor '
( Tch% {QMr hC. Qu).Sb Mav iC ecl-v h \
o u p r u u o p t % .I 25 kc. Jcw tn dkL^fb N l/guAMu
.
.gg J/p q.7-
. _ _ . _ _ . _ _ _ . _ _ ._._-_ _._._ _ _ ____-_
'
-
-
'
f}t t .w t{04 599 A G'f8 i
/L(vh eo 30 I '//r-/ M 7 >
'
Questlon Number: 17 D U NQ WM l P# I'0'l~SS'IYWII ,
#5324 '
OUESTION& ' f4" INT VALUE: igg
. .
;
Given the-following: ,
'
- -
,
i
- >+
.
. Bus 1DA experienced an undervoltage, and the D/G automatically .
;
'
1 . .- started a. nd assumed loa , m y, .. <
'
'
- *
tty)grIufe oYfage nht[oo h)sicleare !
>uf - - - . ;' . : . '
g
. .. , .
#y .
A" Reactor Operator has been directed to supply Bus 1DA
.
I
.
y "7 ), ,
'
.
.,
h .} 'om - XTF-3 .
-
e .
-
No protective functions have actuated for "A" D/G,. . , 4 .
+ idtTsita e"d$d frequ j IAW dme,the f ARDW~;a,dJ[I.(;g[ jib
' E8 A
/ ,
S (P 506:
-
'
-
aa
*% . , , fpm actionslKs6eMary to synchroniz~eh Whl5 acr6(5nd iclose dNE the (1) "A" of the -fol_i
' .
"@WW6?fyI \'
. ' ',' M
&
d Bus 1DW " lSEdtieiTESTiSwitch to'S h.$&$ R.T; tp('N T h a.h(I5VNC5^fMome(tsii fhfibMbF0Ai$Foidse
" $*"
dYd2g#GA b. YI$MG Ndk $ II E, NSY <f shbutton, morgestarily f] v gDep,rps,theJMERGjS,TpRLOVRRig$$pje~pp 4placedhefESTsswitch to rSTARTtplage
SWEfMN'DRfi 18$ths.QMNiedk'eC % h)
.
^
$
'
- Momentady p[ ice \'YN QUEAak O
. EST Siiltdh to START; plage
,
v-
,
.-
-
[/ja! . c. . l
' SYNC SEL Switch fo'EMERG; then close &ke the G/8%6lJi QG A Depress the EMERG START OVRRIDE dbf Pushbutton&W
*h'Q
.
,amomentarily
/ place the TEST Switch to START; olace typ Df;i
'Sv0 itch to EMERG; then close the&&Yreak,eT*pSYNC SEL e
,
Y alh4k W
#5324 ANSWERrh ( 39 Y d, (1.0) b ~
b
'
#5324 COMMENTS-Significantly modified from 568. Changed stem and all 4 distractor .
. :
.
'
. .
, ,
t-
,
,- , ,r--e , e,,-r-e v ,,,,-~,,,,-o.,- , ,..,-w..n -
,wr -wnn, - - , - , - - - - - - - - ,--,w----,,,---s.n, n . , -, m---.-,,,-m,n m <-
- _ _ . _ . _ _ - _ -_ __ -- . -
_ .. _ ,
.
..
. !
.
~m j)
'" Requires examinee to apply knowledge that XTF-31 is one i alternate source of power to Bus 1DA. After an emergency start, the D/G must be switched to Test Start, and speed and voltage
. droop most be reinserte .
. .
.
.
NOTE: Included "No protective functions have actuated for '
-
'A' D/G" to prevent having to include " Depress GEN
.
.
REL AYS.,RESE
. i, j ppusQbuttontis,d, ypressed inTSOP Pushbutton"in 300, Section V.A. choices. T
-
u
*\ \e'flodhe eJeni 6 sig, palls'wfie'ngenerated in Test mode.. spuriously.that
. ,. . ,
',,' would trip D/G bredier s-
-
% ' 5 /,
. .
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'
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Question Number: 18
-
'
!
;
'
#5016 QUESTION:- POINT VALUE: 1pQ !
~
. .
t . A lightning strike on the 115KV Parr line causes XTF4 Lockout Relay to actuate. In .
- response to the undervoltage condition, Diesel Generator 'A' reenergizes Bus 1DA '
f with ESFLS complete. ' Which of the following conditions would cause Bus 1DA to i ,
, subsequently,deenergize? g
.g s %'td . P4 r
. Bus 10A 5kBXiLockout Relay ' *\I- . *
, .. .
: '
Q (p)niGenerator Lockout Relay (86)(jf '
.
.-
*
T l -- . Dj6 (gffg *
*
,
'
rss
#
, ,
Diesel Generator Overcurrent, Relay (51v) .
' .
G . ss of Diesel Geneg sgal
**
#50 f,6'.,,/./ - - ANSWE w, s a hr em '
'~5rdle@n
'
n 4s4g P affWi. ' t T !! i : AY,)
#5p6.,
COWENTSl ,
$f$pg[4pyggj Q $ ,
@ Sig n'ti mod
% $bbkd$stenNN strsNtoT ; g ' ' ,-
F
!
;
l ,- ' W@%%h.ds s w .
-
j
,
{!Mir9 7 s ss ~
pr . IN 4 correct 51BXl oko c.,
.R.elay.WiPi() t trip the D.G. Igea,ker if -
thE6idi(nisIdfirijripi"%^Aidehch.ino'd (Vjjji \& f/$ [)
.
' '
%r
, b. . , Requires N, amIneg o, ,terminEtilat D/G is in emergpcy start
[<f * -
, .
,- - .
-
- e which disables non essential trips. One of the trip signals
' k/ _
' available in emergency mod N/
f ! Incorrect since this signal does not feed directly\1o'the D/G
'pthaker trip circul . .. ~Y" , '.i IncorrecCsince this will only trip D/G brea er in test start.- ! .
q ,7;m ,
,
y ,
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.
q e 49' t J_
. - .
-.- -
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$ .
Question Number: 19
'
,
I t #5326 QUESTION: ' POINT VALUE: 1.00 .
. , !
The following plant conditions exist:
'
3 }
' l
- *
The plant was initially at,100% powe !
~ ' *
A Q'BA iOCA fiQcauhd DByTrain Sl actuation onl I
'
,
e m
. .
g.",. \ ,\,,/( A" Tfain $1'his y falleb td Actuate;)f ff
- *
- 6
. ,
,
*
\gjg
'
* y -
Q(B) ("A"ESFLS ESFLS hashas failed operated to operat as designed.) #A
&
,
f" '
' '
h-i An XTF-4' Lockout has actuated with i g the the DG reen(e *
.> . .,/ * Pnonto)hiev@eEM$[[$Efff d@$
the RBCUs werel.n arnormal, at poWdr lineu I i
.
og
* !% mI$ PUS 0dkr k. yf3f' - ,g rN -
RB NNM pressu$m re;is:25 pgg s
, T';/ , W,ogg%2@
f) h
*n;0 ~
-
- c' tion, ' W S B b6fi$Efoll6Wirig' A #{f @
A dthed;7.' L1 @ < With NO operato hi6h:ONE31) hscribes operatl.5$
# sys'tehd inat ardi DTOALO(MitOVIDING ?Cd60NG td"thefR'eIactor BuildingQB)?
r wtg g g g g g;pe gg'f q= 'e FA}apa gg"B" RB; Spray Pumps deliveringp/2500 _ ch' to gpm flo e' the RB<and,;MO running.in SLO % h ND7^kw )!RBCUs;3, ONE (1) RB Spray! ump.fe'h.$4venng/~a 2500 gpm flow hks t - b .
* [6,7 ,and ONET1) RBCtj$h'nSg~isSLQW and TWO (2) $CUs - .
7- -
-
running in FAS g*\-
"A" and "B"
'l/. #tQ the RB, and ONE (1) RBCU running in SLOW'hnd+TWO REi Spray Pumps deliveringp d' 2500 g("m flo (2)
'RsCUs running in FAST; '*
s T' , , $vk . ONE (1)lflB. Spray.Purnp delivering a 2500 gpm flow to the RB and ONE (1) RBCU, running in SLOW spee ,
.#5326 ANSWER:
-
- (1.00)
.
#5326 COMMENTS:
:p
,
.
.
e c- - , , <.,,v-. ,e e v.e-, , ~ . - , ..n.w.---,--na ,,+,-,-,-,,r- -s,,,=.-, , < , - se-., wn ~ - ~ ~ ~ - - ~ - - + -
-
. - - .-- . . . . - .
.
. . ..
.
. .
.
.
'1
) NEW QUESTION (9/18/97) Correct. Examinee must assume that RB pressure > 12.05 psig
'
generate'd a CSAS. This will r, tart the RB Spray pumps. Without
'
- *
"A" Train Si actuation, the "A" Train RB Spray Discharge Valve .
. will not open (no "A" Train Spray flow). Failure of "B" ESFLS will ,
lea'v e "B" Train without a slow speed RBCU. (Fast speed RBCUs
-
on "B" Train that wergj'unni prior to the event will continue to
+
.
'
rtu3,witttno?qooiIrig flow /as' dustrial. Cooling Water is secured.)
f !
u
'
-
- The, XIF-4 fod.o6t With D'GJdene'rg'izinnolaffe'ct'6I 'as expecte *
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'
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.
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Question Number: 20
#5325 QUESTION: POINT VALUE: 1,00
.
The.following plant conditions exist:
* The initial plant startup is in progress, per GOP-4,.out of Refueling Outage 1 *
alhreact9ri[TsiniEiEllyoat12 - 15% power Th with
. .
.*8 1 iftitial c '*,, -chnditio'nd sk-sofi'GDP-4, e t complet *
.
- -
e
* \(\s*TheiMain Turbine has NOT be% ^.4d/ent: %. rolled to 1800 rp e 9 Trips associated with Permissive P'-JU'have been ' < - blocke *(/";i \* , [7 A,%circuitcardfailurecausesalosoof#$4.'
V,& Assuminct no operator +actio.n ~'ciho:ose'the rdipw5,?%pw na, d5
~h. ~.p s .~
statement
.
A.s below.w/. <7" hich describes the ef fectc o p ,nsthe yQ2"g; n , , plant: f t%- .'t iL , ,
. .Al wf-
- +.
Oc,,, p
[*%m w,a - Thelrea.ctortw11L ew trip,fyom_, f0 TA (;%)
W *:'o _ c. r % -a *
...s : f r ' < J ..
k,,y , The Yeactor w p.=2, d! a.: I e Nw:etpoint';Oillotrip'; a 6S sq vi, Ag-W;;%9 c .m e : y Ga p, - 2 ~u6 g-fromiNIS
,A ,q PR V
e s High Flu Q^#f . c. M RCS,. temperature'w;p .n x ,l'llfincrease,untill auxi] iary's~'
~ t, :
y st.eiamiloa'ds.idnd h di~elit #1osses[6puhl RCP hea ?w q\ \ w&;h h
. /?0llp{$W .m a nf.&^'
c[**
\M RC& temperaturg.cwil:
generator ssf6'tiies? ,r\ Nincrease' I until steame/7 (
' "
_
& &! "
Q;PWRRELIEFSope *
'f *'
-
l"[
~ . . ' /r V.> . #5325 . /j'N4SWER:
g ph,'N
/) N(u di (1. 0 0) %'h .
v! , \
#5325 3 ' ,i .
COMMENT,,S: , ,
. ..i Modified questiion from:~527 by .Ihanging "IR trip" to PR trip" because' examinee would have had to calculate a reactivity balance from memory to determine that PWR RELIEFS will turn power prior to tri Incorrect since initial conditions are too far from setpoint for Tavg penalty to bring setpoint down far enough to trip (Actual AT is low at 2%
power) before S/G safeties stop transien .
.
_. . _
-
.
. ,
. .
.
.
. ,
*
4. P'3 Incorrec Power defect will balance Tavg increase before power range trip, Must recognize that initial startup out of
' Refueling Outage 10 has'a positive MTC. Also inust
' ' determine that a loss of C-9 will cause a loss of . I
-
steam dumps, which will heatup the RC Heatup *
' -
adds positive reactivity (due to +MTC) until
' '
balanced by. power. defec PZR level slowly ; ,
+
increasing .itrya sgptom o, " % Tavg increasin " ' [ g~f"~ >,f% .
. - . . .
Vi ;/ /f .
.
.) s/ s, . . .
.
. .
. .
.
- .. g *
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. .
r ,e v . ; O
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.
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'
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n. o,, j~~ A ywr (n
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'
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-
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\ ,,e .h. Nh . . . . .
w._,
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ft ! s
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. . , _ _ _ . _ _ - . _ . _ . - . _ , _ . - _ _ . _ , - . _ - , . - . . . , . . . _
.' .m . %l c) Question Number: 21 #5214 QUESTION: POINT VALUE: 1.00 The foll.owing conditions have occurred or currently exist e The plant was initially at 100% powe e A malfunction in the MFP Master Controller resulted,inp(a)resy'i ~
4' , t fn ftor" trip on lo-Jo S/G 1eve e a:
. * Subsdq(eit'TailuIed lii* tie' ;5F,P's- required the crew - , . 'fof' implement EOP-15.0, Respons6 to Loss of ,Nke,c6ndaryHeatSin V7g , %,g ( /5 ,
4 ;9 A high-high sump level exists in ONE q 5-g Intermediate Building sump,
.v l(T[)
y ,
~ ,/*
- h*.1e '4 FAS/G has beenrdeterm'inEd5to be!the only\' INTACT fl ,d s /y CWA v i - ..m.o ,,o E.3ds!hR~; , ,*"" -an,/
' #y ;4 e
z%. .. . . ,
-
s'ecuring thdERCPa dwh ct the operators Af to to'r,'cc pla the key switch [es) ifo1,doesEOP-iSIO$dhe0XVG-01611A$(FWIV) in BYPASSh 77 E ' :MZ'c~:-y
* '
"
% *'
rN This : willvblock', f eedw'ater . isolation signals"(SI, n
'Ny ["~~'
td(P-14hanePj4(w[thflof,TavgP,(allowingafeedj
' -q supplyJ.via(thelFeed.iRegulating, Bypass Valve 7 V/ 1 m
AA M ^ 'q!&J (
,c - . u p.,
b. V'.s:(FRBV) .k FJ' :y$[Np NIrisokI[y4$nsig .
.e c.;hinfdillbkiickfee h)
. t IPf.147,and?P 2 4%i'th/lo}Tavg)$611owing a feedh
'l},i L supply,viaithe'iMalnge'ed.jRegulating
' - Valve j FRV) .
, g.tll3. % ,, .f This will bl6ck('bkhYido'lation signals (S1 pPL14,
[ .
, - .P-4 withilo TaQg)1'and the~ existing isola' tion
~
v- .
(,,i*" ." - ,
signalfromth'ehigh-highIBsumplevel-[(allowing
' ;//.-,' )
a feed supply via the FRB (*% '
<
s a
>
d .'
'
This will block the isolat'.on signaldh(SI, P-14, P-4 with lo Tavg) and the existing' isolation fignal from the h1 Jh-high IB sump level, allowing a'! feed,s.upply via the FR ~; ." 3 ,. 1 .
#5214 ANSWER: i ,.F
^
.~ (1. 0 0)
#5214 COMMENTS:
NEW QUESTION
. .
.
-
,
. !
.
.
$)"- Requires examinee to comprehend reason for BiPASS and relate to the subsequent flowpath established :
in the EO .
.
!
, '
'
. ' Incorrect since the FRVs do not get bypassed bp key interlock . : Incorrec Although the BYPASS functi0n removes *
!
", both FW Isolation signals (SI, hi-hi S/G level, P- t
'
4 with'lo.Tyvg) afid pig 16high IB sump level - isj2/3 IB sutops. The
. . .
s1@ngle,J~the'coid61dehrd,'lYOp/ swf tch"doePNO'T rerdo%' 'On Fe (1) spmp's - -
-
Ts61Atfon signa '% *
)*
,, .
% ,8 y
,
\ '
-
%. Although the MFPs m be used to sup, ply feedwater ,
to the selr' -i S/G in EOP-15.0, this/iw incorrect .
. .
g since,ths I mrControlleroutputgoes/tothe "
~
a and .tc.. .:he FRVs or FWIV '
' ?L! ea. d %
s.khs% n%gM, @,(- jefWM?
.
'
, m gg ep} gg.WW (
.
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w cd A<f%- k
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-
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.
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,,
y) Question Number 22 l
#5309 QUESTION:' POINT VALUE: L. '
'
Given the following conditions: s The plant was initially at 100% powe ,
* All systenis were in automati ,. s n+t ~, .
n v ya t s . .
* i At 14 0.09 FT 4 77, dd.'it'he cont M111.ngffe dwater flow <
transmhtt #, ffil f~5 ' ' " ' b ! T1,, /. ,, +
.
-
* I&c.haA'pdetermined that it will taEe.ab8ut 8 ho'urs to i fix.%)ie proble ,A
'
,
Y
.as .
t WhichONEQ1) of the, following is the' latest timeby,,Qh,ichthe associated bistables must be tripped? ,#\ '
- *
,,. r . wWm.h@, ...g %J Vj' 1500 s, eML e .. . .
g ,e
[aA s,te s,f W :.s :Q 3 'in . . . , , '. . .
gC g. # w. e .., & F gfW
-
s ,.z
.;.; f ,. a ,,4,, ,
.- : :-
.g g(. ;Qg,
,,
1800 e g/~ ,W V:n,s, - c, ~M;. ~
;& -b,. tr, y.<u. u w/.,2 !., z :c-~.
-
s 7 p
,. . .a 2000 13P.%.
4-s,.'?j 'O 'Yh. u.!_ j,s. ,;7; Q .o ..,h, ()
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. .
. .e m
,
%
;
-.g: p.rq... >j< r , ,s.c;..C, ;i , 5, {
- -
..
$
.%' P"d . 2200,5 & lki M: * ~C5.A?' R$ .: A %#
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. '-
Q601 W~ Rih.;. , Qi (m
' #Sh09 #
Uf251/SWERI Q M QO'lT Q Mw~[: ; r g - ef 997,% .>;lm,.D,@9 2 g,e ~. p y;p%g f . ;
~
p.,.
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#53 9\ COMMENTSh.ed $ 'i * % d p M %
h Significantlpi
' *
MQ modified,,\{'& ,/64&? ,~ .f
,.. stem and reformatte ("p '
g ,,- ,\\ Changed
\/ Reformatted choicesjandfreplaced distractors (a/and d.
'
,. . .e # ,,- .6 Wf % * f,ss#% $d r f%,
N s k
/ ) %N b/ / / '2,.%g, s
bd ( , N p.%a- ,*(-
-
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ew ! 7 f' ,, .
-
4 .
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'
~
.
.
.
.
.
m]~ Question Number: 23
,
#5328 QUESTION: POINT VALUE: I,00 Given the following: -
* A reactor trip without SI has occurre .
* After successfully performing their Immediate an OperatorActions{'ere'w&ORANGEpathonSUBCRITICALITY isonotedlandr6he,* '
tr'shsitions t'o the proper p'ro. cedure'.M * A = 5..'s J.ij
. ,
,.e s -
* p g%--'v,.In ab istigation into the loss of9.subc.riticality *. y
.
% reveals: *c ,%
/ pu
,
r ( - The MSIVs are ope Qb
.
t,/ "',,) D.k"A" Re. actor.rMakeupt Wattfr p, ump is run,nin o - m. ,a - - ,. ..x s
[. M ;'$w&uisd.O.ifdi'"~ ,J .r*'d Ps, y +/
t [. /
, ' (* *7-k:1f%XVDD8430) BORIC ;"
ACID BLENDE.R INLET
"* >% NlVALVMf,Wkhis CLO3E iXVD08454',fQ* )
7 * 'g w & 1- ,i? %
,' -
CHEMICAL?MIXERLTANK HDR ISOLATION '
r,y% laVALVE2 is(CLOSED .' n i"' I
#~
m.,, f-"~ ;% W.l b & Ull50,W . ; S O
# ' -
QM ~(XVD08441RRMWECHARGINGiPUMPSUCTION
, ..
Q h k VALVf,$1'sq0 Mg i [[ $ % F PEN? M;& T ( $j <[
-2
< @s.rf
%
sjv.%' 9l &Qj'EFW
*N. . ;
\ lbd flow, ' kbf tg
,
, (ea,chl.iS/G cs'& " is Approxim Qk <-
ykf(;M
"T -
r. w' . , .
'JNRJ1gye15inFal'lS/G's
.. "
THREE4 is % b;.
(3)
\,
"
"Pf? $23,^ft h $3!._."" d2'2'"Cr"^81"9 - (
Pre, ssu,redih~> iill! THRdE (3) S/G's is .. h ' -
.
,# - -
.
-
n
\ - . . . /[( , approximatSIy'1000#andrelativelyh'6abl .
pp Based onk_,ht,ise indications, the loss of suberiticali.ty,1s
? w due to:
d'. An unisolable faulted S/ v C'* x
/s s, ,
. "Ari" inadvertent dilutio .
t
'
+., -/l,
, h.- Blowdosnlof the:MSRs through the L.P. Turbin m Overfeeding the S/G's with EF #5328 ANSWER:
.
. - . . . . . .
. _ - .
, -
. .
.
-
,
.
-
.
$$. (1.00)
, ; ;.
#5328 COMMENTS'
'
, ,
.,ignificantly modified from 285. Changed initia condition Changed correct answer and replaced two .
.
.
distract. or .
*,
'a . Although an unisolable faulted S/G is one of the
'
most 11ke,1yqyenMthat yould cause a loss of s.oBeriticality tWe act s
-
.
MsIVd *are~open',' dnd '/ Gip'that rchsuges NO SI are'has occurred, increasing -
%hses;'"^this to be incorrectb>/
* ' . .
'
' .
'
:
,
) *~ .
%,,ff With a reactor' makeup water pump running and 8441
_ L
, ,. , .
open, there is a direct dilution path via CVC S/D of MSRs designed to protect turbin frpm '
-
f h,c. - 69erspeedirl VQm rgnota;tS~p%K, MreveWfcooldown M!Mu;%';&m 16se SDM).
f v jp FlowsSo 1.-g 75!gpm are norm.,6c w
%.7fy g%l*4 f d.' a fflows after,a trip, I
D'* onde:S/cs?a~rd atg'inimuthueWi# S t. i (,%
'
& n j@NT4IfsQg$,$.MCF s
- T@% mij M ,
@@ $ff:V2
.. .
%/ - , .
-- h d);IbMkI ,, ehh_!N kI
'@'.@s (/+,)
-
.
Qgh_Si(0$hyA9h@hfa3Isp;7ps$$a$$$m$$ WMe 4 4 -N c _a 9ggsn ApSpf{ a&5;i
.
6 a m e~ m i Pa 4em WN %j p w'p%[%gdf d.D,s. h5 3/ * N( gJ%
... i 3 h, N
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" m (# 'FJtM nwng @ g ., mm Q Q&
-\'\h, NNQ y:syq;<;,w$hg f %?:b5Y S
f LA
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v w
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. .
.
,e
- - - -
, t w -
.yv,
e w ';-9 Question Number: 24 #5329 QUESTION:' POINT VALUE: 1.00
'
Given the following: e The plant is operat'ing at 100% powe e During a calorimetric, the NROATC is in the
-
process ofIi'8, o.cBurs'. adjusth gfN44,,y\ / hen a Turbine Trip
,I U ' i" 1' ~."-
not trip( a[utoinatically,
. g "* % ) //
Mey[eactor does and an
. . . * *
Q ttempt to manue'ly trip the reactorg is N ' unsuccessful, yjN ,
~N *. Txvo is 8 degrees greater than Tur. e ,A) ,
.
(
*
( e CRS directstthe-NROATC To use"the p
' The,E,d .f rod.idnssnfon?.fo,r1.th.dse d ferred condi
,/ J- m'eith -
noAs
., .
'
. . ww n .?: . : ?..
D a.ctswc e,' W *n,e these s A,co6di <t h ion % w'tt 1 v, q. ;
.
..%.T GW,e
'
r ,r r r NROATC e r, d;houl s~ .g
> &*_ Switsh36?MANUAU"E5'dfinsert 'Tdds all the w(ay 'i ,% . %
r;. s, r'&: % .*q.,. y G.; r s a ?. G; J
- +
[ .% f* [S t ay (in?HANUALWnl es s; ONE s(f)/ PORV ha s be erig).
. <?:1 r
." t.)q ,,
N,M}freviiidslp/
@:;gu a C .;w, isolated .:: m. [Lin1.which" M_, ,[i" Q p,to case)r 4.. switch to-AUT e ,.
e(.% c . Q. :, o.Stayrin AUTO'a euntil Nodispeed ,dr,op~s/ ' below 4 8**spm, c
%dthenM nserti" rods)iri NWUA T M { UM . ' N p#@/T'!
/ eg h'**,)" 4 Witclhtio Y%7'Mbc$ AUTO uhtlR#ciilsp? eed drops below%48,spm, (b,,e s thenin' ert.TodsiiiMP.A.'TUAL /
,;.C}y
-
V L(:N& ' ' y
. # 53 2 9{/j
, MSWER i C "sXjy& L.(: J -
'
(f,e
,r-7 y
' hd , ,,
(1.00)
{
#5329 COMMENTS: 3
%s Signi[w.-icantly n:odifie Changed st6mfand distractors a., b.l& , .
'~
e4
* % Correct";i RequEres traibee to analy::e symptoms, apply Note 1, EOP-13.0, then determine appropriate respons Note 1 applies to an Immediate Operator Action in EOP-13.0, which should be performed from memory. Manual rod speed is 48 spm; anything faster is acceptable. Also requires examinee to apply knowledge that prior to adjusting N44, rods must be in MA .
.
T
_._ _ _ _._-_ _ _ _ . _ . _ _ . _ _ . ~ . _ _ . _ _ _ _ .
. -
+
.
.
.
, .
-
.
**
-
t . 3,h
' '
Question Numbers-25
'
~
i- #533'O QUESTION:' POINT' VALUES 1,00
'
, .Given tle 3 following: ,
-
,
.
-
*
o The. reactor was initially at 100% power with all- , , controls in automatic. ^
'
- e' The-IB .e Ypr' N#118"the.,Centrol Room to report aA0 4IAdi ib rokeE'36'ths 0 6 I ^
'
,
'
..
( \s ~ ' ' % q f ,* ,. ,.
.
.
.
A (DATC reports the foll'ovfihg: _
* .. ' . .o '
4 ,
'
, N~ .~ .
'FRV deman'd~ signals are increasing, and
%g {
.
,
Q- feedwater flow is, decreasing. #
.,
. - IA Pressure 70 psig and decreasing *
*- ,/ -e '*di' ate dp ra A TNf EOP eni k['
. I .,.
.
prl56E.disr,e'hhaYe been -initi*aYe5E "d a "MAI RX TRIP"
- f aniinif6iNf65 flasr actuate'di$EIN* l- - *
e e ThefSEZc 4W* 14 %W i % ecks i IpC6andf port re%dih?sithe % ' fol , a i ,
' WW 'W "
.
. . ' ll@g I
\condli'EOY15T Nd '
wa 3 ez" kYR$ R l$$%yg,, gg
, :+ (f) '~e, c
q==u g
""#
-
gAn G: ML . ./31% arid # decreasing
% i? .u 0'>f
'
,K/' ~ f
*
e aog " GrWRalieve
.
' hi f z nd decreasingurbpidly
.Yh29aseers
-
-
- t d s/w$ \WeVeh /24Nand decreasin
-
4WRT I t,p* .6 . !! repprts;/the! ? '11owing: "'v_ , ,
. . .
g/,ww e- .The NROATC $ h .
"
Rods moving in at 52 steps / min. Q -
-
-
- ' /% e/ yus
*
The appropriate procedure (s) has(hav Leen
'
,;Lmplemented- for these conditions ~. \
}:% . . . .Z~1 With the prer entiplant . conditions, what 3 is thefb asis for tripping the Turbine?- Th= _&_ e;T mg
,
<- p.
[ . . To decrease 'T,,[To no-load to maximize auto rod * cspee . b -To shutLdown reactor due to RCS heatu To minimize-RCS overpressure, v.
L
%
-
-
.
-
.
4 4
'4 .- . . , . . . .. - - - - - - . . . - . - -
. . - . . . . - . - . . - - . - ~ _ . . - . . - . . .. - . - . . . . - - - . . . . - . - - . ~ . - ,
* '
. .
<
4 - .
. i
* '
e .
,
X?.'g)-- ,
. lTo prevent an RCS overcooling. even ').
. .
'
-
#53301 ANSWER:
'
I ( .00)
'
, ,
.c, . .
i #5330 - CO@ENTS:
: .
.
~
*
'Significantly modified.from 27 Revised stem and-distractors'a,& d"; R $ordb'd',co'rrect' answer'to require '
examinf59 td'g " 'b~Ep'erRijtFtas$s r -
*
. . .
.y Tncor(rec,t.. , '
~**
%f ,f f .
'
.
.
. . * ' .Not part of the Wasi ~
.
*
,
.
-
%, .
. .' Incorrect. The steam dumps will d'ecrease RCS .
*"^
.
-
-
temperatur '
- . . =
L)fhdent
, . .
_, ,
. Correct - per step 2, EOP-13.0 basi ,S
@/* * diffst' determinestromplanGNnditidning t a
,
-
'. '
'
/[ s' oOhthav$$"$$iphidsdif56 Tor *S$NEvel ( 7)
"
SG m 5E..d.rdent }nust assume 6655E ,Thual RX trip was the RX n "C"
- ~
* b$p% 3 7 f .
k qgh j b$
' '
Y An oVercooliing g/en T1s$$!I$ra!f6oncern whil(e-t' e ,
' %
reacE884$D till'cri '~c'a M 3 T
'
Di ~
:S' ?;
.,: R
,.
res examrnee
$$ h?% 'termd.neNtlist
$$$W .
4., turbine tr
!)
. .
,' . I '
afEEEEfgosdTO$Mee"dE5BdEg~'SjiTire,qUijedtopr"gpp event a loEA wil'hfke}t's$1dQ%5i5.{hedSorrec,tlajkwer}; whi'6)f Vturn,.p^reve RCShoverpressur M Q m y .
-
' %1 yxy p'y '
+ , i
%
ji
'
'
.
.
.
.
,
. \y .p
.
.
! 9 68 (D ).
<* f*% ,
-/ / %
, _ r .~%% . . N L Ua.- Ns
? F
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*
.
g ?
- 'J 7;-
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,
- 's ! . ,:
_ s
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- 39
. .
.
. - .
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- .
Question Number: 26
#5331 QUESTION:' POINT VALUE: 1.00 The following pl'a6t conditions existed initially:
* .The plant was at steady state with reactor power at 50%.
.
'
* All systemspere['6peratingc in ;
automati . 2s x 9p L Iap;s s ,
. The..following c,onpiti, w s sdrr ons c n t ly. a.ex. .is t.b 1r: / f
.
. , ~. .~ . .
.
*
,. {gvgis575'Fandincreasing.N,J,#fg
,
6% es . 4 ) Pressurizer pressure and level also*b6 gin.to
- ,,k increas (*~hah *
These "s tho's6TE$at wolfld be eceived withf ptoms IEe%consistentitwith:ShlNf5116w~1ns event $(
. , ,j[the first'@Jum,.ag.% AS y, fnI2te q onshidh%f + . cri ,m := w e -;; - ,fgj F %
4,-% PZRicorspiv(alves;.partiallWopeii? then fail close b:n t new: u - ry xv wx t, WM, g - t , , - - ,...3 e)
(
77., o Cont'inU'h;5!frod UI 6draWal K W; Rn %'
,%
i , n w.;v . a; y
/
sw. .,.u . . u- :py - O, I'" /t.The c'ontr'olli5gCPZRiPCSetranbrititter f ails l'ow?
@ * t M35$9f M 'M NIkNr,$ D [ f1,-} .
I r[3-) d.;N$[3 d The;ccontrolhng. PZR4CSctransmittet cWc ;p <- f ails l'5~,.; 4 o a ., a y n:: La w.:
.p s, Md.u' r:W r ., . , , - v%nn ed ax hr fe n c.H y: f 0 [%4 - ./96 4 , W; J.% #53314 c
4ff?W a h $ (- pJMd. h. M/~ ~ jf %y
\ 5 ANSWER:$ $ G g
-
; w, p d b. ""p g* T'15'oo)f af/;aqi Q ; , yg,,, jQQ2 b. py
-
4 ,m. ,'a. rvpQW m , :s sJ n .
.
.. t, * ~"
#53314 f .COMMENTSt $Xi-?/" '
.
.x,[ '
# Significantly modified from 22 Changed sSem'and
\ ."'(/i
.
#,di,stractors a., b., & c. Resequenced distha.ctor ,
/ sIncorrec Has no affect on Tavg. %%Distractor .
. .
fased on given information abodt?PZR pressure and level beginning to increas " ss A - -*, Correct) Student'must determine that Tavg for 50% is 572* With"Tavg HI, it should not be increasin Incorrec Tavg will not increase in first minute, Incorrec Tavg will not increase in the first
.
__ _ _ . _ . _ . . . .. . . . _ - . ._ . _ . . . .- _ -
- .
,
.
d
* -A '
w'*
- M0:}),. minute-and PZR pressure decrease .
y
.
9 4 4 e
9 g
e 9 4 1 *Y / ,{#$ "f z. j"\
' *
' %, Q, ;./;
-
, ,
,% 1(y g it L t e, -
,
. * . [% g % [ *
*
9%
~
\ a4
:
l k. d, g f , W *
,
- - s .
. J ' .
t
'Nw1%w 5 egh w w&Mg?GP sG e q1< sg u s.~y' ~wsshaw . &-
Nm..oLg;ge G# f2' w ta1 d.[a s%mgeg . peedyE6ch7dfgNyU -+
/ .
m .ws n w p.- o . Li$$ $
-
5 -
,c e
AJ '
-
b, ,wa ~ F;gze>s1syssW ememG,y kJ d-) gyna -
-
1;
%s e@x hs s. m L3 wh w p_ u g g n~ :wi, w g m
?ga J 7 p M(S,
,
, Wp h!? 4 - A5 'k t%Y N f,,+
y g u&p;rp% myCP
-
%gk 2 -
g "%~*7;g&g 4 4*c.* y+s??at mhWm sg
*
% .,5 4 $,1 J u.-
% Y 3_n ~ ,,m.$5%Q"elg{fsyn
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n . .~\ s e
-
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l \\V h.'/ Mb" f** fj .
.
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.
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-
-
.
m _.'A d Question Number 27
#5332 QUESTION: POINT VALUE: 1.00 Given the following: '
e' At 0400, the Control Room is being evacuated due to , toxic gase 'o Two operators,have3 b edomersick due to the gases, so the SS has.: balled finkeli6f
*
"- '
6 ;for/these two operator ' v fu ~ ~aw '('? $ f , , ,
.e Therp a\iInimum maintenance'doipiemen a, sy ~ n. - '
s Cont *rdl of the plant has been establi yshed.,at the CREP ,
\V ,f' xes k ,4 * # 6s ~ ~% CS pressure is,being increased via PZR heater,s -
g B/U ' I+ h* group;1,
' e ,47 ep}" J
'
-
;* e Prior @to;; t.he e. vacuM.*?"*WMUN ationgther.e~w ~
,
Th. eiNROATC,zeported the d,o,ere.bproblems n_oted with
. %v,;4 CC llo .< wing RCP parameters :
E u+.
<M , . k--ex:gs t OM . - . - p:fy.: g * %,*
t : n =T
-
T" Maxcmotoribearing steddy'.3d:l ~~ kdOy temp @eratureiwas 'd' 150*F. (< a n d N, ye% - Max (sesMater.QearinVltsmp, Nis 200*F and stfead t n. _ f* - l'M,,ax m,o..%t. ori st.at. ort.t.g,pe, c em
. , , rature*was
, , 2 5 0 * F and 's_teady .
_j- f ?b .*' r' Y3 f _ Y- ; / .="f j The/followinggpla{nt condit:1ons exist:m[
,
.
'
w r/ 4
%ffSPn %PZR3piessurdjiih % 3. % 219_0k [$ [psig E .'% .. fj%fj ," % % -
M 7,# 3 TSU6do31,in Fisb26 P M. C$'N' Qo_
[# j - - "PZR $iU7e h.id",Ii'2 Waiidh EaBl E55 %' \J -
ChA'rgih'g flo@pA Letdown'gflow'lifl1'@00[Wpar.,G9(adjud3edto85gpm!"A
? -
. ,uf
- .q u - s.O,u y-y*
x f n The oper/. the CREP should p.;v ar
-* , ator at erform which one of the e followi Q actions in response to these indications? f%[% "* f*) Initiate GOP-8 to cool down the plan}t .. ^ ? , 'a m:-
t $ **
, Secure the running RCP to prevent pump damag s v p -
4.,.
. ,;, Turn offtB/U group-1 heaters until PZR level is restore'd'. ,cme . Turn on B/U group-2 heaters until subcooling, sufficient for natural circulation, is restore #5332 ANSWER: (1.00)
.
.
.
. _ _ . _
_ _ _
.
.
M n ::;. , v. .
#5332 COMMENTS:
~
Significa'ntly tnodifie Cha'nged stem, replaced 2 distractors. Modified all distractor Resequenced
. .
choices'c & . is incorrect since this cannot be justified from the information given and would not prevent heater *
, .
damag .
.
. vs, y ~... .,,+n~m m In. tor,.rectt 'R P'1t ripf cr. i,teria met .
c . . . - Maximum
, , .
W . mo tor"b. w:in.Notempef tep bearing temperature 1se225' e.ar g ture,? l, s ,19 5 ' F . Maximum seal - Maximum mot 6 Mgyatortemperatureis311* * %. d< g h
*
Student must analyze given condition F
[\..-
s+in light-of
. s .
r PZR level interlock (17%), and CREP kefation overrides to. determine that PZR heaterssmust.be *
*
LA shcure , e -#fMIP ;O d #
#
V5
-
d
%rx,d bd.w!; y .m m
A.%m.,,.c.,,;,2*,.ig
.1.. s .M.prf 4 ??/
Mp/ e[ y /\m t .'k , * Iril correct 4 g. M-'N e e d t o p r o t e c t',#..g ,,:-9 P'"Z.# R i h e a t e r s a n d. %-not
*-* j- ^4 4 E'
?**w tuistidhn65befheaters thht"?chd1'd?be damage y &1:.pr; g s v ; r; + p%. *
,sCI# hm h .- h?a my+,- NN ,
;
.
y%* m d;.;- mp .m a i ; v f: y
-~%
1' {*** Q p .3 _
Yt O}yfO' + q;mg
$yG H Qs:-bRvf %;j . . .YT;W Ls*L w'.'.'t % jC'WT) Lp
.s.; f * 4
%WAy+
h *
* .[ U.*
w,p a me, pan g . ._r , Q&s[.f,;Q@ as n+ ,u QQC t, ei,kk
gn$f & W+ 1w%ll$ a lw[' e w Ah yL %.a m., t ,n w: e s ~ ws1 ,..:,7 e%.s k s;%c .:N& .;m q, .,e ,Q.;Q%.. t j-Q3.i ")a w g .y? & &sQ
\p\; -
m.Q,_[q1m 4 QQ;qv a m.3, p
' s ~~g:'.j rgafj/ plth .
.~
m3
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s a %W
,,.;;L*y., J
,.
*w%%m:.u%g_/,s f*
% %~
. .
n: M.,yf ', qr !g; %gg i s }m%
.s; g i s\ f.> w. **f
- t e
.e** Cy 1 v~st- ~ .,f O.,? q *wt .: ,4.- ?-
+
. +f .
sI e g
[ [ ,,d [+\ -
)
~
'/ / , . w,O p 4
%
i j Zy ;, ~ ; y = ..
*W .k k _g
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' A *! "
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,
.
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_ _ _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ . - _ - - - -
. .
*
e f. Question Number: 28
.
#5032
'
QUESTION: POINT VALUE: j 00
'
The. plan't.has experienced a blackout of both ESF Buses and implemented EO.P- While reviewing the Refe.ence page, the CRS reminds the ARO to reduce loads as necessary.to maintain voltage greater than VDC to ensure operability of DC load . mm
~
.
. ~m 9 m . -
12,5y vo[s. f%[, >1 is l[,t.,[i(~-h/}; r
,,
.
,
- '
b. W .
#a12dW olts -
;s 9,4 s
.ocQ. .111 volts ( /, * ,
c <%
- %Y, fv .) .
s .
.
.
- <#4
, 4,08,f?v.olts 05l NY,~AN& m .,
. .. ebb ^ /
#5032 f j ANSOERsM!h M N $$ *h "fW" dsh.ekT
#
' ,m
~w, ww.s w..wn y ewn n:,:.=. .v
?%
f (n:.too i
. y.m a y #J , >
f M'&;+J' p ~ vu rg
#5032='
w a@N5.%M5s ~wce ' k sw o .-
$TEjn;MyMi$f3 smm fr (%}
%
,
"}f COMMENTSi?u%m
'-
a_ w m
i ., { , . . , .,A,
#
?n Aw-W 'u s * /? m
*4
.m e 's ln,,1 (
,.g sys L W W & .g & Y[ a r X [EL,
.
V.. : 0 ~ w,H: . AA eme m: d+.%"J SignifIimcantly modified?iChanged[5tenfandedistractor d@2Mb qr cF*'t RIM. $ f y. ep " p n Mr#C' 4,fg N ir*? 4(5
%,,. -m ,
tteryl;lv{A'" olta
:';e:ii,
[94 0'y * p;TechiSpec limitforcc:eque La u &. t *; .- .as
--s 4. n > = ~ m
.
:P *~*
.-s p: 3 wo r
gg s%w t charge,
**
~~k
' *t* sew.ge
.gi}.
up6 . . ,
% is equal:tF60" cells' times'.tfie1T;Seminimum cell voltageM V' i
,
-
. ,
s/r r ,,. is the$m miriimum olta,,ge, ,, m ,Uif.\\y (.R. ~L'?ll
..
n(tper STP;501 u,a. city Test
~ .
.
" s
' /, is the value given on the reference page for EOPf0'.03 eJ m <
%a'tz/
A
/ *
/ '*.@.
%
%"? %
& p, ry ,:
Y ,
*; e t y
,
%
5A r f, * " _ . . . ? sq g- +,
.*
9.a Q
.
.
.
l .-
- - - _ _ .____ _ _ _ . _ . _ . . _ _ _ _ _ _ . . . . . . _ _ _ _ _ _ _-. . . - . _ _ . _ . . _ _ . . _
f
.
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.
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'
Question Number: 29
"
-
, i
. #5334' QUESTION: POINT VALUE: 1.00 i
,
. -
,
,
The following plant conditions exist: ,
'
.
I
'
- -
-
The plant was at 100% power when an OBE caused a SGTR and
'
.
.
'. sheared a weld on a ' f the PZR safetie , / A M,% , M b., e
* '
-
Ttle cr.ew f p"id cooldown of the RCS IAW f16GO.' las commenced >a,ra
, * ' '
V/ -
,.
* '
.
-
) %d /r z%
'
.\g Reactor trip was verifie / %
. ,
; *
Y Safety. Infection actuated and 'SI flow verified, +
,
y Q1
*
-
,-. .W a s- Con . . .. 1 gfand slowly; tncreasing. /
k.,feinment pressog;m$j0pyh"? hk?lf-1 . f I Y) -
??bWh, S/GilevelsTggroximately 50 Waded $ creasin D 4B.n.4En i M Bh
"
f,)* RCS,"pressu&s re;1400v
-
UV.mm 7id. y n&uan?) %
%* -
DF/N}b ~ psiggd'Ydd$y an slowl decreasin W,,, 4,90 . h Given the conditions statehAt%ds" p sadtionsjsh6Dld@be'take3 f or RCPs A' U) a,fhh,,,holu $hEfhIhQh&W (b?rb RpPs s
.
g-gkaMRd5 cooldoWi,[dge"ctediby Pf EOTbg8Ingped because
%iM 9MQj; 2%dh %h 7aN. w%
a
,5w 39 we's
.
Q,$ RCP op d'NOTj%,7..6eitripg beca prchibit amRCPgrestartind c>)psE'PZR s level > W Qi;gi,U Q* ,
...
-
'
.
-
-di . %
'The RCPs should be trhped because CCW has begrg61ated to G
"// the RCP motor .,
"1 e df -
A) .\
,
The RCPs should be tripped because #1 seal %P+is in jeopardy of
'
bein u
'#g los #
.
#5d34 ANSWER:$
< y-l..c .[-f o,
-
;.y (1,00) -
- '#5334 COMMENTS: ,
l
-
NEW QUESTION
* ,
s L '
l l ---
. . .
.
? . 5
'
- =4 - - . . -1- - ,r-
- -- - .- *w r-.- -. - e n e--.
. .. - -- . . -~ - . . ~ . . - . .
.
- -
, ,
..
- .
.
.
q .
.
Incorrect since this would be the case only if Phase B or other 4h"
,
"
= a .-
. SOP-101 trip criterla did NOT exis ,
, - Wrth a PZR steam space break, examinee _ should assume that
'
- -- '
PZR level' exceeds 92%, which is an SOP 101 limitation for.- . '. .
'
. starting an RC .
'
;
'
. . ' *
Requires examinee to determine that with RB pressure > 12.05i a Phgse
. ' *
trip crife(ria hidystapply,le'va!edAOAG-10 IsolatikihasIdcuir {" n ifYOP .0.operat' '* o controlled . . . stat
'
cooldowrfhas begu / .
-
.. f' %g
* ' '
. .
V . . .
,
c . , ncorrect since 1400 psig is more than adequate to maintain: . minimum #1 seal AP,
' '
.
.
{. ,
,
.
# [""J}
'
,z.h- ' Ngg@amBG$gg?
-
.
.
4% wa * a dr$w
..
bjk # y '
-
*
.=r^~. ,/w% ,Qy : %g < .
}
';g ($ r
,
hJp],$g:t gf[h ,%
,
'
'
. l .
.
UM}'g?
,,
;;. s nm y q :.3 W
. -- .
. 1. *.; 9 rA 3 eg andr w . . . E g;d;g s .c a- >
*
e Yy ~' e vl).
'
. " .
.
,..
.
.
.
..
.
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'
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w% %r c u ^
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. Ik1 1.a *
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4 . ' 46 >
.
4
.
S-r 4 w, , -- w, 1 - , . . -
._ _ . . _ _ _ . .
.
.__ - . _ . _
.
,
, ,
.
.
d
'
m r
.;1],) Question Number: 30
- , , ,
'
#5036 QUESTION: POINT VALUE: 1,00
* *
. .. .
,
'
Given the following conditions: ,
'
,
i
* -
Ths relay room is inaccessible due to a fir .
,.
~+ The S/S directs the N ROATC and the CRS to trip the reactor and C6
' '
-
prp, geed'io itae@hEPAh'dir.ect's the:, crew to place
. .
4 - From IN ChER, the s/Si . ,
', "4d/_
' '
,
"
- NJMdgF,'5.# % Atx Which ONE (1)wf he following procedures will the crew use to follow.the direction of -
,
;
-
-
the S/S?
- hs .
*
._ _
#
/
Y]e
'
,
.F gg
, , h ,027, Safe g k'/ b.
'
- #
GQ 8 hnt St$t[[v[nistbotitIhl5ho f Cold Stiff'down WithiC6nif6f;ho"mJnaccessiblEffQ@# AD
'
$
. gg.g.. wg gN hk(% 2#m} J}9Wengs wyn 3
.
. %, contropRoom5vacuationy ,,,
, * -- h= 4 AOP1600!ir$$I),474MhDliD:- 9M$i ' Ne,
'
i h pf-4 /g'{nttSfiutdoWrini6m' Hot l ( 3' Standby Due To Fi(elr[5Mii3}5'ul$il'n*$Ef# YNEhfG
I F # <f.,[6/4M
. '
ANS
% [f 7
,
#506]
-
\&w . ~*%f1@%g$f 7 ' W[' U
"
'v r p2 jy-
- O- . #5036 _f1COMstENTS: *
..
.< > s**
sGIgnificantly modified.' Changed stem and distractors af&s Rssequenced choices c & *p .
'9R *1 . '
FEP-4:Ofwould have been implemented for thefdontrol Room evacuation due to fire to sf5611ize the plant in Hot Standby. *FEP-4.1 is utilized to cool the plant d3Nn to coidifutdown under these condition .
--4"
. ( -47
.
I e e-
,y-
_ . _ . _ _ __ _ . _ . _ . _ _ .
,
,
.
>
O *' t Question Number: 31
.
#5037 QUESTION: POINT VALUE: .L ,0,1 0
.
EOP.-6.0, " LOSS OF ALL ESF AC POWER" should be entered if both
~
Diesel Generators are unavailable for starting, coincident with which of the following set of conditions?
. . '
Trip of 1DA normalincoming breaker, and loss of Pa.g,r ,- 115(KV7,fi.ne[U 3 pu I" , . u Ag . I L * ,
.
. , . .
.
-
ADB ov,ercurrent lockou.tb(51BXf
<~ e
- an .tr[pflockoutofOCB-8892. "(JDB)-not' ,,9 reset, pu
.
.g M Trip of 1DB normal incoming breake9/g 5 d loss of '
Parr 115 KV line * 3*
. . D' %,. <
I .
. DA overcurrent lockout set Q#,,f IMiisqf Parrel4QKVRineM[51BX-1DAL not de,4
'
# jf3 l wb.;;h
--c.x n u rs.%%q=~=ce ,.png:,w?r n
,
, /-
y %ggc27.n.%9. y &Gk::. ->;nMiM
- , ;% e ne .
_a ~ ,
~~
-
:.y+ s %w ng' .;y m+p '
#503J,,, ANSWER: e@w*s.:ks:[+f"k;r,?.
ijjg W > (7%, )
,%g .n rew / .a s *
r=m vt jp(1500. .. +&e.v-< w-mw.w,. s Ac v ,g;m.< s f t
< *
.m. . , y
.' *."; s
,
f
i? ,.u
.> -fna,c
.s,,ty;i-9%nw. -
w?9
-
%.d .1
#503T) COMMENTS:
I
$P / #7 '"*77 "' NN$b F~ Reorde?f.*g Y Gb n% HMMe$yW1 ?ffh s-b & c .,M p'EW[h% u.r;vr *y:mwn & ).ao Modffie% p u.7 &p3 E & W k b, red %..
f"3 be*8 R d:c$aq b OWi w e hms<M - & 6*e
-
/f i #%
the normalRsubjilffo"1D'A*&.3kithibBtih5D/Gs outExam.ine'etmustMeter and'lo b\
~
5SPY biides/~th'e ESFLS locks buhYthe normalincomingtpp//fhYP3f/ ' i,p* - alt, breaker 6 s" 5'v.' ,f. '/Ws
.
g'".*'
-
e *
\ #* *
W$ v- , % <f
* wf,/m (" 3 e
s) , t
,Qw hd p ,. ,
fh y f(
%a
'
*w,.
, r E ',' Y
-[sz f* . A.;.
. . -Cw
).! '
+
.
'
. . .
. _ .. _..-._-_. - . . . ~ . _ _ _ _ _ _ , _ ~ . - _ _ _ _ . _ _ . _ . _ . _ . _
, ,
. ..-
.
,
*
. .
'
,
. ).3 4
' Question Numbers 32 -
-
#5335- QUES' TION:' -POINT VALUE: 1.00 1
-+. Given-th.e'following conditions:
. . ,
*
,
.
e- . The p'lant is at 100% power during an A1 * maintenance wee ,
-
.
'
e APN-5901 as-beeni ' transferred to APN-1FA while -
'
woYk. mis t hfogrliis hn XfT-590 (
. * * ' ' ' ., , '. .
e
'q ' *** Q $ f r
_ ,. fTh * g Qu,ej ormal feeder breaker for,, bus-1DA trip.s open' etoafaultinthetripcoil.g[[ -
,
, ,
, .t t 75 ,
e "A"~D/G is tagged out for cylinder A,,nspection . .
'
,
. . .
e'. .
.
Q' bus '
-
. ] TheCRSimplementsAOP-304.1"toreenerg).tz 2PA- ~ cqgggm.rgg Agg ,
.
i . . Whic IfE (1) of lo ng describes 5 owethe "A" Tra in ESFLS t is wilQ.ferateunder[$t f ~Y$$odditions?-[MsThi@ ige 'tr # N5M
* Loak
'
'e sliedptndS$h'elESFLS will resume b /
- pN'# segun "
'
"61hcy,once' iti Miesst$1'dBall ^"
#%
.. . - ===
w 2g .,,e. ie. wRP 1
>) .,
-
-
b
+5 Ibad fishe'dgth,e_nnt'h'eFESELS; will rema ne in 4r Mandii9j$i6t$1filietD 38nEbbt bfeaker closes'~'or a
7 ~h
'
g
%.}is %igIternWtd ,,p ~ pf'e'edd"r g$
*' YEdker'1 ~ cl'6 -
^ se p, I
%.aJ c. %e , a.d s . ' c a.N,O -
=c *sheww ..s~
'
a,nde.th,e ESFLS will I'dsu. me ~ gsonce 2 sges.et ocall % spqugy!A eM// a
.
,
..k ri qd 'andi the ESFLS will
.
-
i Loads will NOTie b' e'
'
#-
#
, , ; . prevented fr'omj6p'eyating'"during the blackpt 7- + . - - conditio '
#5335 ANSWER:
x '/*} ,, . vA s%
- (1.00) N y> _ >
#5:}35 'DONMENTS; h'",7 i-yg ,4 Af n NEW OUESTIONN-- 'g Y,
,
- PRA Risk Important Operator Action #2 (RE: TWR
- in - TG10894) Incorrect since the ESFLS will NOT sequence even 4 fif bus'iscreenergize " Reset-locally" is 4:. ' aplaying'offa .a common misconception that ESFLS g r 49-
. .
O %
.. '- ,,-g --,.,w, , - , r.~,, .x w.ww-,e'---rwi -- ---+e--L-+-----~----%--+--+e ----------2--
-- ~ . . . _ . - . __ __- -. - - . - - _
.. .
. ,
.
.
.
~.
- VD
~j.",ig
%^
needs to be areset" (vs..deenergized) in AOP-30 ~ to recover bus,
. Incorrect since outputs from ESFLS,will NOT occ,u ' ' '
Requires examinee to apply knowledge of sequencer, - apply understanding.of Caution 2.0, pg. 22 of 54,
' '
-
i in SOP-31 * ' .
' , . . .
g - y Nt f
* .
dj.'g.," g,,fe
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s L ,',6*IL%
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t (*=t a%*& ,
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-
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ye
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m , N %y ['>.'t l{;gO.y,$f g%
,
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%awg i3 ;g}tedydy%w%B1199
% %l p
wramb NgeW:,.mdv v ef .i~n aws er > , - m t[ :ta A p:LM $
* '
;
m' n. s t RLgR%.. W :,tJ: 41: %Qc: qq n
$$?.) kN&y} ($lh50$ilb$hI?s&YbN.kki$y?s&q%V N
$.,1 * * 3"
.
g ::r C yye% WFM Gang * %p*agggm&Q ,, ,w nf Nghvq*:s#4 Ek#s$ ~% e
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h # rA - k Aft}s"h*%qqlMit@B%c:(E -
\
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r .s + .kIb W u h h , \ p\\ i y rh 2%< a r0 w r
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- - ~ ___ . - . _ -
. _ . . _ . _ . .
.
.
. . -
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'
.
.
.
%
.[. .,.) I Question Number: 33
'
.
'
#5041 QUESTION: ,' POINT VALUE: 1.00
'
'
Given the .following: '
-
.
.
, i
, l
. *
.
The plant has been operating at 100% power during a B1 -l i *
'
maintenance wee .
' * '
The plant experlepcerstloss of.offsite power with failure of both .
'
Didsel:G'enNgt'6fsito $$nq7diz6 tiie;ESF Buse ~
- - - -
- ; ; - '
s a fiftestfm{ inutes later when 'A' D/G isitahed.to r
*
~
'\ DA ' * *
" 3 The NROATC is directed per EOP-6.1 to ensur[ hat the charging
. ' - r N -
pump e ininiflow isolation valves are open.NROATC reports ,
,C
'
~
mm'A,gGI59 &1
' .
ejm Underith"ese
! %;
conditionsg q cW w.. m %ar&=m% n..gryn h %nmupfMVG'-8306 bs'op s k e w; N PlaceiT N
.
RWRICKO Snitchiiri!ON, then ope'n MVG 810 ar* 3'" sycUTwdyMMM
<
;6 (/
w'
. .
f-
. nxsh c.thbb $ /
ki #M h!I; y G f%
.
z + lace TRgP fr$me, ,5witbb'irbOFF, then open MVGt
. [;$.5N f[y10 R CgOUTi ig I!h d lj 3 -
g Switch I j p pggepTRN 2 ort "ik %g g~pn:MV p QPy(yL g 0& t(0Ug&g,n .h
-
.
ogopen MV bQ '2%stgGLu b Place TRN A l WR/LCKOUJ;Switish'd in ON, open MVG'8109A, b
- , . :. . , .
y. .
,
or C, therEhpeln$l j
- 1d6' $M
.
i
, .. #5041. < p/* ANSWER: . . .
'
e s
%a/ (1.Oo) .,,,4(..>
N' , <'
#5041 COMME $TS: u . .. T , . 4A'
Significantly mollfied. Revised stem a"nf all choices.- Resequenced choices' a.&'b ' T lM P Risk-Important Operator Action # 2 (RE: TWR TG10894)
.
b.'& c.-Incorrect. Power Lock-out switch must be turned o . g 1
-
4 / s
% % .s
__ _ _ ._ -_ _ . .
.
.
.
m 1,';$ Incorrect, MVG b106 is not interlocked with MVG-8109A, B & .
6 9 e t
4
4
.
e 4 g d, y % f- *k b9 *g
.
,
, , ,
*
L+ #%k. d 1 ) .f.,,3 r%
%i i(' f7,l' (/.
.
. &gg.\,,*n
. , . vf *
.
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Question Numberi34 N n;f. -
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.#5046 -QUESTION: ,
-POINY'VALUE: 1.00
.
,
c : With the plant operating at 55% power with all control systems in-
. . < ~
r automatic, FT-477, which is the controlling feedwater-flow- -
-
*
,
channel for_'A' S/G, fails low
, lWith no immediate operato . -' action, what condition will occur?
h%
'
-
* ,
% fry ,"h' wilbopenyMF,P., ppeed. will increase, and -
L
. ' *
S/d! %5 f,ddl twillli'ngr efe using P-14 to,close ,.
/ I
_ on y FfIV "A". f
'
.
- FRV A"willopen,MFPspeedw11INnbiease and-
'
' '
'
' -
<
.
-
S/G -"A" Level will inc'rea;;e, causi'ng"Q4toclose ' _ , g
-
all FWIV.'s; ,
. .j . . , .
-
'
. FRV "A" will o eng MFPpp.eedwillpeereifeL '
'
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'
"di5'giting-s agwh crelsieddfEsdwatfr flow 26/"B" 'and:
-
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#171"6dOEeapl}jlfS/r1 eve'lm W A$j%rQgid
' FRV Q Y lhA VYTt Aj!!wa11 pen resulting3 1njan increasedMMain hh?W .
g*% Feeddum,p'Ta eedNfil 'hYd$11hedUse a hi-hi lelel on ()
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#5046 g .
.
COMMENTS: ; 3 g (edf, f f ,
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}NEW-QUESTIbN \( h),
./ j **
- With P-14 : locked in, alliFRV's will NN
.
ka)-Incorrect
/
/
_iclose.
-
. .
Gricorrect ~--- S/G's "B" 'and. "C" Control Systems _will
'Q
, /sphbilize--levelsatsetpoint..JQ
-
; _
_- A j a. ,. r Incorrdeg"- FRVfpositio(_doesn' t . impact _ FWP spee .V4 *
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;a Question Number: 35 #5341 QUESTION: POINT VALUE: 3 QQ Given the icllowing: ' * "A" CCW Pump is running in the' ACTIVE '.ain, "C" CCW Pump is in Standb ' * "B" CCW Loopis the JNACTIVE Trai "'h .,f ~} j ,
o Dlscha'fge}y presbur[e% 'f'6r f.f~ (Ay JCCNjPump drops to 50
,
-
gb lg,Jand the "CCW LOOP A PP.*DISCH PRESS L.0" j
. . \a nunciator'has' activate N ,d g , , / /* . ,
Annunciator "CCW LOOP A ESSENTIAL LOAD LO LO" is
' ,
4((. in alarm with flow of 4400 gp C D w *',ea,
#,
E,/"#Ie
*
Thermal barrierxflow totthE$RCPsfi's # 80 c) ,j and
,/ f thcN.j,'R,C,P n ,s A/B/C$ THERM 1B'Af. &,.BRG7[FI.;O c LO" En,n, unci ator xv**/
[g iscact:1vated
%g%s.: M( -e g%,
.+ 2 sua-M
,
C .' t. . * i . I N. I . La f ' s* * CCBP,idi's, . , ,. p 'r3Dt,chaigeepressursfisE85fp'si .# g% y gag cogm ;g:.c. Q], wa gs ma ~sq* p;;ge ,- t , C,y.7 q Jg pp _ x yp,f
. .% Whibh*ONE of the'foll'oWinWdescr,i3es, tthe'iist'at'us of the CCW,.Jystem *- @
n Uj WWM@MNf' j4 h giveng these R&%reonditio'iisMd]GyQiW1M
' Q :, M' /y,LC}3 y t
a.950Cb e v sand *non -- - l valuesfesd6,Etial K.~floiidldsh,,e,nEf,a$, loa
%becestoredFto rnoinina
,
f611owing automatic hp phj p M
*
9dtiN{g.,j
~"*p3 6Qh%sEahdt3yjcCW fyg]Q3
_ pum' %'~ A h)g b. CCW flow wil1$$enreddcedto'g pessential and/non- - essenti[1 l'o'dd6]iehiihehCCW or CCBP stan[dby# pumps
' , ,
f{,,r -
.will automatica1;1'y) start'.' .
Q@<r
/j-[h *
e q .
.c CCW flow will be reduced to essentialeloa'ds, MOST non-es'sential loads will be restiore'd to and
#
.e nominal values following automaticms.t.da.rh of the 4tjandby CCW pum ,d. h
\n
.$' 7
, CCW flow,to essential and MOST*non-essential loads will bE"ientored: to nomina'l values following automat'ic star ( 5f the itandby CCW pump; thermal barriers are isblate ,#5341 ANSWER: (1.00)
#5341 COMMENTS:
I
-
.
v _ . _ _ . _ _ .
-
.
,
.
.
m * , m.- A,9 NEW QUESTION P . Incorrect'since standby pump automatically starts at 45 psi ,
, '
Incorrect since pressure to CCBP's is enough to
' prevent CCBPs from tripping on low CCBP pressure '
of'30#. '
' Incorrect;,, sfuge RCP therpal barriers have an agBomatidjcl6sur#"bffth6 jhermal barrier return *
*
. ,
flow h/d^ y l.veMn hidh 'fTo~wl(V.~p - s.ip.Iow flow).
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f,' @ Questi'n Number: 36
#5336 QUESTION: POINT VALUE: 1.00 Given the following plant conditions:
* The plant was at 50% power will all controls in AUT .
* A loss' of_ ip'sprusidilt'" air forced the crew to
/
iJtiplem6n t"'ADP(22 * -~0~.'i .k.".-3- * .
.
- ta s - lu a f / /. *
rd'a actor trip and completing EOP 1.0, Immediatie -
, Af ter Operator initiatinT): Actions Ehe CRS directs the ABLL Oper,atbrgto the IB-412'. in ozder.%o take the following actions regardin*g XVG-
~
,
9627A (B) CCg ~~ SW SYS OUTLET HDR CC LOOP A(B) XCONN ' VALVES (S) . E ja , Locally gag open XVG-9627A(B'). torest(.o5e af CCW Surge r
(#1 & * TSnk ~h leve1 ~
g~~-4.&n,lLi "u2
,,~S M T -f d ir Verr,n Y fycachumulator
@ % QR~ &**'~MW air pre,.c* 9 W' c}
& &s XVG-4) ,.
ssurethas opened
,k% ' 9627A;(B)Ati61Eestore CCW?SurdeETshk level .
,w 7 g -
,A Locallyfg,sg clos n o 9
N,.,96EXVGQ627A'(B) y < m .1-f ..,, y i to prevent g% #
; [\ CC #7 4 overflosing,s ym a<hq'.3 t
m..s w., p, w,9;%y~y surge a m,. liTank! 7
& t g w 4 d ; g , 1, AM" *.. /..p.7y u- 2 c . .,g
.
'- s hf .1
~ .^ .i? r * XVGfS627&(B)QiaveLFAILEDeclosed on losau of U() d.NM#erify)ienEgh5EtT'
DYdit tl '4slkssic1b~sedstoiprevent AC G M ef,flodihgaths EC Bhrgd" Tank.%{/ ~# ywE-m _ A%,.;l ac fly &jktI . y g p ar., ir .
%. .
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#53b ANSWEP4gQ ^
mryW pq,ng.g,d Q(134 $. F' W3ewmahy.g%;/g.) kg
-
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.#5336{ -f
-
.COMMENTf:
L m{;n;
" ;,g g)7 aw -
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'
+
g# Af'ignificantly j modifie Changed stem and ,di'stractors
,.b ,T c , & d. Reordered choices a, b & c. s (,)- # s ..
Q Evaluate response with the position of PVGD.627A and B on lo % .of IA. Designed to keep SW} valve 5 closed for up to 3 hours.on loss of IA. Af ter~the accumulator associ ated fiilh thesei valves:bl'eeds i>f f, the valves fail open, 6verflowing~'the CCW* Surge Tank (SW at higher pressure than CCW) with no operator action.
>
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D _ _ _ _ _ _ - _ _ _ _ - _ _ _ _ _
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.
.m
.'d Question Number: 37
#5342 QUESTION: POINT VALUE: ,1,.d0 The following condil.tions exist: ,
e A reactor trip without SI has occurre e The operators are. implementing EOP-1.0, Immediate
'
Operator,Act'i~onsPi ;% i
.g y ys rf-4 i -
'
* Ahh$c'd5[Nohpo['$:n.j,msit ibn\lnd'icat-ions shows that on I
(D'o' , \. ;.rdf rod has not fully' ins'e'3rted,
.
-
* . 4.y g
,e s T . ,
%% % *.V;The taning ac operatora ion concerning continue the with stuckthe 'rodh proce'
t dure without y t s .,r . Given phe conditions above, why is Emergency Beration /OT, ' requirecf'at tl. intime? .m e A.gr be
,jff J um VAQN W ,7"A~%FN'*Q u ' %; y w g ?) .%*e Emergency 3boration will.soon % N'beMequired, m ,
I followingdhe transitio Mt'6[EOP21.1, " Reactor Trip WCw
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,
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. j Mainthi.n.ing a *s e shus.d6.w,,n,t,inargin is ONLf"dg fpconcernQf611o.de'auat.is -,.,-
j"" wingf,a :. reactor trip with RCS ( #' s 4 , . 3
-
ft }
^
d's c t
;o e.mpe
- ra turet:less Gth(an f557 Fi[ and 6de cre a s i ng . =.s~
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.
J# g$$v)?C
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M. N N sn ?eff e~ct sh,utd.o.,wn :,m,nt.ro,hrods thatto.*"" m,u_stJ stuck
- ..- . .
p% a a.rg xtent yg" . ), . Semergency o r a t
- ,a i o n t
c .s i s
. requi a . t o t .
h e r,e.rede Q
'
hj d. ]$Qi@S47'downemargin Adequate shdt f b y 42Cpjd wrl1 be maintainecPeven , A during h^n tinc6 inn 1'ie 1 'RCS cooldow dd y:# n q t ,\ A , %.; : .e ;,,>
.\ s ~- ' ANSWER: %
4 "r *
#5342 "M~lp *
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+7 ,A, ~/
#5342 . COMMENTS: , \
,
, , ,..
.37 Modifis C,h,anged order of distractor .
.... -
.>
-
.A
,. EOP-1.f'only iequires Emerg. Boration if two or
, more rods are riot' fully inserte Suberiticality/SDM must always be assure Boration required from two rod . Requires analysis of intent of step and effect on
.
_ _ . . . . . . _ . _ . k g i
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): Question ~Numbe : 38 , ,#5338L __ QUESTION:" POINT VALUE: 1.00 -j
_
-
.
'G,1veni tlje Jfollowing: -
.
'
\
With the plant-oper'ating at 804 power, a reactor
, e - '
': trip has occurre ,
.
.
. ;
. . .
.
-
e The Controlv' Room)))etatoks have been directed to !
* '
EOP-jfD, ,l".Shs' a m Geneht6r[' Tube Rupture, " for the -I
. . ,.
ptpp*io'5 fan'SGTR.'*Q[[f r .
*
- -
'
.. . e ..
.
% ,.
'
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-
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e: AQpi part, of . isolating' the rupttYredCS/G,' the
~
-
.
,
\ g been adjusted from 8.40 to 8.85. associated .,
*' -
S/G PWR RELIE
.
.
;
-
Which ONFg 1) ofthe'followingdescribeswhy~therupt(rs1 S/G SG
'
'
n -PWR RELIEF Setp(lpt; yis' adjustedg%,
'
.
ragays . pods %p.E.~ !f .
. ~#
f [w
" En eIdha the S/G c e[sft valves wilt open -
b ii bef6Eehtk$2PfR4ELIEF,551EF6dus forq PW'RR to watern nihiiHng the po
# * %J5306Nf ogenF ff .$ h h h %,
- 4.Q,3
" ~ ~
. ..
(f) AlloWsh bhe PW
~
LIE h rh/ducee f sr3 mary.;to-seconday re prior to ope ing
.
V/ akage,: ^ C ; uM+ %., Dip :
$h "
(
.,jektsphkljRjREU 1 fromfo,[p[.gning,
^ i . as ru red De- .1S/$5Me,ssurefscannot%,n, crea above 1150 psiga
\' dpxtygR:aneSGTK
#
#
%
f>'
'
f , f* i ' " ' y . Minimiz$ es PW IRE EF%cp whilepre(enting- v
. . .
3 ja'. ,S/GCodDSafe((jajveser.ation,fi'm o opening, t
. ..
,
#5338 " >~
_/}- ANSWER:
(1.00)
'
+&
f]\ . .
,
4 . u , *
#5338 ;CQMMENTS: y{
u- %.
*
Significant1yhmodified. ReviI6dandreformattedste Revised and'resequbncqd all choices. Changes correct 1 answe .. Risk-Important Operator Action _#7 (RE: TWR TG10894) ' a.- Incorrect.. S/G'PORV should open before Code 1 Safety _ valve ~
'
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__ _ _ . _ - . . _ _ ._ _ _ _ ._ . _ _ _ - _ _
.
.
.
. . .. JS 'W - Incorrec _ pressure w ill Although increased ruptured S/G '
result in a reduced primary to - _- secondary' leakage rate, the setpoint-is adjusted to. minimize atmospheric release of the ruptured
' ' '
'S/G. EOP-4.0 reduces RCS pressu.re-to minimize'
primary-to. secondary leakage rat . . - c .- Incorrect. .WOG ERG concern is to prevent lifting ' the S/G Code Safety valves, which are set at >
'. '
117 6 psig,. **", i a*
,
o, y yg LA
* * PSr if0GI ERG Backg["rotf6d7""%
*
o'cuinedt,- for E-3 page 59_ h t ..t - /
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Question Number: 39
- 4
%' . .o ~
.
l
#5337 QUESTION: POINT VALUE: 1,00 I G,iven the following: ,
'
!
e A reactor trip with SI has occurred due to a SGTR I onB' S e Thecontrplyrgom(dperatoyshavejustenteredEOP- l 41), Steam Generalo27 Tube ' Rupture, from EOP-1,0,
^
React'of*. Trip /Safet "Ihjhc51'on/ Actuatio ~
.
-
,\}* ~ %El
*
condition [sjareasfollows:
.
Plant
% ,3ll /g5
.<
,%,*-)SIflowonFI-943, es CHG LOOP B CLD/ HOT / i FLOW GPM,
.
,
g r
\ is 400 gpm, -
42d ,
-
t/) e PER. pressure-1350-psig4and$ decreasing ebj
/ ',.
e DDh NuMAO65DMi[57 4 y%j+ > PZRA:evel,&30% and decreasingusiowly q w g . p4.u .r, ,[ n ,.. ;wy_. g.mgy' 4 ....r , e s~ Rupt;+bre..d!:pG;,
,. , . .
press s.ure c,,.-.,,,, , .lpBO;,
.~ w a psig;. 4 j ,i
,-
w r w_ . u.a ; p % y .% e RCS jub'cooliingion TI4.n n,e~;.99A(B)i,9A (B) TEMP 'F.i'sM35*F g O l* h(40 i[ jpi.M.][1-E M - (/
~Y ' .
f\ YNY<Ql.fyl&Q.hQQ:Q.0ll$;[,-}g Eei ~p Wha lt~must +:-- beklone$at
; ng MthisZpointAand2Why:?
ze g r. b n M M gi fs % Jh w Lc W . ty { g,,1
~ char.sgm,:n.lgrp.[i [ p; t y; d ope.r.s ate > val,ves a NSta.rt!7 i umps;:an (.+1 gra s .m y$necessaryi.andigo;
.
. .- -
toFEOP}4.2ZiSGTR
--
with Loss %gf e a~ <. . ,c., ,. .~
. t _a g Subc..~ooled; Recovery Desired ,.
.
, .
i Reac~ti" err > Cool hJ,,,- '* Q Stop thEtRCPssiWo@rddi
,
4 p// ,n QN \ , ~ fprotectito(f' agains,t>*d
/"fy -
{g .subsequ'ent core (ya' mage'if forced RCS floh/was lost e- # ry later during a concurrent small break LOCA(
Ils jm Q
[c^.'N h" eat input '/ Stop into the the RCPsRCS, thereby in order to minimize helping to th'e.5"RCS reddc ' ~
pressure to equilibrium with seconda[' pi essure., 7 :.. M 'Ds'e~ normal PZR Spray flow to rSdbce RCS pressure to s tE! ruptured S/G pressure 'to minimize
. primary'to-setondary a m leikag #5337 ANSWER: (1.00)
,
#5337 COMMENTS:
.
g-- _ _ . . _ _ _ _ _ _ _ ___ _ _ .
_ _ . .. . ._ . . . _ _ __
, ,
.
.
.
M '< ' Significantly modified. Changed and reformatted stem and changed all-choices, Subcooling and PZR level air > Reference Page
' minimum values so transition to EOP-4.2 is not'
-
'
'
require '
. RCPs are tripped to minimize heat inp,ut in other ' * -
EOPs (ex , EOP- 15 .,0 ) , but not in EOP- .
.
-
, m, pc * *t o n
% . . . . R.CB pr6ss,ure,. " ot rediTced t until later in. procedure afteE"'liCf h5s ~
een ' cob 1'bd[d'own ,r W
, , . -
Pi '%.) l '
. I N -
y .
,
.w -
$ $N g 4// .~/
.
b$k vzwno 9 y;$$$$$$$$h; ass&p&y$h m f ~, s y WMiWOR r. woa mw BWBRM mo 2 ,
%;% w% w.jfh s ,.,Q:= r #%
ssva' g khh 13M t f?
.
L- 4
,
mpa"$n t4 .t .L,x l w w?. h-
.
_y
;' Y.) thg i pKP 9fiW j
==
.
t" ) y w . 4 ,qt mpa
.... s tut N 1 LeW .J
i j4,)-4 %y h:am+/WEq$Q2% a es.gqgg&Wpinga Me j + q ,h ye AA eg% nh e e~n q
,
%
F . %y EV ~
% & &
* s* '$ bh L.kbhf g' ove h " r, N ;e , %
't
$,h [S'?l vlff.\ s,$s 0I e q u c'}j} W} '
-
w w . . v\ ,], " A).;~, r
= . .
v- . -
.
' ' " / '
, _f
,
/. sv
/** 'D*)?
uh
,)h,4
\ 'i
?r (
, j . f**
3 yg,3ns - , %,, &
, .x .=' s
:%g K *,,P
:
Q' ;* .
4
.
.
+
.
.
.m .
"N,4} Question Number: 40
#5346 QUESTION: POINT VALUE: 1 00 Given the following:
.
* While attempting to restore PZR level per EOP-4.2,
"SGTR will Loss of Reactor Coolant: Subcooled Recovery Desired,"'a grid disturbance causes all 3
'
RCPs,q jp to trip" yon niide pufrequenc gi f
. .. r s . * RCS s~ul5 coo .ng on T&499AjB) ,/A(B) TEMP FF,'is >' -
60 h F ,7 %f
' ** , .V (
h . .tSafety terminate Injection has been reset, butenot ,
, WA' #
#$
C) All P'ZR heaters are of D ' <
.
\% ,,~=mw~~MRT? f t
#%i
! 7* Tie 3dispat6heNrs38FEElliSt$.th'h$g$1d wi1Ig"robably #
pAf+I reliaish.ud ~vzytable for anothirfhbur v , www pu 9.:, s w" N Jr.5b g f;C""% ~3 A ?5 M N'k" Givsn phese conditi$r:isl;;lJ,'wh;ich@NE i 5(1) fdfhth$$following is([Ne prefpired method of:7refilTing tibe7PZR4whife?6cnserving reactbr cooldnt
;n inventory s aiid@s+oiiidings. t;h.e[bistSR'CS$ressure cont:fbl.:
q .- 5 Q), 4%, 4 4 +;;;:~., L!gan & y ,y. B, mci A x. .+ 4o
~:). : and establi:sh bp) a.t-4sStop Wj3d6imal a'11EbutAONEd+(1-)ichargin;g Miialynip?I;EdF1htidown7 bDy pump / 'C c . ;;.y :. y "in e t L u c y'"N .ip was %: .7;',v ~ Y y h V f! y y urs d .A b. y,rCyclWone Z PZPJ PORV sashnecessa%gylgA 'ry. ! #y,_
k,M+ dat h['^d.i,ately imme-
. .
"[r.es tart.If,derik 'NfdhbdmMk CRE" A. ".w?o.r " C " and e s t,'abli sh
. ~ g5 g .
-
kt(,,,s-
\f)# normal 'PZR (, Lilll1 fiprag.\ , s s /~p $( A . .Establi'sh noimjii[H WLI >l1c'hargi'ng' and auxiliary ig2R- ~. . <[#.y d . *< #5346 ' y//n ANSWER:
f%(a ~' c
./
b./ (1.00)
%r t. e \
#5346 _ COMMENTS:
,
, ,
>?
~$ ,+
Significantlyfmodifie Change'd stein and distractor Reworded original corre'ct answer (c.) and changed answer to (open DNE (1) PZR PORV).
. Used in EOP-4.4 for loss of PZR control but not EOP- Requires analysis of advantages of various options to determine basis for actio .
.
.
_ _ _ . . _. _
. . -
.
.
.
.
'
,
. .
r isq) -RCPs not available for normal PZR spra .
. ' RCPs -
would not be restarted until an engineering evaluatioh is done and the grid stabilize >-.
,
*
. GI'still in servic .
'
.
.
* e
, . , .
,
3 cut,- N*z f** w g vlr#
* v (- y J' '
. . .
.
a* ,[ t , .
.
. .
. )* v f,A i .. '
~
A .
#%f % ~
kg) '
,
!
.
% . .
b
-
. ,),e '
.
i)
'IEnAo, Ediff5E$m w- <sMcNg n na nk . "*! tAWdTj;i f $lk".lDIAW2 E ,! T:ditsis.vu*, fny#A%ME?
mGMT - u~n Y[50i'7 dis 2 wse, e } [S (e
,
eq"#
.s
'.;s i
@e)ffSMg
~gs l%
j
~4_.w,-A *%.
~hM7ight w*
-
.
4@.)' f,~. up.hkEs -e%_w~ ppg.s-4w.as m (f%g , a : .. WKlal% $
(' * e& %w#JJ w i d- ..
~g ya$ws$rs.q$p$,y$OV@&
$y %n
-
hdi?$q{va$lhh"d C Y%ge isien v .. V %- v,<. hh??}L@4R!!)kKE@
%9J$ S$43 w% 4y w:bnw~.o 34'
N- .
.
s ,.
.
Nfv) g W
,, --
~' .
%4
& M
,, *
+.4
.
,
.
%
tb*
[ 7,w
,i- _ d 1
-
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,,. *
.
' *
, . .
a e
.. , ,. -, ,- - . , ~ , .
.
.
.
4. 9.4., Question Number: 41
#5347 QUESTION: POINT VALUE: .t, , Q Q Given the following: ' * The plant is at 100't power when a malfunction in .ne SGWLCS causes a low-low S/G level reactor tri > -
e*s g g V".: m %
* Af ter-trd+nsitioniw ,tng ttr EOP-1J.1, S/G' levels ,
contfiflie[EiPde'cr5ase""duh.Jtio"f a'ilure 'of the EFW - fpt .'ap,s '!"~ 'V/
)- , .
s s, , g%.c .w.*%a,*
*'
%g. After implementing EOP-15.0, Respo.ns\eN.to Loss of
.
,
,
Wx
. Secondary Heat Sink, the crew notesft hewfollowing:
(-}.
p, 'RB pressure is norma p.,g
) ; / '&% reMU"BMTOS g65 - n;p RCs, pre,ssureAisE2280 psig M r #4/
2 .r s h; ~~ .+s en,:- m m.m(bN2'I:, f Nl[ 4 [N ..J %
- 8.. a.n. ".<~C" d no ? WRiil]$evels are,21%23%
- N:S/G.!G-. " .[. ..EB p%an'df221.'
(A
.
-
x ~dw : 'Trespe a p %,m. c t ively. w;,.m '. Rv% tyM 1'Q j* M Q,f, W CQ'
, .. &y z% j
,
taa,a t
-
JPREccnditions
'W 'a :gg;jj+%.;V:x;j.;,;rma efno':*. .
.
3"*:n " ;> .c ;np h qnW oCf y# W
# e t@; EFW . cannotyi n, Sw4.'f.RF,dyatSlth'
restore
' ' . ~.w w e N f's time . ~n *
k.1 ;+A % Dd rn/ Given these p_l,D.lm"?;c,ondi,t a
' QWons
. Q- wa:j Why,Mb:R. u . w
*
;
$,.% C
" ~""
ant raretth~e RCPc5st opped immediately d$d[dit>
'g, N['isdndet'e'rsined! that EFW fcSIIri'o~t be restoY5d to aerKi.de? \ ,
t % ,Q a w- m
",jQQ(J%;pCM9~
.. . a %z s -,s %
M 4 7:g; ig , p% k h ,
, , , , To*' reduce when SInflo'wfis RCSr.p}ressure b'atheli'she topmprove f!marg.in to#DNB %
~~
.
y/,Ab . %j,gb1 'v '
'To minimize core uncovery and prevent Inade'quate
@
'f/ Core Cooling conditions, f* Q
/f%/) t i N b'/
c/
# To remove,an RCS heat input so thatsaw .B.l.eed-and-feed determination can willbebemade as to whetfei or not RCS requiredr7 _ abe To del a*'pithe need_for bl"eed-andif eed by reducing RCS hestiinput thereby gaining time to establish a means of supplying FW to an S/G from the condensate syste #5347 ANSWER: (1.00)
.
. . _ _ . _ . _ . . _ . _ _ . - _ . _ . _ _ . _ . _ _ _ - - - - _ _ _ _ . _ . . _ _ _ _ _ _ _ _ .
. .
.
. .
.
!
I
.
43) #5347: COMMENTS:
'
u ; i Significa'ntly modifie Rev' i sed and reformatted ste ! Changed distractor Resequenced choices c & . . .
"
Risk-Important' Operator Action #6
' '
'
(RB
-
, TWR TGiOB94) . .
~
.
,
- No' direct effect on RCS pressure (reducing RCS *
* '
1 heatup does indirectly reduce pressure). Reducing pressure ,wili] redticermar, gin to DNB.,
'
*
,% / ) ' ,
, Bleed (drf eed *g p;' p p- ( "fo si pi gde by S/G WR-leve'. .
,
,- , , , . determinat
/5ttdfCS'yd
'
*
,, . pressure After RCP q ip, RCS pressure i
.
\\apd temperaturs are expected to. 4n, crease; crew - !
- gQ%QorsecuringRCPs
,
.
.
. I6ust -
Presence determine of RCP hcat doesn't, (ERG if this FR-H.1, is StSp-35 prevent due to' pg K6ss%f 69). hea etertaination , je C0 * Cqrgec (d % .tgw Trainee & GW'nn M2uathyesearch W 's &
' -
f
.
A,f*/ d . dede(Si'neWha't is occurfifig%'aEE;the f and redlTie EUPthat Tor
- / i4Wefated , .-
N achi'oi@Qyp q*;M fg y 't IM@&MgwR,'; M# -
%.+ .
+&%3 w e g:q
.4 aqppe%m W $4;g (/%)
% -
, % -
,1 "~
en
$p%y$j-4ff' ,e, ,
7fyy~;;jgd7~ W s .
,y.. q ,,, .4%
kne %.g m $dH,g4e ar h pv 3 Lpa q.;W9M!p,:,pg;.ng ywMi n g5q a ep
--, -
Q_). y, y e$.g ung qvupw .r ~ Y,q,9 fy h $ k yY $
'
(,,a
%ypkg 4 A s ' h:'gWy ViG q g"amym .
M Mp',
%.A % ~
f,$. a
,
'
,,
w- 't i
'
-f [h s(k W'
n a renO7 ch
. ?' . . , ' ,/,.
J
.
- ,-
'A /
/
.
g%y n
;
* *
NT
.
-
-y
.A ,
i., uv
'
[.. p '" ,
J'be, 4'I, ,,( Q )pqf -~ L*m
4
1
66
.
# .
n .
, -
er , , ,- ~ , - , - , , , , _ - .,w.-er---- -ew--.m + ,, --
. '
.
.m
$} Question Number: 42
#534P QUESTION:' POINT VALUE: 2,00 Given the following: '
* EOP-4.0 has been en'tered from E0P-1.0, step 25, based on high secondary radiation level ~
e EFW has been+fsol'sted-from the ruptured S/
. 9, ss G 'y.% , * An,RCS'~coolBohnha)s % f '\
eendinitiated by dumping -
*isteam*f~ rom TWO (2) intact S/Go'. .o _4 .,s y~ -
w A .
'. Ar buring the rapid RCS cooldown, *the AM" p\r12 permissive ,
sm\ Y light goes brigh I % N.>
.
'
.
.
The "A" RO places both STM DUtiP INTLK Swi\ches to * g'") V* * liYP,2NTLK ' and-cont:inues" t& dump,. steam in}tilje STM
,f Ir PR ~
mod f i(t o. M:hE " rsqtti o is c' .RCS u tie mpe r a t u,re . u $5,i!!?u %
/
Nl,, '1 1 o h. A ,mN). -- ?,
'!-
M
*
['% ThelNROATC?neg;lects u :,...g t uus- p ;r < u , to, block 'the[steamline S . -
;"', * Prior,.'; to /completitig? the,ncooldlow,, n , the SE (es p ~ t r; reports
>
y q% heatin gcup and the ruptured;SG
~
.m '3 j ""' /'sPORV(injcyclin5p .that7thelplant/is '
" Q ()
'
J s.JA (m 9 . 3 , s J/M . , , " -
.~-,
h-%) eYITliefc11ow'i'ngTcoNdEl'nEexi"stI.' E t s ;o
~
C[
..
c% . #j 'g :w'.'7 w +'., .n n p if n p p,c.1+ ',n q pyy .,;2
;e \.jy-'/t-RCS cubc[ooli;g .%_
r-v ~
( )g ' 'AyAijavg'fis7522F Mi .is;x40* /"$ [I [, @/
f ,," M
\ ~3;>;i$Rdptsfed?fS/Gj pge'soufeTir 1130 psi %
hvg ',, ,
- *
S I s f 3 cw pi s'(4,000gpm., -4.; Con'deriser'/vacuumi ont PI-3 006 (3 016 ) , NAIN A (B)
/ py -
PR'ESS INCHES 2HG', ~ Fea'd s 2 . 0 (2.5) iriches .
~. . \.,",,,, v */
Which ONE-(1) of the following describes the cause (s)"%of'these
'
"
plant. coh'di't, ions?
<
..y. w I
/ 3 ,,s , Loss of condenser vacuu N
,
,x t- ^TE5 MS.IVs :. 3 , are close .. ,
,
-
.%, The RCPs'were'['~ rip' ped as required at 1400 psig RCS pressur SI has automatically reinitiated on low steamline _
pressure on the TWO (2) intact S/G #534B ANSWER: '
.
. .
._ _ . - .
. _ . . . _ _ _ - .
.
.
. . .
,
I i e ' I
'
Aj) (1.00) .
.- #5348 COMNENTS:' i . *
Significantly modifie The stem has .
' '
choices a, b t. c.have been revised an,been d reordered.-revised And - i
'
Risk.-Im,6ortant Operator Action #7 (RE: TWR TG10894)
'
;
' '
'
Incorrect yG4verd' valve of' main condenser pressure ishless tbaffC-9[periniseTve,(5" Hg abs) .
,
- '
* *
,
(Co(rr,e(ctiMSIV Isol.%* Cf / / f
,, , , ,
, fit . -
. .
. on Lo' steam pressure without -
I
. \pfo'ckingit'at552* '
'
\gdg%
'
.
. , ,\
.
o Incorrec RCPu are not tripped on i f rapid
. . '
cooldown, and condenser cool _down can (still be * '
*
ytili' zed without RCPs.- * h#
'
'
N;A f5E'IEITGepO N 7
- Iqcorrect. p-49preventstAuttsydIgifnreinit OP at[on, and~ /[ "
i ~ fl%
-
nue SI!?slibbfd3h.6f,p
[
coolinwm the7RCSiNBF
. j,,
,, f. ... h Ajf * 2 ?
%
*"*'f
##
% .dl{f@s'A
.a QTT t%@;.af
/
7=s.a[$. <,
" i r%% W ','*.dh' ..
..
",b
.
~ a-e#
M% W %..jf, '*"*am;.,. % ;b .. *' ".$'y VWh T W i gum & {g\ s 5 (;,:: ; # n.4g h .n.' a
. ,v..M i y4 ~
W La#
(f) $! IM$ $ i d Ay Fr.s*chy(
4 .M
%n?,4%. +wa ,
i
%. $ ;s,a o%
c j $ g[ y .:.1tua&
,
p j" M*
.
r
.
c j;d #' MA M a
t* f s f%.6 'kh.gf- '?# ..N 5) N*:f ,, ' o g'i . , f. & m,h,
44 t
.g a&&g
*
*
Q\ k%.es94
-
##f4 j:}Of'% ., &lgNj Ap
//
t-b, .
. ~- . .
t-s ', .
.If!.@;.y/[Ihqw\\;JIiO
. ~
cnd.#
, .t , .
s l
/.
.
w fi
+
Qs s5 .
sA s
[ p> . F ,i .
3 %A
*,;* 9 f f ,a .a'
ge 5
~
* .
**
_<
'r=.) * .
.. .'m.-*'
'
.
9 I
.
_=
' ..
m 8, - w y .- . , - - , -
_ - - _ _ _ _ _ _ _ - _ _ . . __
,
_. .-
.
.
.m .
,**i..Q C
.
Question Number: 43
' #5350 QUESTION:' POINT VALUE: 1.00 The Control Room operators are responding to a small break LObA whe'n theya identify a red path on the' integrity status tree for -
EOP-16.0, Response to Imminent Pressurized Thermal Shock."
After verifying adequate subcooling and RVLIS level, the crew '
'
establishes normal chargin ' O ' UYJ . TheseactionsindOgdi6fl>g5wereperform6htoachieve'whichONE
" ' (1)
e,,J ' ~~' b d~s/ // / ',* -
,ofthefollowing:(y,(lowuseofauxiliaryspr$yitdtheeventtha
.
.
'
I a.3 Jh al .
.
RCPs cannot be used during RCS deprps'surizatio d .
* . . '
Reduce unnecessary injection flow bec/aud % aubsequent minimum values for subcooll'5 [eWill be '
. - ,
r,)
%/' *
1%er thari ormairSI*teh ina'tio driter a "3i , d p:ufetWM21%p--- "/
,
~~ a w m
.y/ f c .. R uc.of s%u
.
y,
. sequent RVLIS ,mi.,'rhr nimum;. level requirements Or h ,. and@herebf4 i allopRCP i rlj.stytij'6 equalize s _3 e"
tem temperaturec,b'( DN$ f~ E $%$mMNw y< [*
#
. EliminathtSIflo '
.q I""' felim'iYnatibTthe*pEis_as_ so'urceFof' RCS cooldowrfAhd to ibi10'yfofeSI causing subsecluent CO Tih$$" Y$y$ h
#5350 D/ ANSWER: t
%j y 1 g h[fA/dfdW c
"(~ J !\ rd N@N" sy #Udhyl %
~
. .
""%\. ,y Modified
' ***"'
by'N '.k.Ls 2)
%ling'distractor resequen {h ,f 00' - .
.
.. ,/ a .
g,. Auxiliary spray would be available eyeliNif SI flow
' g/ } still existe /
/ w . . Termination criteria is relaxed'in EQP-16.0; fowever, subsecuent required v$10es of subcooling
. meet or. exceed normal termination values,
-
vt .. ,x .-" -
,*
~
.x , . . , e This tests examinde knowl'ddge on the basis of RVLIS requirementfs of step 3 3, immediately after normal charging is establishe RVLIS level '
requirements are based solely on RCP status to equate to 50% void. content, Correct - The examinee must first establish the
,
fact that normal charging means SI is terminated
~
,
.
% .
. -
_ . - - - - - -
_ _ . _ . . . _ . . _ _. __ ._.___ _ _ _ .._ __ _
. .
. ,
.
.
l>
.
-
,
,
. .
;
*
l MY and then evaluate the conditions that EOP-16.0 is trying to establish by stopping cooldown and ! preventing repressurizatio . .
.
t 9 9 9 * e
# f
4
. .
,
;
'
*
. .
,
,
'
, t
$
$ gg (
*
*'
[
'
'4
, *
CJr
.
\,vv
,
- -
; . ~ -
. . . .
.
y ^ .
:. . . .
.
'
l , 3
. '
'
,
([% e R*
^ '
, . '
.
,
..
N ()h
,
0 ' '
' - . *
d~i *%w%g;WGwatuaEMB%nd wan 4-ak s,,v %f gk* uo.n- no .,a-eam, A b p*aw n&-
.
*
qY y-) 1FGQE-gEN -" #v$19?'*'PdyN5$#N9E v:n S<20 w%$ * 19 #M.1-: 1 C:q% yiW / Q n,,
.
>
- c%m.rai..ymw >
.- MQ pn %W:@pq+ m g
,
y s =r a n& yw).
- w,) e o gsw m.apy
-
l *.
* *
,) Q y,,,f ,w 4 'Ylf
, /p en # u. +1, a 4.. $w[[A h+q,pu e[h&,hh?h 5, &r, /
n.2 7_s 7 0?h., f 7 - s g,g ,,, h h[yhfS AhigI hh4 su A,' M %gse; s i k
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v, g e y%
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.
44,
"
4 . 1 9 s
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-
70 i
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p : b l' E
- , . - . - . . - - - - - - . . - , - - , . - . ~ , . - . - ..,,-,......... -
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- - - . - _ . - _ . _ - . _ .
._
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.
;
-
.
t
. ,
m Question Number: 44
.
X.) 3
'
#5092
'
QUESTION: POINT VALUE: 1.00
.
.
.
The control room operators -are responding to a . reactor tri * Without SI. They have verified automatic actuations and have . ensured that the primary system will stabilize at no-load conditions. All AC buses are energized by offsite powe ~
' 'Cohsideringthe'conditionsfjustfdhscrikd,whichofthe-following . *
explains why the.fpredhutA mo'd e Ts)pi'irfsrfec1' over the T., mode for '
..
.condensersteam,dumpi$obtr61." "' b/ f ,
- -
..
- -
-
tsv . t s . a.. AS.Jeam pressure mode does not requir gseparat ,, \ . arming signal to operate the steam' dump '
.
,
.
, .
eq ,
. . The pressure control mode gives moreIp,rgelse control of S/G pressure and '
g therefore dg W
-
.
*
,.
A
'
e m'KE E R M - Thkiteam pressure +modh@p@rovidesjextra pr,q[ec
'
f pd , adagnsjQxE6ssivecoolpf,n%
'
b Theh p'1km 'ew$iihhbiuallybe'disMiled Y
% gbe bs160 552* %f w m. w.:
h, whenMWt'emperat(Eb / g e +F~i[n:, e pu MEhinJWds%mp.dhli 875 . m c...
' ' 'e. ( :
s id}y&Mhr qm,w g,yyy m.% W D(y M % vg d.h W G
-
'
#5D 2 S Ni
,f ANSWERh%$3da 2g .(hiNgF(Y iil@4G ? .-(77
'
.
' -
#5 1 h c .
_
"
Modified by yesequenca.n W stractors and replaced
. .
k distractor d9 '-@j)tM 7' (Q .
,. ye
' No advantage seen her ~/N
'
d,"//f br#
* Correct - Under the range of normal,ySfG pressure,
.
.aa large pressure change effects'a relatively jothaller temperature change (Taig7.- T SAT for S/G)
therefpre finer control pf TaVgfis available by pressurM controR and also7 control rods are not in controf%fTavg.[ W Provides no more protection than Tavg mod + Steam dumps will be temporarily closed as temperature drops below 552*F, but they will reopen as soon as BYP INTLK is selecte . J'
. .
4 * .. *
--_
. , , ~ . , , .-
..y -*
.
.
. .
.
.
4 Requires comprehension of the basis for selection'of
,
s%;U steam pressure mode and the characteristics and uses of
' .
that mod '
'
-
. . .
8 , a
,
. .
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.
,
f 4
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0 . . ,
,
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e g * * s '
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Tfh>.k<v l h"'"'t
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n , h O ' igx h-4/ w am'gssssag84;
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w' f'e@hf,5I 9,
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hm$g;ue[> kh
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4yy s9% rum a s 7t~>, -
:;,e., u wn l' b hq.jhk $!h yfkk hh3 rh I
%
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.% $y . . .
v- g j-
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~;allj.t4l14 vbAr
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+ *
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)'$ . . % ,
y>1 . T% '~4 h n r~Q ~ e'yi (
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'
. Question Number: 45
'
!
#5356 QUESTION: POINT VALUE: 1.00 l
~
.
.
.
'
.
The. plant was initially at 100% power when a SB LOCA occurred causing an Si and
, ,
implementation of EOP i 0. The CRS is directing actions per EOP 2.1, " Post LOCA '
'
Cooldown and Depressurization," with the following plant conditions: -
;
,
- ,
'
'
.
* *
*
* To is 430'Fq RdS su6cooligls 508} "' h /
py f: * % .
.
!'
'
'
* '
.
. -
*
S6 acto [cotilant pump A is friserdieg/fl ,
'. ,
y
*
* PZR 16 vel is below the indicating range:. 4, *
(Tfie PZR heater control switches are in ths*,DFPpol!
.
*
* *
*- ' Charging pumps A and B are running in the Inje,c', Ion mod !
'
.
,
p y .
.
'
*
eIts th perator to.r'efill the pressurizer byJf epressurizing)h@pCS
'
The using CRppl(l gorrna spra'y..Li ~ ance<w pressilrizer being refi %ghiEgfg Qwill thisiction $![fy reqditJn e the ;
)- ,, i .
N I N .
.M f (
The water; RD.S)will
% expand [$t @wer pressure
~ hE
~
77" intolh'e \ .
% M tgPENE y "/ .ru lowereRCS pressure:n&g:?.p.X{nw
,
.
, f i_ e S efill,n)g
,
;: will i i "
PZRf'fdiHISijydEDK{ h.'d; incre
.
'"""
(})
'
, 1 hyg g y:gyf gr j {j . cou lator etiortADd ow will force" 7ater into theTZR 0 h%_
Yh M howet ML ? dsf' RCS pressur .wilCi'% gHR/SI flow, refilling the ni i
%
, , i
'
PZR fro . i H SJ ,
"
*
.
'
, #5356 \ ANSWER: %
'
\
f} (1.00) - ,
/ #5356 COMMENTS: ,, n\v .
r ,
*
kE' Significantly modifipd from (093 & 439s, Change'd stem and original' di
... distractor b. Also exchanged' choices b & . .m - _ Negligible magnitude. RCS fluid is subcooled and is relatively j .
Incompressibl ! . Incorrect - RCS pressure drop will reduce break flow as well as
,
increase injection flow to create conditions for refill; however l
* ,
.
. .
-
)
_
, .a ,, ;-- . ~ , . ,- . - . ,-.u,.- . - ~ , - - - . . , . - . , , - . . - . - , . . . -
. . - - - - _ . . . . - .- - _ - . . _ . _ - _ - _ _ - _ - - - . .
.
.
.
t 4Q) accumulators will begin to inject under the postulated conditions:
. .
c, . Requires' analysis of responses to be able to discard them and
-
application of basis for step 12, EOP 2,1. Expected for given
'
-
.
. conditions, requires calculation of PRCS at PSAT (430' + SO' =
480'F) ~ 566 psla[581 psig]). Minimum accumulator pressure is
'
t 600 psig ma .'
- ,
e Is t.-d mp, Pr>
- '
.i gs Wit T'
' no enough.to inject '
"t. b
*
. Q **.,$s 430*E,
(//pressu e.can/>
'
'
RAB -
:* . %
*
.
4 9
,, .
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w. ~ s ~n ,yN w ,4
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,4 i ,,%
% m\p:,13,gg:;% gu :[ fMWy:'n f %, c,s- n 3 tn. W n: p&'L' Oo 4 9 c-rc ~
;x -
7%.
>- " A , ,,pd fgMUrf)** N W r;'r'W'i:r ype A& cY . ,a(e Ql%* [9 7) u<';*a %jiyl ,
g%
. fl _ pu, h {=, ,te j&'$g/bydT@fpgjid[;)/
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~~~'"Q.)jE #
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- Question Number: 46
. -
.
#5097 QUESTION: POINT VALUE:100
*
}
The following conditions existed:: ,
; . .. .
.
-
*
+ ' The plant was in MODE '
'
'
,.
.
' VCT level was stable p1.30%. -
"
-
P >*- .
.
,
, ,. ,
-+ level gasIt'Able Leto$e.flpas1 10s gp at $5'9."'hs[.
, ,
.
.,
*
'.
*
'
f % a v
'
"
.
-
;5 An ernergency bo oration:
as begurilAW AOP-106.1, 7 Emerg'innpy$jN "
,
' * '
. h. Fl;110, EMERG BORATE,' reads 75'gpm - .
.
* *
A Assume PZR level remains constant.-
*
.
'
'
Predi ehavior Jevel, 16jii(Tu ct s$ ke I Increa f valve -d? t% gg g <\ m.,$? '
.
*
( Increi$rs . 11.TCVf WullTdhe yu libI
~. c. e I
'
el&twe -20 and 40 co wdnLe
-
ncreases, t on: . c .wm e ola,s atesorpe'sYel be
, and 80
'
#509 ,,,,
,,
.
,
-
7* -
.-
.
(1.00)
#5097 COMMENTS: s Modifiddty resequencing distractor g,
.
'
%f~ c.f.y .x '
Requires apply,T6d:CVCS system know} edge to unusual situation
.
y . t,..~ VCT level will not increase high enough to lift the relief due to
-. :LCV-115A modulation and check valve keeping emergency . *
boration out of VC * -
. TCV-143 will NOT divert under'these condition .@. ,
.
-
. .y .
_ esos *
.
7 h g
' ~ ' , _ ..
.- .
-
,
,
.- .
{
, , ,
-
.,
,
- !
. M"- % is normal makeup _ band; additional flow from letdown will cause level to continue increasing.
,. ; With'105'gpm letdown flow and a constant PZR level, charging
- '
, flow will be about 90 ppm. This assumes that seal injection flow .!
+
. is a total of 24 gpm, with'15 gpm going into RCS past the RCP *
- '
!
' thejmal barriers and 9 gpm returning to the VCT via seal leakof '
.
.
, ,
,. ', 90 + 24 = total, charging, pump flow of 114 gpm, which balances , !
-
'i
.
" '
- with,tio,n bo{a of{7 l gpts Is es ablishVCT leidog3+ sea !
.
'
I' .' ,
.
skgprqylli tome from the VCT #,ed;on thh.144oing into the VCT and'- 9'gpm coming out of VCT, VCT level { vill.jncJesse until 70% at
-
:
!. Q which time LCV 115A will begin to direct, it wi ,
l l*
* ' -
h% until flow into VCT = 30 gpm. There, it will turn,ljanod seal returh + 30 gpm into VCT = 39 coming fromNGT s~ its i ..i
.i
'.
'
": CT level -
- . .'g@iribution at olgt whTrIsto tottheleJsla
$chqgigg)gtCV tiilihd5 bet115
4eenwijlpodulate letdoW nio VCT
. .
/ !
/
(+Is$$p]5PM[6sv) and the fIo%gbliigiihtyhe ch
-
' 1 etiirn
-
(' suc't16h'
-& f. -c~,} 4 .YND- '
t
I l%%UlW ;
.
$ --- k.}g Ql /, ? * b $ $
--
~ %g . >
ns '
'
@ .hh< ykpiz;. ! . 9%
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.
ca Vgr [SpN W"45*hvuA < s 3(;;
'
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.
Question Number: 47
'
j
,
#5354 GUESTION: POINT VALUE: 1 OQ
'
Given the following: '
.
.
-
.
The crew has completed actions in EOP-4.0 for a SGTR on "A" '
', S mn
.
.
. .
' ThN'C[S tfahsbons to ColdtShutdown!afdp/ h0PMh
.
as the ARO establish an' . '
' *
RCS c'ooldown %c * -
"
- v"
'
, .
:Qg -
.
,
,
.
.Q to'74% note in EOP-4.1A states that a ruptured S/G,skould be refilled apd allowed to decrease to v0% before r n ,
.
,
.
p ribe ases Which 09E (1) of. thetfollowing desgh@s ddh* thged@N;for<allow betweerithese valueY$ MS ti CAS%4 Qp% fi Af%274?
#[
-
#C* Allo subs %g%e11evel to_ drop to 3088belore'rsfilling e W setp61ntQ(MdO MQ@ filf%ill'n'dt'ptessu[W:lis"de'6d Q)K
%
Ch
-
-
.o llow$ h? Y B fi$ N 74%N,hk? N E(b
-
"
J b., ing tiefo[e draining assdres
*
h- id$dwate;thei rydh,e toycrgs,e n f6mrevent to)Y! a rapid' pressure decrease!8 oddensation$y(! ' I $ II[f!F p'Q[ (3 c, ei ktc 1 k$h ru'p'[d ed/G aids in co~o of tlEiystal 5'tM4~5r ~'l[75fS/GV
\ %(~ ! Qj (NO, - ' . Allowing i e leve ol(lc -
the ruptured S/G prevenStpe 0-
.
.
*
[/.fpl
'. ,,m
'
formation of a therina tiarrier between water and stelim. -
)
.
#5354 j/ ANSWER: w -
.e , N, . tj4 (1.00) v
. ~\f ,, .
4.( *
#5354 COMME'NTS:
.m .
x7pq 4 h.: n - Modified by resequencing choices, Incorrect because part of the basis for the hiah limit is to ensure that the fill is stopped prior to lifting the PWR RELIE ,
:, Incorrect because the purpose of stopping at 74% is to prevent .. 'f
,
9 4
w,, --+-.,,,r ~,v- -e -.,.-rw.r,m, ,m-,------.- -,r.-,.,.w,, ,-.,,,,w--,,..m.,---y---w,, . , , -
. . - _ - _ _ ~ . - . _ . - - . - - - - - . . -
-
L i
. .
I () - ' overflowing into steamlines. Step description for ES 3.1, S'tep 6 (page 30) describes reason for keeping tubes covered (> 30%) is to prevent depressurization due to condensatio .
.
. .
+ - - Correct. ERG background cortains actions to cycle level to cool '
.
. metalin upper'S .
;
, .
s a 4/ s y 1 >*{ jw / \ ' _ u i 4 _., g. . . f . .
- '
j~ C///
-
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.
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-
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-
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-
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$ I, 4 F g , e .h
[ ?."$NY
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,
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+ g 4 t ! 7. ,igy 4 / ./h $n! h- ;7eg
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' M.., Question N;mber: 48
#5137 QUESTION: POINT VALUE: 1.00 The,following plant conditions exist: * * A waste gas decay tank release was in progres * '
RM-A10 Waste Gas Rischarge Radiation Monitor, is in.,. service. Q b,,) -u g .
. - . - * *
s, IS\i t 1 3 % 1 % .i
", WASTE, GAS DISCHARGE 1[I'RADIA'rJON" annunciator ." . .
receive '"' ' # ,4,
%, . ,\ v; .m \ . *\ JHCV-014, Vent Stack Hand Control Va19'& h >
Q tripped close " /"\ as
{(,%*\;, .
bb .
) '
TheCountRoomhasperformedabackupsamp}le aniilysis opthirsEstbggssidecayetgnk. /
% y > %, 63 W"~~~WP f
f%, i[t 7
* A Me%3sljasy" permit has$,.. ~"U.een M 5ued, and approval hasi@een;grantedrto,res'ume2th':deleas i e
% m
/, ,.g ey; n
, j :f
.J,u. QW g -.t , , ,
V '; ',- ,. 4 - , . . . . _ - + %
; *
Whi"cli..e (1) to takeJ,ONE or HCV-014 of thif followingris4(arejf thelMINIMUM (VentiStackeHandsControl; Valve) in ordereto actiod'(s')k V
:Ql: contiinue %the 3:7wkste ,
t.q"'?;g' ; yX,Qi, asireie'a'sh'?D 9 O[R ~33 ]dVit Ii[ /M a..t TReset thsivalvepocallyaan' all.o Cit to % pnut.ioniatic'All[g y; , e. y re
.n y e.-hp[eh'e # Q t.3f-/ CC" p
,p .c..z .... ,.~ s , , e }t p u. ,
..
-
,,#yf,;,,.! y be LTalic;etheivblVe,? cont' e roll, r to;ZERO (0), ther'% i'e -
. NJ1P,8
'
/g\ f f,Q'jvalvc^.' y '\ (/y '
t .# cip,esth'# .fT ne with y'{l'iPurge nitrogen until'RM-A10 tfie reiea'ls}h;
. - \ ,/ returns 'to uh'ckg'ro'und, reset the valve'locilly, f'[ , :
then re-open the valve, p[ a
"./ .-
-3
. , xtI T
-
.
Place the RMA10-INTERLOCK Switch in ON,vand then
/ take the controller to ZERO (0) , . thendr> open the
\
svalv , , , ,
#, a ~
.P
#5137 ANSWER': y. /, ,
~.,
;)' -% (1.00) ,4 :
#5137 COMMENTS:
Modified from Question #181 Correc Per SOP-119, the controller must be adjusted to zero. The selector switch does not
.
. - _ . _ - - _ _ _ . _ _ . . . . _ _ . _ _ . _ . . _ .
,
'
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'
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have to be change ' f
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- . _ . - -
m
%) Question Number: 49
#5138
,
QUESTION: POINT VALUE: 1,00 The following plant conditions exist .
* * * Waste Monitor Tank (WMT) #1 is sampled and ready .
for discharge to Penstock *~
* RM-L5 'andis .Rpo'E. 9 I'c but of servic .g ei
~, p g s
. e Fa,irfdT*1 bhdro s'bi*ing Us (to increase level in*
,
' '.. .%$
~
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.s( "*""
g ;- *
,o'
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.
*
.
s*G .yTwo qualified st.af f members have rey 1'ewed the , Q release rate calculations and disch'argh)-line
.
A valvin (., ,
, '
theMA9WMTTif3y bedeleas d j Based'o1 thesNLeonditionsr prov{ Bed'T '@,?h,, Q7 M M S 2p2 d p(4, @J
,,Q *) .;;;m + . +: -
:- .e
"" ElihEd[m$5f.qt;RM-L9 iIi'ebY;oF[d to operability
,
#
pridrft'o'iYeleaseT ! fd Wf (^<;
/T" u. ;.. L'. - ,QGM. u , ' ' ' . . . * >/ 's
! y% Both!RMfL5i;andQUhL9, are rentored to operability
,
;,]N .
l'"' /,'priof.ibfiele'aseliC12,6_:^ ' f* b" (
'>v b 'd bk * .i e 'b ^%;hu[
c.% The ,Fadrfieid"IIfdroWg.\enerat ds Sj' 'ing,;]yith two C,,i,p
"'*
.s i il'ed 'a'nal f\a \l Mindb'p;ende'nt
'The:qFilrficid!Hy
.02 k dastld[ro?
; stays
& W . pied e, P(plog/ to re1 ope' rating i
modeiwith M 05 aJd J PM9;i}nl ids current
'
bw} k,\ M *
,,, prior yto relea'seTgW wv. l;iu $>g w "restoredtoop{e ,r i
.
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#5138 #.,.fyANSWER:
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u ,/ns
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#5138 COMMENTS:
;~ .
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\
g,. a
.
Significantly., modified from Questionft96 Changed stem, correctranswerJand choice ' Resequenced choices b & i
,0 ,:
# Incorrec Release discharge valve interlocked with Fairfield Hydro in " Generating" mode, Incorrec Don't need both RML 5 & Correc Fairfield Rydro " Generating" mode and
9
.
- -
-.,
_ . . . _ . . ______.__.__.___.__________________ .
., .
- ,
,
*
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,
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per ODCM*1.1.1.1 requiren.ents and IAW sop-108, ATT l
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VA, page 2 of Incorrec Don't need both RML 5 & .
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Question Number: 50
'
#5104 QUESTION: . POINT VALUE: 1QQ
.
.
{
,
The. unit is initially operating at full-powar, steady state conditions with the rod . ,
; ! .
control system in manual. A malfunction of the reactor makeup system causes a '
.
dilution which increases Tavg by 5'F. What effect does this have on DNBR '
:
,
(D eparture From Nucleate Bolling Ratio)? Choose the conservative assumptio ,
'
,
'
.
a, DNbR c~oulhgo low e ign imit during $ subsequent *
- > >- - e achde[Et.be*cause Tavg is oUtside):thpjecid! ' ' ,-
b e D BR has decreased, but is still a
,
v'E epesign nitial , l
_, value for 3,H accidents, '
.
; , .
'
*
'c'. ' There 'Is no effect on DNBR, because Critical Heat ikhas '
i
/
,
/ /- Op %nd.g h tdTNiTal'Hiiitt]eW~
due%y dma9f6deEreage . ' ' irGTsased mW :s
'
,,,,
I ,
.
The'DNBRehas increased, becabse Cr ical Heat Flux has r ' N * increissd%%to' aitiTal . Teat fl0Elli$5ai '
.
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y W Pfi! b?~-
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#5104g .
V COMMENTS: '$r, 9t hg l 4i-g,' t~ h' . 4..* ,
.
/ $ Modified by resec[uencin . h ce j d
&
.
i .
'
\
/) Correct - Requires trainee to recall Tm Lirnitf hs at then calculate actual T,vo based on programme 'd 100% power,(onhTech Spe c
'
#~y" ' 4i b.- Non-conse,rvative assumption v(hen violati,ng T/S Aj~ .pp a
%*
. c, Temp t decreases m. Margin to DNB (i.e., CHF 4)
.-
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. .'
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.
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.- __ _ - - - - ._ .- . - - -
.
-Q .
Question Number: 51
.
,
#5110 QUESTION: ,
POINT VALUE: 1AQ
'
Given the'following conditions: '
' +
The plant is at 50% power, MOL, holding at 50% due to chemistry
. concern A arg in AU f76.f," r g + -
Coptrol, Main rods'fbine'is dn thellrhiter. I
. ' +
Ttie '
' ' +
PTVjprT rbine impulse PressITIE,ffall cf'o : * i N . k /the time the instrument failure is lderitifie(a'n(rods MANUAL, the resultant Tave - Tref mismathhos.3' . The CRS directs the NROATC to match Tave witti' Tre V
,
A .
' : e effect on .
The Shutdown PT(f46
* Margin? failure,(Q)S%g ar d the FDM 'did @ M resultant,.gonttoj,,@r,od motion, / has. had L, ,,f ,ig:w!?
e y %n w. . t . aD pp e### J' &
- !; Sh tdow ,imar initially.increa,w sesythen'
u + decrease s i% 1 ,? +m w; _ s'a ? y v.~ w ';:i (*~ Shutdown:m:sd ~w%,.e.}argin has' decrease % :ad . a r N,h w,qq. y~ c5 %*
. .m "-
j~ , e,Shutdo(K b n n?Yy:grem-:. q # w 3
$ wn margin h"as re .
t y3 .n p d thrysam,e, .-7
: y 3,.gm j.,t> (d ,
M..?-W /? k *% A MJShutdown argin has creasedP' m.Nh.37,qm@.m.aine
,yyd' .
s'IW~7
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#511 ANSWER:
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em
#5110 ,AfdMMENTS: ' / q~hs ~e Significantly modified Changed stem and distractor d'.' Also changed ., order of.bhoices., . ,
y T.% . . . s.. .. R
'
'
Answers a,b, a,nd d can be shown to be' incorrect as the reactivity from rod withdrawalis balanced by change in Tav .
.
I B4
..
e
_.-.-,i,---
- - - --. - - - - - - _ - - . - .-
.
.m NJ) Question Number: 52
#5111 QUESTIONI POINT VALUE: ,100
.
Given the following:
- . The reactor trips from 100% power without Si at 131 . '. The control room operators take actions IAW the appropriate '
p . pedures
- a,n(6_btalElfieI,6
..
quired ., plant / system / component
'
resportses. Ot .., yj . , ,
. ' At'1,350ra control room operat f bheck's'the -
NIS instrumentatio . ) ,-
.
.
s e.&.
R power is 104% on both channel * ,p\ M> The SR high flux trips are (['g
* still blocke .
,
.
wg Which 08Eg(1) of the following describes the status,of. nuclear flux for th'eso
* "
* @h
!(* IR heutron flutis as expected /but Oie:SR trip should huve KWL A yY reinstat6d EoW(1350);.5
:.:ui*~ v* ('# i on-'3;vd ,s #
h flux decreasejis a\*M, L ~ g .
~,- p. ,
f~ ,W ,1 Neutr,% . s expecte'd for SR trip reinstatement at
' %'#
O.) Tapprokfrh6tel .33'555dM ~ :v v
.
"
(. c. Nlh p*B eutron
'Q::M ::~
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.
a WA % " 1 h,.'tc~}i
Y e Dpfeseni.startup16td, R ip'sM,for vill plallthispgint j% In' time. At tl h*,)
'h1405%u7g?g, 9A N ym% GW probabl/$t reinitia :
% z.q; , . ,,f .
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b Neutron flux is'abn,or,r.c.ariall shigh.forithis point in time. sR trips
"
.
,
-
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,
.should ha'v'o re' ins' tite'di.t:al5proilrhately
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#5111 ANSWE,RS z ..
~
-
' (1.00)
'#5111 COMMENTS:
Significantly modified. Reworded and reformatted stem. Changed all 4 times in distractors. Original time of 1405 is NOW a distracto . .
.
e:
-
g ._ , . - . . - . . _ , , -
._ _ _
. .
,
.
.
'
.
x..j*). Changed answer. Removed YES/NO from choices. Changed order of r.hoice l
'
.
. a. & b. Not nor' ma .
. . .
.
.
. .
Ind,icated flux is biqh, not' lo ,
,. ' Correct - 10' to - 104
*)B.to g'et t , ~Kl7.5IS,J-5 ,j0 of) {. decades x 3 min /deeade -
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r m ' Mj) Question Number: 5 . t
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'
#5113 QUESTION: , POINT VALUE: L ,
. t The following have occurred or currently exist: '
.
. l
' '
- '
Thd plant has experienced a LOCA from 100% powe ,
' The ECCS is now opgating in the cold leg recirculation mod !
'
RCy p 1 atel , Core e,ressuxit Tp . ,QtableIst afproxirp/ y 35. psig., taret260'Fl Q(./%d
+ ;
'
' '
.
;
+
' Sd:.gre'ssure is 200 psi .
- .
.
\j'
' ,
'
,
Given those c6n.ditions, what is the core heat removal mechan'sm?)* .
*
W
% Injection water being bolled off in the core
.
- '
ain ,and ndensing sfe%
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.
i
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*
,
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- *k*/ . b. (spia"!S,h'dM.s, H ransfer-C'
een the RdS'and'$e;REfcooling sys eihs A M U52T8 t
% ca . r- . . w,en hp ,
I
&
,
W. $$lQ m.,m \ kwt The liijectl6n& oi water fr6ip,~the'.r$I0$[bh ec rculation sump and th'eh,
:u ., I k removalMfisiearp/watercout.6,f[tiVe;bie's v mm - ww
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.
i,~ m q. , yJ w gy
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t trarisfehb eett SCS IbbfationtoM ' i ! ; -lI F;an the$/Gs due to naturs1 " ,
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#5113 / . NSWER: -
t
:
A) %,,.
(1.00)
%
"
. #5113 - COMME @TS:
.
%
.
' mf' %. Significantly modiIied - Changed wordiIig#and viives in stem and original distractois b. & c. jAlso changed order of distractor '
,
,
. Sufficient subcooling exists to prevent core boilin b. - RBCUs and spray cool RB but have little direct impact on core decay heat remova ,
87
'
i
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. .
!
'
- . .
- - - - -
agp-- gyw,gy w.-- -<y.--p -,,e-ygo.-%,gv pe e- t ve vi- + :mwy u -- e t a N#* g T g= g v g * me r v ww-g er y w+- *-w eyJ"p gy Tw ytir-s+g g -=='q+er' +- +=17au's%ye4 --g ywe'*;le-p.1- cyup- gy--r--
..___. .-_-- _ _ _ . _ . . _ _ . . . . - - _ - . _ _ . _ _ . . . _ , _ _ , _ . _ _ . . .-
-
. .
-
. .
-
!
'
i
* ,,
sg') ' Per ERG Background - Requires trainee to evaluate core ' conditions to determine correct answe S/G heat' removal not' indicated because TSAT RCS < TSAT S/G
. . .
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,a A Question Number: 54 :
w .
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#5114 QUESTION: ,
POINT VALUE: jaQ
. . .
,
*
j Given the following: ,
.,
,
'
-
.
The plant is operating at 100% steady state power during B1 * I
-
'
, .
'
Maintenance Wee ~ ' The(Plap of-thei@ay L INIgdis.'a maintenance activity o
. '
Qi/ f
~ . '
Charger,XE:C4 B. L 1 . . !
' ' '
.
' t
!
,
:' -
(/Thh eslimbled
\J@remov,ed from servic ' time to /
complete thi % . l i
.
,
' ' L ions to be taRen for tagging out XBC 1B are: The reavire
. dsIy3REN e4STFt$ hen r 4 XBC 1B k/ dolm lg:p $hgQuart @3i
'
4W<{;f3E?S-) ^
'
g&+ froyk@c%wJn AQ y f . '
- NT, Remove XBC?jBifrom 5 hen s,epice;,Vdb:p;yM~ s t
'
.;
%s Surviiliaide(%Ay2yQu{P/@55$@ STP. M % % % 'm pe
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1 Repove;XBC?1 B'froiii servW d. M};@ElecerXBC-1A yu B hn se' AM $ M M ] {ithe$ %i.,
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, . #5114[. - /j d.ANSWER: (1.00)
ft . Q y-
'
'
-
#5114 MMENTS:
./ -"
-
.
order 6ff(hoices.Significar,ly modified - Revised stem and distract R. . ..s J*
.
'%i
.. ~. Incorrect.. .'Not per SOP 31 P ,
* Battery becomes inoperable without a full capacity charger in service per T.S. 3.8. Incorrect. Swing charger must be placed in service firs f
'.
4.-a
.
-
'
89- _ . , 1 _ -
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- -
, - - ,
. . . _ . _ . _ - - _ - - . _ -
r
,
.
$.) - Correct - Need to maintain battery charger on Bus 1HB & Battery 18. . ,
.
t
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Questlon Number: 55
'
#5220 QUESTION:
'
-
The follohng have occurred or currently exist: *
- -
,
- + '
' A steam line break outside containment has occurre '+
,
-
'
Several equipment failures and misoperations have led to all 3 V4d Allh,e Rang /TpveQt qqant pumps'RQ%,with
.bpve b'een tripped.no EFW purnps available , * ,
enctor
'
' ' '
.
,
f
+
jSa#fgt . QpS'glnje' tion has been activ$tb^d a,n(SI flow ver
.
'
.
:' + '
-
lemperature and pressure are incr^eayjq(!
'
l
-
With a continuou2PCS these.coIo tions
" bleed" path for heat present, removal when: all available PZR PORVs sh
.
,
-
,
" --
~ S/G Wide /
'ggbig ?Ran%LS~ 'adEr$Ns todd$.
.
'
- *k'f jharroN jnge Level decrease;} s
.%
};ijpgg;is40%.
N RVL(S;pfM
%jd P ggym@ip s
,v PZRfressu% re
%
ged? 'lcre,asesito?2335lpsi a
^) -
A 90 Coje$$dk; it .f$$MDDM9[p hw
*
& , lh Eg'%qCc;inctesselto-1200Tp D 1 f A
#5226 %: IsWER:%Yhit GWA?QWdf@NNlk'NA }h#
"d /
II[7 h&
- "
.,
(d
'
#522B COMMENTS: ' d- (M
-
y-
, , -
y . c,,,, NEW Q' UESTION 4 Q\ V'# _ pM
.
N
. * /
MiEk-!mportant Operator Action #6 (RE: TWR TG10894huf
/ -
y..L in(orrect - WR level < 15% in any two SGs.ls an initiating criteria
., "for feed-and bleed in EOP-1 yh j'f
'
41'
*
b., d. Incorrect %These ' ate (:both inadeq0 ate Core C Establishing feed-arid bleed is designed to prevent inadequate Core Coolin :
.
.
, Correct - PZR pressure >2335 psig due to loss of secondary heat sink is an initiating criteria for feed and-bleed in EOP-15.0. RCS
.. temperature _and pressure increase signify that the increase in
: .
.
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. _ _ _ . _ _ _ _ . . _ _ . - . . -
. - _ _- _ ._ . _ _ _ . . _ _ _ _ _ .
. .
.
.
.
. .
,
,
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'
9)** pressure is due to loss of heat sink, and not just from Sl flo .
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Question Number: 56
'
#5117 QUESTION: POINT VALUE: .LQQ
. .
The following plant conditions exist: '
. - . ' ' -
Refueling operations are in progres . .
, . The "FU.EL XFER -- CANA.L ~ L,V,,L Hl/LO" annunciator is actucte . -
Thg, level is 460 f@Let and'decreating. ,
-
* G ft.f ^ 1 iC ( r.'4 f
.
,
.
.
: * because The Fpel HandlingpRO,fs no longer sufficient the wate(lejbl i
% Af gto:sdspends refueling .
g s ,
- .
k. Limit the maximum velocity of.the spent fuel sh*,1ppliig_ cask to an
' ' \ impact velocity of 22 ft/se %# . -
f Q % -.- demdveJ9% 7the@m n.,.n.mWactivityeth5t<iAlgrates4 obgh the
*
M.,/ m W8 w W enortgag'#m,m "" f fuefE6d.sEf3.A9 w .y .- 1 r%
, C CdRh LOT, Limit;thl& maximum Ve scity of al dropped. fuelsu l DW assembly to an [,J,, impa$j$lkcif/of 443 'ac.y[f w d. ys II_ in it thpquCAtspng'e.fy( % 75 % 4 . d .;y 't # ",~ 9 '. hO/ s mr/hr wdun...akimuni'ddiciist ng;transfeJoperationsa nat'the'
m - v~n.~. .. .&spen,t fue,l pool surfacdTo
.- .
- U;;jr3 n l E y; p+ n itij;"7 &<
QW%*7 ,.$l.2 ',i/ 29.ry, , r g
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f ,.,t,;.,, pa
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p\ p;,,$$v..~
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w" 'c ~h0h .
+
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#511 ANSWEN.Mi } ,
.
'
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(1.00) %,jg, ;)J T' ' (
% g-
#5117
/*qj COMMENTS: /Y s *
RW+' Modified ,by resequencing c,hoices and replacing S/ShittbFuel Handling SRO. 'Also replaced "SFP LVL Hl/LO" with " FUEL-XFER CANAL LVL Hl/LOj'T .s 4. s.-. *
~.- . 6 f, ., , +- _
, = ? Incorrect since the Cask Loading ~ Area minimum level is based on limiting the speed of a dropped cask to 44 ft/se . Xenon doeg migrate through the fuel clad, but typically is only a concern after plant transients, greater than 15%. The xenon would be mostly cleaned up by time refueling operations starte .
.
.
_ _- .. . ~ ~ .
. _
. _ _ - . .
.
-
.
,
s ,
.
,
'
-
.;
.
N.7"') . Incorrect because bases of 44 feet is for a dropped c' >K, riot a * _ dropped fuel, assembl , ,
*
. .This will require. exarninee to apply knowledge that_ for refueling
'
*
'
-
: . operations, the gate between the'SFP and'the Fuel Transfer
, ,
*
, r .
. : Canal will be open and a' decreasing level in the canal will be - ; ' - '
seein in the SFP. The SFC DBD, page 2-3-1 (Function 1.). states -
,
*
, . . . .
.~ !.' that the SFCS Maintain' s a water shield above the spent fuel
'
,' as.Spmbjiesjto @t radiatjofSpls in,the c area of the pool to less '
,
5thrhpft55(-3. ,thanM2i5 %,.- m /tirn Thisis amplified ;
. .
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- -
>
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Question Number: 57 ]
. y #5118- QUESTION:- ,
POINT VALUE 1.00
. .Given the fo'llowing: -
.
.
-
. .
, ...
4 - - 'Ths plant is operating at 100% power with all r.ontrol systems in *
*
' .-
+
aut'omati '
-
E
..t leliilQdev Mth leg. D f * % ( , controlling SG L'!-4g3 reference' '
JTh'e co'ndsnsing pot islea unable 15'1/
-
.
.
.
. .
' * '
-
-
keep;up with the -
: ' '
q)Y %Q
* .
.
Which ONE,(1)J ihe following describes the response of the plant assuming no , operator actio,g $N
.g
.
..,
, .
s
,
. .
.
- . The 'C' S/G level wil! increase,but MFP speed will decrease to
~
'
-G pident,sexce [/
.
g rig,dhg(f~R$~ llfifseigdiN y The(distlE6endi$g'thTS/G Ld-lENi;Edipoint.Ci>S/Gjle
'
Q prev Gbgg# eWkd pr5R,x*v r&7&yr ("3 w p % zww gThe reactor!will ./i -og.S/G,Lo-Lo levelt F #w %
(d't
.
.&d L
% wm% 9 Ml%
'MMCMgd m 2v
'
h* d. 'y w i eM
;The turb@in&=i
*
'on:S/G
, -H y g y[leve't. ,?7
,
=~ ~ -
(
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#511 ANS Jj
^
h ,
-
,
.- :- .
,
. (1;00)-lf i P m {/.3
..
, ~A31id < COMMENTS: ("D OModified by resequencing choice g%
'Wf
"ge- .
sy s~ + . u
' '# Requires the examinee to determine.that aveference leg leak will cause iridi$ated levelito go high.Examin'ee must then apply knowledge'of SGWLC'a, nd determine that high level will cause FRV to shut until lo'lo' level is reache . , . .
Pt t 95' 4 _
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, ..
a -- - - _ua - , ,, ,, .<r -
, e
. . .- .
w: 4 Question Number: 58 p
.
#5131 QUESTION: POINT VALUE: 1.00
.
%
The following plant conditions exist: .
! * I A reactor startup is in progress per GOP-3, .
~
*
, _ Desired Estimated m Critical Position (ECP' b Bank 'D' at 145 step g bz Qn~g py .
* A' max,itpum> rod withdrawalJiplit of 190 steps has been '
establijhecf: ~
.
* (,,,//
"
.
,- .Cdntrol rods are being withdrawn with Ban.k./D,' . resentIy at 180
-
.
% .sfep l; _
'
,
,
The NROATC pulls rods 10 more steps, and the Up decays to
- ( zer #' % -- -e Which l W(1)
E' of the(following paw % % - actl~o'n's+sWQdTe$n-C ksiFbpderithese conditions?
* eWW A A .
/c We!Zbh V AW.JP
/ Boratelasmecessary,to-ach.ieve..requiredfshutdown margi.n shut
*D dowri'thSIN5istoh;ieF50P-5'5iid:ibchb0 late EC ~
'h Y
[,2
*$$h3 [EhMMSMIE5 , ~ m. a h
L fpontingliwithfstartuplopef:atio@andlrehalculate
%(Qn,Q L Qvi % w.M ~ n nyw*h:g ECP.(w)
m wn (*%
(+.J 5 c. hShutdo'w,.&C'j'%hQ:UO;Q??"dW---u.tn.thfreactorspef.; c GOR;5fan N$j8p3 ON $ [jhNd3 F c' -$7 lculate ECP. N kll Continue witlysiartup[ j operation until c (%+A o Qe -
g m ifQG{;@f ;C%l%x;w;.5%Q%g %w 5k? " % -
#5131
%s ANSWER: 'ijik
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'
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-
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(1.00) '# 's "
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#5131 #60MMENTS: i
/ ) x%lT NbW QUESTION n~ 5
. Y c, dorrect. Conditions must be evaluated'fb'deterrnine Rx is not critical with%tartup raie decaying 3o zero. With Bank 'D' at the withdrawal' limit, the'distractors must be evaluated to determine that choice 'C' meets the requirements of GOP Appendix 'A'. Incorrect. The Rx is critical before reaching 10 power and is stabilized at 102power to take critical dat .
.
-
. . _ ..~ .
.,_ _ __ . . . __-
,
. .-
.
.
'
}. Question Number: 59
'
#5323 QUESTION: POINT VALUE: 1.00
'
, Which ONE (1).of the following correctly compares the severity of th'e plant pressure
*
transient produced by a pegged HIGH failure ~of pressurizer pressure detector PT-444
'
versus the severity of the plant pressure transient produced by the same failure in .
. PT-445? '. -
.
- .
.,m n .
'{h h hL *
' '
Assume that the plant is sIblefatJull hower th,all cor3tiols in AOTo prior to.each . ' '
'
" ' failur'e, and that the fallu#res>oticur separately. NO Epiratoffsponse' action is taken-
,
' in eith'er case. +Q .
*
4,4(/s g, }
,
'
.
(. -
.
'
A The pressure drop rate will be larger for the PTj4~4jailure, and .
. '% the final pressure will be lower for the PT-444 failuI . ..
f T pressure 6roptra]bjili~t5id$'m ,foritfie PT-444 (aifure A/
;- % / the%j;d4%failu7siill 1P res'uTIFF5 lowegli$fpressure.#
qygn. v" a The Nii rp will bd5I gwyg!the fy: PT-445'failtTIe7and
'
I the fii@l)[dresstEe5 ITelower:forgIhe PT-445 failure,[
$F he pr fb$ s f r' hpjPT-445 fall but-(.[) 'i PT'fiffsi0re;willidi61tiiriniM7e"r fi6 L ssur Kygg MT {"]~
"" "F
,
"
g(
#53f*3%*d VANSWEf: Mkik;hT .
'
-
,, g
%N
;
h* , 75 d, (1g% 0) r
w f(), f-7, - y)
-
, COMMENTS: ;- J %
.
~ .
.
.
#5323'\ / ..
-
,
.
<
'
- f[bj The PT-444 failure will cause only one PORV to ofen vice two for '
/ h a PT-445 failure so PT-444 rate will be smaller.shlLtfie PORVs
/ will be closed by P-11 when actual pressure rs~ aches .1985, but PT-444 failure will keep spray valves oper),jcausing actual
.
. * pressure tg drop to Rx trip and SI setpointsc so final pressure will
*
be loweO,f6rxPT-444 failur .f .;7 29 ;,_
'
i^L
'
,
: . -
. .
.
'
I
. . 1
..
3,
- -- . - - -.
. .
.
.
p Question Number: 60
'
'
#5352 QUESTION: '
POINT VALUE: .t0Q ,
'
. .Given the following: '
-
.
. -
.
-
y . . . '
' - - , . ~
_
'.- A reactor trip,n has'occurr.'2ed e- due to loss of offsite powe S1[hidWIOT a'qi L., ' .- - .- '
pr y _
,, ;
,
.
,
.
,
.
,! '
-
\pBpMDA'is energized by the "A" D/G. %,gf
., ,
.
. y .,
.
; ,
* k The "B" D/G fails to start and ,reenergize bus 1DBF
-
..,
-
.
N-
,
.
,
, ., t - .
. . The crew has just it;pped the MERs and has ensured ,,at au f hY *Wi-k
- * '
-
Pr lineu *l*![MN I Isrtt, pfMN$$ the;PZR PC$Is ] n $ormal
/ Yhi h . % -
The f31iowmghlg ' arame existPp ers% (n), m
*
kb A h
#
d Y&h PZRd 8Wanda&h ,y
[,
# 4 e "% t u hW ;g[;prysslowl ncreasin4 g7 -==
M
.
sig and%e
-
Y; ZR Gressute p !kbW 7 isE }980gp$f;.5$( greasin & gi .[ EEW Flo,w, htkh'm'Q m-M55 / h . ad 1 h6/ bb~.
- - b, 3 The crew' Ensure s; t! /L' f ~1 FREE Od -
Y.! 'the spray valves aIe cloTe (3) PZR PORVs ar$ . A closed and' A Which ON difof the following describes the MINIMUM actions that.MUST be R _ performed to re' store control of PZR pressure: . N M
'*@\ ., *Plshe both ESF LOADING SEQ A(B) RESETS to AUTO-START BLOCKS?ind allow the PZR PC'S:to autornatically stabilize conditioni'.f 'Ijd 'M , , Manually actuate Si and return to EOP-1.0, " Reactor Trip / Safety
_
'
Injection Actuatio . Increase PZR level, then place the PZR backup heaters control switch to CLOS .
,3 . ~
'
.
:- O .
- .
- - _,- .. - . - - ... . . .
.
.
.
. ,
a ? 4 Question Number: 60
'
'#5352 QUESTION: POINT VALUE: .10Q
'
Given the following:- -
.
.
,
-
. . .
.
' ~
- -
'A reactor trip has' occurred due to loss of offsite powe Q aO1 %[," $
-
- -
Slhid.N,OTlg
. .
,
-
a'ctuat :'
- -
'
-
.s y'
kBtisMDA is energized by the "A" D/G. y ,.
.(/)/ .
,
# ,
;
'
.
,
*/ s
.
The "B" D/G falls to start and ,reenergize bus 1DBIN Q-
. . .
g .
'
. .
Qd
,
. 0The crew has just tripp{ed the MEPs$nd hagen
-
a 0 ( 1 1 o 1 ods srfnilpldsIwTe~d3!EP$egd w m es [ N-'/ k., w~m
.
vs 'S -8s,WF3dk
- / -
Prios eieVent, the-PZR PCS(was:in'.a~ normal, at-power
-
*
.
*
{$ ,
.
' ,w
- 4
.
a. The f611owing
,$nt;pararpete s,egQp
_c ffp p~ ;a ~ h h PZR evhiki18S,I$$hiribg$g!n^ a
"(
g Mslowl ,
$TbM$9 $N$}hhN M h ** '" '
]k!khI
'
L ,
>
T(* , - ,The crew dnsur ti ,, REE'(3) PZR PORVs.ar]e J. closed and
, , .*' .
v- 2 -
, the spray valves are close '
R
'
-
Which ON}/ %)Ttore control'p* performed to re
,(1 of the following describes the MINIMUM actions that..MUST be of PZR pressu
.
.. *dPlsce both_,ESF LOADING SEQ A(B) RESETS to AUTO-START
.
t,.e
' BLOCKS!ahd allow the PZR PCS:to auto'matically stabilize conditiods'.E ' 'jd 'lA
'
,
- Manually actuate Si and return to EOP-1.0, " Reactor Trip / Safety '
Injection Actuatio e Increase PZR level, then place the PZR backup heaters contro!
.
.c switch to CLOS !. .
,
.
.- . . .- .-
.
.- ,
. .
. .
.
.. .
,
'
'
- i-Q.) _ Question Number: 60
..
'
#5352 QUESTION: POINT VALUE: 1.00 -
*
*
,
. .- ..
Given the following:
,
-
.
.
, .
.
,
,
. .
~ ' '
'
.
..
- -
'
A reactor trip has'occurr'ed due to loss of offsite powe l Pa .
- '
%.mL4 Sl[ddidIOTkaqtuate. '94 . ,.,
.
.
-
_, h^gI Qjj
,
- ,'
-
,
:
. .
." .
'
- (n\ -
y *BtisMDA.is energized by the "A" D/G. % ' '
.L .
-
.
%
/% -
. The "B" D/G falls to start and reenergize bus 1D
'
#"
' . The crew has just tripped the MEPs,and has,ensuredhat all-f C"5dliol ds sr67uilpTN'iEii621f5Mgy //
Q%j-
.
9m " # ,4 g '
& - f --
x GI eveqt, the;PZR PCS wmd wasan%vfp
.a:norrnal, at power Priort
* $ ?!?
' - . AThe fBNhiijj[ plant'
(A\
.
lS,.b P %u_$Rm$ff,; rarn'etE t%ub CeEU$(&h
"' p- gi gba$. PZRieveh_sii e -
aw s ,.i y
.
. :<increasin ~ slowl <
"$$%861 W WW <l
'
""
. Y ir { ZR .sgei .h g80 h p.sig agWd' ecreasin M*
.a.aus
~
i_ G&$bf[f% F:";i/ ht
>]h -4 IhW7ow:isiG4 ($lli p!Nhl iU
%
ODI '
- 'f$ ,The crew bnsures %t /, ...
closed and the spray valves a(r,e c o, sed,1,TRREE'(3) PZR PORV , , v* g
-
.-
#
s , Which ON (17of the following describes the MINIMUM actions that MUST be ps perforrned to re' store control of PZR pressure: d 5.e .
"p .
-
' PJ5ce both ESF LOADING SEO A(B) RESETS to AUTO-START BLOCKS!ahd allow the PZR DC'S:to auto'matically stabilize
~
conditioO '5[ Y
- Manually actuate Si and return to EOP-1.0, " Reactor Trip / Safety ' -
Injection Actuatio Increase PZR level, then place the PZR backup heaters control
>
switch to CLOSE.
- .p.... ,
7. .
~
.
g &
**',
, -
. .
,
e s
% ~ y".) Incorrect. Air entrainment (vortexing) will provide low pressure > '
and flow with fluctuating amp . Water hammer would produce erratic condition .
. . .
.
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Question Number: 98 -
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#5090: QUESTION:- *
POINTVALUE: 1.00 :
.
. .- .
*
Given the following:' . * .
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~
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,,
.
- The plant,is in MODE 5;
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* i' "Il"4SW is. u .fsg
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% -
p *#}, " .
, C ,SpP*is OOS and racked o ,
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% i8 y: _
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.- . ' A" SWP is not running, but is in standby, whilpmaintenance is ,
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, . Investigating an MWR, fg . ' ..
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' ~
Given t apove conjjt]hns, which 6 j f the,following describes thI uto start
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. LOGI 'A" SW pu , . MI [ h~ -
- I MVGOO3J43SW to EFW sup fy){openT5fncident with' DS- -
hEMF i[*p"kb$$$f
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SI/Blnfi50t@949MM i
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,7 s GE n y- ~
.. VG)103L S 8-Wfs m[lpersco incident with
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.n h - b.- rEEW,:supp# .
vy a i' 3D
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d-kb {)prels:( fe h
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--_4 ' i #5090 --[' ANSWER: -
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#5000, COMMENTS:
n v 441
*
T,% 3 .]'-: -
i -. Modified. ChaEghd order [of{Sistracto'rs:
,
c. & are wrong because the_ low pressure only opens the valves, :is wrong because the auto start on 1037A open is locked out by
,. sequence . " *
_J 148-
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" Question' Number: 60
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#5352- - QUESTION: . POINT VALUE: 1QQ ,
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.Givsn the following: ,
' -
. .
.
.
,
'
.
.. , . . .
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'
,
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'
-
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A reactor trip has' occurred due to loss of offsite powe ! g t at . n ee). w
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Sil id aquat ' f, x E .
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f .
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ef,5
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h DA is energized by the "A" D/G. % '
-
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.
-
h - The "B" D/G falls
.
-
.
. : to start and reenergize .
Q bus 1DBW) 7
, .
,
.
.. crew has7dijust ~'@"' tripp@,e,d O$M the T M"EPssnd has, ensure ~
N Pril - ods sii{k the;PZR PCs asiirr no
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.?T y - , he f6$owingjjant)aramete PWi pxytJD s,3##pw
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YA$ : M?hg 4 - PZB slowl increasin ve
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pZR-j hy ll$F s; 980psig and ecreasing, Q( er" hc N3*
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6 ^;,ey ' he q%Q
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%.r ..- - The crew $nsures;
' the spray valves aIe c oTed, s P PZR POR -
* *Qlof the following describes the MINIMUM actions thatsMUST be
.
R
' .
Which performedON to re (17' store ontrol of PZR pressure: "'% .
' ., 'PJ&ce both.ESF LOADING SEQ A(B) RESETS to AUTO-START BLOCKS?and allow the PZR PC'S:to autoinatically stabilize *
conditiorID - , 'W 'id' ,
,
i ; Manually actuate Sl and return to EOP-1.0, " Reactor Trip / Safety
- '
injection Actuation.-
~ Increase PZR level, then place the PZR backup heaters control ~ '
..
'-
-
: switch to CLOSE.-
.
4 g
..
- 98
'
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*
-
.:
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,
_ _ _ _ _
. .
!
.
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.*
'
%) Place "A" ESF LbADING SEQ A RESETS to NON-ESF ;
LCKOUTS, then manually energize PZR backup heaters as necessar . .
. .
' *
#5352 ANSWER: '
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-
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(1.00)
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#5352 CD M,ENT[t ~,, Qgf j',
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Sig ino ificaptly ichanges to modified.' distractor a.Changed and reformatfedyt.e,,m\and disirac
//
-
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*
'
isk-Important Operator Actions #2 (RE:
! (* .
TWR TG10894) h,
.
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^% SSMo W r--%.sr"'?Q g use #B/(heaters,
*
y19
- ' "% %nR!*I@R\r Inc ~
rre Q, Sjjen.f r.ia e ,t p a ug w g ,y , p %. s d$$$Eff %. bsw u:2 (, 54 IncorrectgPZR Hea,ters7wil,l[,riotitH E
. : C t
ALocko6tFiliti(6 t m ph = 1;24 max-e{to;befr'eself$u;p gh u(w) til 17% level
' , .D r rr %g.\ kW W h% A^ ~
V) d. %dp%. trec neup;mean.sithb GRP 1 B/U.,,.?
% %;hedtEe rs aret.th;Normil-$ft'
Agorga (at-powg e '(StNrt" and'GRP,,2 is in Nornta
/*'g $Mib6Phfter thdIB/6,[if68tj5 /Gs sta *~Eload, then PZQP ( *( ige 5Urd:drk%5dlbdE236?"Ygnarid e ESF UOs are [esst, dNPYhElefUltl'5i$y.'liff. itl fdr6ber 3 light) and GRPg2 Mill .
automatidsily reEp'dryhdl ;GRP 1 heaters do load sh@ and Y,, .
'
. .
.must be r'e' set b'efoi,ejhyy, fan,Wenergized. Trainehyst
+ - -
-
// analyze cause of heaters not being on and determine corrective actio d
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Question Number: 61
, #5333 QUESTION: POINT VALUE: 1.00 . .
Given the following: .
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'
The plant'is at 40% power and all control systems are in automatic.
'
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.
. . .
n w.. n
.
The PZR' tLEVJL C Bli Switch is..!p the359 + 460 positio T L f %
.
- s 4
% b, ce The NROATC4o6 serves that actual pressurize /rdevel is decreasin ' '
. -
*
-
v -
/ \
Which of thefo,llo\ ( r/4
. . . wing conditions could cause this to occur? . , .gv ses a.- R LCS LT-459 fails lo kM -
b.0} RCS Te?lz%*RTD
-
.. . . smwfailsk~igh4cW~MDs 2MQ % g d:cr
;1e % dw #s/, m
%f C%dm%
Temet N A(4:'p,aMedt
,i PZR PCS'PJ:444 wyn 9 4,9 ;
failsjo s
& 89 ,m ge w4 N f.'hhhkN NIS Power-Range't@!4 b h??
h'd failsV~ high,,,,,,.hhb[m (h, ,,1
.- U p %??;@iQh:289di Q %,) #$3"33s q$N,SWER;Q5$s@M"AD%@3 3$f!j ' ()) d.WW l$ d$G ' Nf,!
d<, N$$p 5-jg$if
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ye* cc.d.w.o &c7 Wuu g 9 $. tm[ o $ . _;,.f9+, f #
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#5333"I ICGM@MENTSMd6WW1,%c$u?N
\.
e Up p"%,.7.jysqMSr n y Q;/iM6 % ~ e("dx Significantly modified $"Re;mtae: vised % l
\.r#,- -
4< % '**mp wlistem:andidistractor g.<y,N ~]
+,qr v . 'Would cause PZR level to increp.c Q/%
v-N #
-
y 'fl + e %
/,se &s r\
-b. / No longer causes control affects due to RTD manifold removal
/ and median signal selection (MCN-21315).- M
*J s. .,
\-
) %u g ~n ; 'PZR heaters would energize and level viould t due to thermal
. ~ . . % ,
expansion.t... A q / e: t~ W: ' Requires examinee to predict inward rod motion from the power
,
mismatch circuit which will decrease Tavg causing PZR level setpoint to decrease. This will reduce charging flow and cause actuallevel to decrease. Decreasing Tavg will also cause PZR level to decreas .
.
. . _ _ _ . . . _ _ __ _ _ . . _ . . . _ _._ __
_7
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Quektion Number: 62 ' M.-
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i
#5202 QUESTION: * '
POINT VALUE: 1.00 i
.- .
l The following conditions exist:
'
.
,
EOP-6.0 !s being implemented after a loss of offsite and onsite
- - '
ESF AC, power has occurre ,
.e m~
.ci' s f M k,., !*\ ; '
- The'operat n\ fact S/hs thi240t psi g;cres> islin thct. " (process /ofdepressu'rizing the i
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-
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.
'
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- uring the depressurization, an SI signal is generate .
.\
.
W
/ -
Why is it necessary to. reset the Si at this point? [ . ,
^: % ..,-x~~- at . , . Bec<ausghe pItiseque;ntp recoveresence ^ ofit EFM/.hunng':st -facti 6nsp-f g@y , a w . s ,.~JiW '
G A
['( Resetting !Si
_./ Ni d[dh
$f%m%$@4 plit LE flow % %. &
f Because:thi@h,ll/estor wi E!SF eg;$gnt.to be ma i,
.
O d. 'Igges,eting$$$ SFwil,I;en,sgre
$ $
tpat}hlService j3 fump will beq - i
" iow #nsure EDG cool;tq h% 22FD}M [$W k I favalf5jfe,$ upon:resto[at,oniofg^oweg"h %
#520g) ANSWEF .
-
(1 00) gj MP Q
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% #5202 ,[QOMMENTS
/, %f%M %l NEW QUESTION R p
#
., lhcorrect since SI signalis overtidden whe;n the MD EFP RESET
'
Switch isTriiomentarily taken to. RESE q - y , o Requires examinee to apply knowledge that resetting SI will block subsequent Auto Si signals for activating the ESFLS and that after this point in the procedure, all ESF equipment needed to
'
support D/Gs (SW pumps) will need to be manually starte Losing pressurizer level is expected for this depressurizatio .z -
- .. '
101
- .[5
.
a 4 -
- . %. 3 -.. , , - . - . , - . - - -
. . _ . __
. .
.
. .
.
'
AQ' Resetting SI would allow starting a charging pump once p6wer is
'A restored but, procedurally, this is not done until after the transition out of EOP- .
.
' '
. . The Service Water pump is "made available" by D91 P l acing it in ,
. P T-L. Si reset has no impact on SW availabilit . .
.
, Risk lmportant Operator Actions #2 and #7 (RE: TWR TG10894)
n .my
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Question Number: 63 i
.S '
'
#5203 QUESTION: ,
POINT VALUE: 1.00 -
..-
,
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' '
The following conditior)s exist: *
.
'
:
, ,- Ths plant _is at poiver with a normal electric plant alignmen kf$,unc[ato 'B' (1D 31% C,KOUT" actuate .
-
,. L+ s
* Which ONE (1) of the fo,lloping statements describes thkdafus of eq~uiprhent
% bc .
..
-
.
"
.
power'ed by 1204%Cfanels APN 5903 and APN 5904 undetj,fconditions above?
.&h
'
( % ,
k ALL equipment remains energized through the inverte . i
.
' '
' '
'
.. b.' . pms'ntj,Lernigi(s drz f,[om;th backup wer
'
, su IDthe iriverter, IfurNON-VITALTloads willt e~she r pwngy'
b ALL fxiu pid$b;reri enerJe3Ehine inverter's alte3 ate
*
m y~ * h@ou AC psg;{,idiE%g&W+2%dmW$Oy e1 npyj % N -
^:2:S AL gqu the inverter's ajt..) te eJpa :"
h " O.sourc,eg,tpmentgemains?eriergizekfro hIoii h3h$IirNs/fEr'/ifutiNO
.)5$d?m ^&b&g h (5NV { ~
7AL loads will;bs' f
#52 ANSWE #k I @ - \\) '@
' V a f. COMMENTS: i (1.00) uj![.. a
/ /i (DD
,
gG
-
% #
%,, W 4 '. #5203 -
hQ gl/' , - NEW QUESTION
/ QA pequires examinee to analyze impact of tS1BX U' O, in that it will
,
*pte9ent reenergizing the 'B' train 7.2.KV4uses. Also requires applying *kriowledge that the ir!vsrter-will Oltimately swap to ths
'
DC inpuCN y' _ 6
: Incorrect since all loads powered by the associated APNs will stil be powered from the associated inverte '
- c.- Incorrect since the alternate AC source (1FB) is also from bus
.
.1DB, which is locked ou > :-
,
+
103
. -
*.
. , , w ,. e , ,-n- - - - ,
. . - .
. .
.
.
-
. .
.
.
.
.
9 ), r N Incorrect since Dbi will not tie to bus under these condition' '
,
.
.
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p - .*% w im~%r's;?% .e 2 . A,7 ei: r 42 y L
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amw y LW'js% Qf spas.<b(b#db,I % r's **"=y tc, G !rXG=3r' 6 GfE y h m%w@iq: wf
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"'h - Question Number: 64
'
:
#535 . QUESTION: POINT VALUE: 1.00 l E , .a -
Given Nd following: '
.
'
.; . :. .
. .
. _
* - '
-
Ths plant was at 100% power when a small break LOCA L
' : .l- ..'. occurred., caus an automatic S .
mm
.
si s it M M t"% . - . *
.
'
,
The,CRS irpple'me'nts EOP-L0gd directs activitie . . V
' . * -
J - Q)/ .
"
. (o'nkiiinment pressure is 15 psig and sli>wly, c easing.'
- '
.
dN THc operators verify that all ESF and containtnentTiolation systems liave operated properl (/ -
, [ ' ;
x 1 in meMT to.de$rmining
. 4 .
If the fjtCP are NOT p% ped.at th: ,po =t;(prioc'ioEwlllii$clir;#;an ^ o strategyklvhich r ONE * [1)N ~ gn6thEfoll8@ing' condit
.
h
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w% . eN
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ps a left r0'n"$16l6[$ffContainme I ispray'FMT@/'c
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-
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d$$$'D' Jf k
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5:S
' dTheM$6RCgbear hN$ff'!h h nS" s:and3m
[d orsMill.[
c.$*Ndhb hPeElfcentEili6e em rafures:will be exceeb d due to hebt' input W w.-$ EE / 7~ M ffI"3}I RCf3s@lp g R-e m % .
'd, ItM hk1[e (\h RIirntF@
overalls lea Rd.eEdde9ojslalYilur N6
%w would add 1 (
he,
. - , , ,, ^6 17 QO P' /* 6 .#5351[ff7 '
P- ' ANSWER: g-Vst i).
R
(1.00) het #5351 'C6MMENTS: $ - w\ ., T ,
Significantly mEdified - Changed stemIhrid distractors a, b & , , ,
'
Reformatted stEiin'. 'p[ !^- Incorrect. The RCPs are designed to prevent damage from RB'
'
- spray, b.- --- Correct. At this point in procedure,-diagnostics have not been
.
,
performed and therefore the ONLY basis for tripping the pumps is
.
105-
.
4 .
;
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-
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- . .
- .
. .
.
-
. .
. .
.
.
' ') loss of support requirements to continue operation. Traine'e must
determine th.e basis, based on procedural progressio t- . . incorrect.' Acco.rding to the ERG Executive Volume, RCP -
*
t- ; - Trip' Restart Chapter, if RCPs are run continuously during a . j . . SBLOCA, the flow of steam from the RCPs will be sufficient to' '
! ,- pr. event exceeding PCT limits. (See Pages 6 through 8.) , . . . , . .. .. n, ,
Seg! inj,ect,on si_not.stop ed., .- %
'
- i
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N Yh fr
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e m fl?O0Ny kl'2id q ets
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,-
r% GQM e %fsFa 4..s@t@w +gs - (M,t h d! h khhk3hd b; bh s..,n,g. (vi 4M
@M .. rr >7yw%.s wg w,, m w w . :, a .,
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gy Q 7c.3'p+ m =,.J;;rg-pE.N< vu4 . 4w e Q2A
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M yLQ*d'5Ab:m2. -w % u w !..,D.p g p + p fa.k %. k? er'%I *** m t
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106
.
- . .. . - .
, - - - . - - . . - . . . - - .
*
. .
. ,
,
. ,
.
' Th J?-
Question Number: 65 '
'
-
,
#5344 QUESTION:' POINT VALUE: 1.00 '
.
r . .
. .
..
.
.. ..
.
i ; Thel Woodward Governor on the Te'rry Turbine has failed to the full steam flow;- .
, -aj position,' causing an overspeed trip.- PVG-2030 is closed with the trip and throttle _ '
;-
'
*
valve reset.- An appropriate .. alternate method of controlling TDEFP speed would be:
. .
.
' '
. . . eT ..&-Tlirottle Valve 2865.' -
Mayually t (L rottfpith A L@.,
.
',
\& .
.
.
,
'
' Magufly1 tottle gwith PVG-203 .jj[[#
' ~
-
,,
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.
,
.
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.
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. s .
. .
,
'
,
. i eset the EF PUMP. TURBINE SPEED CONT LGOVERNOR ,
i
;, .VLV by rotating the manual adjustment knob f ly,q , ,
counterclockwise, then clockwise. Then, transfer control to the
'
.
-
t .
.
~ hw @%ME6EENNE$h pWh'
.//
I ' Rese th@E PUNIP' TURBINE' SPEED:C'ONTROL GO RNOR ng ihe. manual ad[usfrhE6 kN8b fully VLVig(y"$$Nise){h'elicl6ckNis*E,E 8E
-
c counler T
'( on th'QCEj l h',1 t-~ *
& SWER:"I epf* &ink., )#MQ' Adhcc: ?.j;. 1 -
L
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y gg*
.
. 24
.
- #53.4)
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y
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. id? R pm .% y(.1.00)' ~.5 g
$> #WP -
*
d A
%
*' -
trf i $D E ,
#53 COMMENTSr &" M.ti * kh*
h
'
?5b I \\31 &p , t
'
.u c: IncorrecCsince Hag,erqdirectly controls _ governor which is faile . .
'l .
107
'
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*
. . - . . -
,y . 7-f 4 s-,9, ..
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. _._ _ _ _ ,
, + . . .
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,
%&/ .
Ouestion Number: 66 '
'
#5343 QUESTION: POINT VALUE: 1.00 .
. .
>
,
. . ..
-
Given the following: - - -
.
'
*
i ,
- + : An'l&C Technician, while performing an STP on Pressuriz.er
,
)
. .
-
PT-455, accidentally trips a bistable for PT-
'
~,
'
-45Q,,
Prsssure Transmitter,iUfe,tyh h results in a Safety injectio Prescuriz']res -
-
" -
--
*
,
- -
*$ b b
" Thgoj5erators L EM are preparing N siflop to fan / f 'to EOP-1.2,'"S .. ,
.
.
.
;
;
- '
:' T,emination." - s
%. .. .
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-
-
f n .
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,
'
. . Which ONEL
' s ' signal?-- N he following will occur when the NROATC
,
*
. / atterhp(ts#to E res
,
'
- .
.
~
,eIESF actuation logic,t is normal F
.
[ f' . it,fvillyOT c$nSl;'diffon. fessl~ angry $ #3Id5}@
~ ~ ghlWo + M f WWN / Mgw
-
* SI wIkh T[iSIe OkPZRfdres$$b 1985 psig, an"d'The
'*
PZRIffMIN
%'
e A(BfSG,h'e~s*aYS', id^de"d in BLOCK.- <
, e , ow - & ~%&&j%?12 u % . . ..m%?) * * SI will ueniau%
h ~TLMf;. Q 'gset d. MIfSMlli resst<an $hdk subsif(uent auto
' '$$$3I$fk and:bliickisu d w a seq $hy[ (tid nw-e +- y ~ - Ess a n . *4 - - '
N MW -Mc ^ 3Eid$h L
-#5343 AN5WE #yd1 1 kh./, D'
Qi
'
~ \ b", % VJ
-
- .
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, ..
c. .
.
(1.0b). v'
vw.u i'W i4
). #5343',h COMMENTS:
O sy[]
,
Significantly modified. Changed conditions of stem tind. original distractof d. Resequenced choices'b, c, & d. 5 - '\
.. T - Normal Wo,uld be ready for eithe,r-auto or' manual actuatio (1 'f ;? MA
- Sl w,ill rese W * b.- .
' Incorrect Manualis never biocke .,i ,
se 108
4 h 3
4:
, < + . - ,. .-~ew- - - , ,-r ,, , ,.- , rwr,.-4 ,---.4 ._,r-,= - ,- w --
y
- ._- __ .
-. . __
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- -
,
,
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;
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'
Question Number: 67 J
.
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.. ;
#5340 - QUESTION: POINT VALUE: 1.00 i
,
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'. .
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:
, . High speed operation of a Component Cooling Water (CCW) pump is administratively
: ,
permitted: .
.l 2 e .
-
. .
-
'
,:,, a. - ' During hot leg and cold leg recirculation for the CCW loop 1
- -
.
supplyjg
. L+ rAesse L IifalL . loa 70. C"(% j f
d1litioryfor e
' '
, the CCW loop- .
.
y (Otirjng'hotIeg and cold leg recirg hT
'
"
,
.' excharigerc <
.. -
5j ,
' [c4 ' * -
ONLY during cold leg recirculation for the CCW ot6pg supplying _
* - - Y essentialload %/- . .. Ycduring 651dils Bli5Glil p' plying f
4// nofis%$6fial Iods a@nd iiERHR,;hisi4EE6 ** ange ANS 1 I O N$$)l )N@1
' #53( hh d 'h fggg yfjj2}$ hgs e 'y!
i
#
#53$4h kyk 6MMENTh.hw ggl9 Modifiedibm -%Tero$sequeNhngtall$ yN g,5 w h *f,.) ^, (
-a I
ya wj p s mp; .4 M
.{s)--
e a gg 4
~'
Risk-Imiso ant: N$;5 Off era ti6ri h J
{(RE orn%p k
IWR TG10894) g <w4svdl b,
- Loop suppfying 'esslelnltialj ads,an'd non-essential load 4- \[#h.b. 'to FAST LAW EOp-2':s."No changes are made to I!ndifphhen
'
? -
#
/ shifting to hot I.eg recire IAW EOP-2,3 SOP-118/Noto 2.0,
/) ~
allows FAST only when that loop is supplying bothuMon-essential
#- loads and Residual Heat Removal Heat ExchhngErs.".
ud %
/h pr . '
Y % _, ,5 l-~T
*
g ; ~,;. ~;;.
*
jA .
.
.
-
%
109
.
* 4
.*
%
- . ._ _. . _ - _ _ _ _
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-
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*
Question Number: 68 )
..- ,
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#5339- QUESTION: POINT VALUE: 1.00
'
-
.
_
..
. .
o
' '
Given the following conditions: -
.
d
*
. .
. \
"
- - - A"'CCW Train is the ACTIVE Loop. - .
.
!
- '
.
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'
J AnpMLi sOpeT4tioriaCchick isteing performe ! C ,. J [ 'i f . 1 L ; G I
*
T -
* '
t j , ,
'
'
* 'Wknjleptessed, the NOR-CS pusbbuttin sticks'and causes - .
Q " f to indicate > 1 X 10' CP '
.
hl' 2A .
.y f./ ,
The CCW Surge, ank' vent will then:
-
r
,
.
,g .
.
.
,
'
A *
(V/*
. Close WR% if the Interlocj!!sgeMIP tsMWPLsyitch is jn,0No m b % p g%) W; p Clqsejfdhetin@terlock switch is in.'OEEagste2
- -
~/
/ b.,
-
wegmey, t awa
* f- gdsgh,P as , M $ eg w#"
ref5- ., . Remaintopentsln(ce,'NO Surg ankihighlevel alarm is presen C
,f ./'ad&# @t,h
% *'
% $m^GyegJ
,ug . .e ,
y Remain:open;beca'use:BdTH RML 2 Wand RML-2B are 6eeded 93 *'
"
(O hgd(30 closphil3CNS'Ufd5TiNIErith M F ak j fhihf* d $
#S339 0 % y$gy;WER:%;jiyqPJ2,=%
'h an AJS 00 'h lib8b mu s sac
\ y\ t Vf y+ ,) ig ,, >p9;i pw a,h m r%ugg rc e ', %x- -
COMMENTS: pptr du,J .
#5339 J
//
. V ..qi j*/A/*r H lu ~W
.
t-
.
-
%- [fNEWDUESTIO ' ' i *
[/-# f
. .-
\
.a Interlock in effect when Switch is in ON position.yu/
. 'q Valid distractor since leak might cause high level, and examinee
.
'thsy believe tiiere is an interlock betweeh/hvel and valv % 5 2 .e - Incorrect"Mcause' 5[uide Tank vedt does NOT require both Ra Monitors to clos .
+
e
,,
110
. .
.-
M
- - - , . - . _ , - _
- . _ _ . __ . . _ _ _ _ _ . . _ _ _ _ _ . _ _ _ _ _ _ . _ . . _ _ _ _ .
*
3 .
-
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* '
*
. . ,, . . _l 1,~
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w *
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'
N.. : Question Number: 69
,
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-
-
#5215 : QUESTION: POINT-VALUE: 1.00
.
.,.-
., . .. .
- '
, 4., l EThe following conilitions have occurred or currently exist: -
.
.
' -
*
A L'OCA has occurred and subsequent failures resulted in.the
.
.
.. .. crew implementing EO{)-14.0, Response to inadequate Core ,
, ., ' ' , ,
' ij '
; . +
-The.cJewis preparing to depressunz.e/the, S/Gs to co'oldown the $ -
'
'
'
:* '
' *% gf
'
, C .
, ?, _ *
During this.co
,y
-
.own, what actions are taken to prevent
'
( '
injecting a[ccdif
"
V#
* .
: nitrogen into'the RCS? .
. di'dhe accum71st6rsildth'EkN$$kosg{"inrIprior i
.
f
-
f*/ * dd'rEidfiiatiodf Sp; app 'YmfP a;ri a A e
,
~ q Isola h
~~ q mdho priorkht d$
ssurization h
,s , /qy w,wnn gg y n,
. . . , top't,e; e" essurizatio :st 140lpsJg in the S/Gs and RC (
. -
eru . wJ WAgg v ! h %f'5$clies op the o 3 #pressurizatkrINrfi
$P#
I
#
fhT$/G NR leveF A
, "" W
.
~
f*% , &{5$6[IS " ilI _
,
.#5215s*% . NSWER :MEY - ,"" %
-
'
CFCE$' u 'I
'
.. (1.30.)(9)
.
4h! e
. .
-. #5215 /p -- -\- , " gQ- V
' COMMENTS:
~
#
-
% e
##p yhs
'
r A}W QUESTION
/
Risk-Irhpbrtant Operator Action #7 '(RE: TWR TG10894) ' .
' T This actI6Mwould beitaken afteIthe deprEssurization and only if Ithe' accu'riiblator c'oUk[liot be isoldted, '
b.- Part of the reason for depressurization is to inject the
. accumulators. Isolation prior to depressurization would defeat the
~
.
' intent.
'
. Requires the examinee to apply knowledge of procedural steps to . .~ -
111
.
t
--
4 t
.' I - , - ,s , * , - , , .~m',
.
-
. , .
,
.
.
.
.
'
3.) given informatio . S/G levels are'of secondary concern in EOP-14.0, There is NO
. . criteria for main,taining S/G levels until consideration is being . '
given to starting an RCP in an idle. loo ' -
.
. .
' *
O e
-
g 9 l $ .
'9 **
t
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A
. *b* /
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-
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*.yv '
.
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.
. ..
g % .v ( ,f ( %
.
5/ <
* , ,
q e t
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kg (QwM+ w^.w--sw @p
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-
D; e,7 % cmgAl e Ma
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. $% }./ Qqqqy%
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,*%gyngpgf AR;;;?sprsy
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k ,[w$Y fhk l%- w% W8@v %s n dinh s/g y "m %;s%p
.
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L.w,
-
-
..- f ,s G %kk%f Cappp Q$ p ,ss a!bMM ? $ n .s @c <nC% 5 l E u: $ j A s )
Mi%g% d s , L ad: v*WFuATF hat &Re:awct AFg1 mu J ih
#
eg kD ma $$p,s, i h TJ/Jy~MIdh y,em'y D e t n Il ph. w D* xp \ u..m a es u u,,
%. ,asw% y,t,uc sQa,r,h'Mr#
v ,Le . , , g$ mmN" N h [m, n, +w,hy ,[,)d
' *
.e W G/.s g5ttb
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sp n, . s * d . **
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6
.
pm 112
.
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. ._ _ - . . - . .
,
, ,
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. .
'
. n 3 6
'
_Question Number: 70 3..w) .
,
'
,
#5349 - QUESTION: POINT VALUE: 1.00
^' '
*
,
.
.
.
.
. .- .
,
, , ,
'
* ' '
t;
,.. Given the'following:- . .
: '.-
-
.. . .
'
.
fn -
. .- .
.
'.
*
*
. Anl inadvertent SI has occurre . .
-
.
\
'
.
! TbgC3Shas
-
eted,tr{epIar'dqperators to. ensure Feedwater
%Q,,
,
L
'
? ,.
'
Is atio i ,
. , . .. .
l~ T I Ahr$ unknown reason, the ESF statufligbifa(e not iridicating
.. '. \ '
( A - .
hj properl .
.;, .'
'
*
.
,
- -
% '
Without the ESF status lights,' select the preferred method of checkingdhe status of .
.
Feedwa@risolation he FRVsMSWM a ;LthelRB,DbuWVskincluding /A thgreason
,* f g ,./. ,
auwsawdk&Q g $ " / M/ Con fisiidic~ a tions - They are; driven ' actual valvs%n
%I y 8 n:
*
Controd,shindic..ations$. I v psdn[v.en e i 5 y controlle: demand-h-
*
d9The,Wa\g:gg
. -
9, p== g%p A () . QQ . igna~fgy$ d g%%&s % ndW $ g AA : r)dswitch' lights 7 ey<are nvenS9 va.lve. stem positionqimit v. I e- - mi, h ( I.- }. u%mp4Handswitch,pm<lijn isThe ,1..z,2aredriven'by./jsmaximum or mi
\: d'shiEMi%gIihldy 3$M .
". ,
..
,#5349[h7
,
.
. ANSWER lhe .
'
(1.00) L
#5349
#f
+ COMMENTS:
Y NN M- A zs y,v(
.
. ModifieBI Reseguenced all choice b . i .. e a. & C'A .ontroller ha,s NO input fr6m stem limit switche ,
- Correct - Requires determination of which is more valid;
;' . indication of valve position and application of component knowledge in the event ESF status lights are lost.'
s. . . Handswitch lights are not related to demar.d signa ,
=
113
,
g 9
. ..
- _ .
.
. _ . _ . .._._ - . ._
,..
- . . *
,- ,
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,
,
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.
%
- Question Number: 71
%c-- .
'
#5318 QUESTION: POINT VALUE: 1 00
*
. .- .
The-following have occurred: -
.
.
-
. .
.
~ ~
- *
The plant'was operating at 100% power when all offsite power was lost.- ,
' '. ' ^
Bus 1DAgas an 86 locRout frEse*fif7 k
"
-
c
,
n i '
- -
* * * -
. "B" D G.has tripp d on low oil pressure.' (/j./. . .
.
. . .
.
. -:
,
7 . .yY q - Given t'ie above donditions, which ONE (1) of the following de jibe 'sdhe status of ~
.
,
, _ ,
the'TDEFP n(Supply (PVG-2030) and its ' associated FCVs? / .
'
,D PVGkO30 sagg
~
#Ed?@ JCVs 7j a. ,5'[quiomatically$$$$$$A3) man 5idfi[kt'tidd[ , manually openeMY2$$fah localth[rN0hES5[ Am ,
mmpg- m nnw; . c M- automat.ically openedgsf f.. aw w'oper)"fsignal re_ceiv.ej ,n; m
' *:.1 -
gan '
; j:p
d ;ag - manually opeDedqdhaglyygen r Ws #gr wmm$ signal;
.
eceivefope _ us
--
m y; y 3 m ut xa 2,9, vng % q2 a
?
y *g' 4 m% wr@Mf y j" .
'
$l h / j
\\ ) Pfd d
%wM h
'-
.#5318k#r . COMMENTS -
-
. . - .
-
' .~',[.a g// Risk) Important Operator Action #2 (Rd: TWR TG1089
-
s d.7b. Incorrect. Viv 2030 falls open on loss of air, reh' ves open
'
!oiEU.V. on both ESF busse U
' Y ~4 a Correct.)FCVs are.lf0. and receTve open signal on U.V. on t$oth ESF busse '!4 P
. ' Incorrect. EFW FCVs Auto open and don't need to be throttled open manual _ly. -
.
* 4
. ;;5 '
114
. .
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,M s- y y y w w-
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Question Number: 72 d. ... .) .
'
. ,
#5225 QOESTION:' ,
POINT VALUE: 1.00 ;
#
Given the following: ,
'
.
.
,
* - '- Near MOL; the reactor is initially at 100% of rated thermal. power,-
'
'
'
,
*
all rods .out, equilibriuryi condition ' ,
.o y tw s,W)
, V*"3m) c..>w r .i j .
, + While'performJng STP-106:001(f Moveable Rod Irisertion Test,' ,
' '
'
' TWO 2)Tods in Bank D group 2%ef Eclared d Inoperable due to . *
T
+ (-@ir$f{ immoveable. % jf .b
'
\ i
'
.
' '
h; The SS has decided to commence a unit shut [owiTwithout rods In order to meet ACTION requirements of T.S. 3!1.3'1 . ' . i
. What ac(tions /) . hA will be requirgd1j .
ma 6tain programme $-mm n
- Tav
.
>% BorateMd;$
g$. c2a kgps%g; NW db* Sg /% . Diluteitojco&g!%p'py
.c ap wk ntrol ax,al fluxadifference%,qp t : T \ J b.- i q %) ' 'e' :S sY% h hNNhh:N%bbEh$$hb?
c. dfgrate'toicontrolfaxial: flux;differenceP4 - U
.
hkhhhk 4
"
f d.k' %Q5ti? I g.dif0te:to 44) W 0hk ymainiain N" p,rogla
#5225 --ANSNEp y *
a.
..
+ -
p- (1.'dC) 9a N'.% gyvDW n/h- hN higd.* r@%
#5225(/* , ,; ' ~ /A. COMMENTS: -
- 'fy g* ,
',8EW QUESTION
.
/ .
~h# .
-
At EObrihe power defect will be > the decrease,in Ze%non and require a
.
'
. dilutichMiich makes "b." incorrec .
4, * Yb i [? 4 . .. is corredibecause need to BORATE to compensate for Tave increas . b. & ; are incorrect because AFD not greatly affected by
. Boration/ dilution.
,
. o: d .- is incorrect because Tave will increas ; ' ,- *
r 115
- .
4 .
.
2 m e y p r- ,ey.-. 4 ,. -
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. - _ . _ .- _ _ - . __ _ _ _
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Question Number: 73
'
;
.#5224~ QUESTION: POINT VALUE: 1.00 -
' '
-
, .. .
A ReactorTrip and Safety injection'have activated due to low PZR pressure. All . 7- emergency systems have responded proper 19, and reactor coolant pumps have been
' '
secured. = Reactor Cool' ant System pressure continues to steadily decrease,-but P2 , level continues to rise. . - -
.
Which ONE (1) off&h
'
:. *
thefollowingphconsistentew& "k ; ditio
. .
iththey,e con .
, ,
V
.
' '
. l)/ - -
k~hksiarizer PORV seat leakage: 4%
'
.. T ,
. .
.
#'$-
bh Pressuraer Spray valve seat leakage. .
. -
h .
'
.
.
<
) '
'
.
-
CD 'd'*""" M@MQA6"ljj"yd*"*"""k,
, ,
, > re?ofC' RCP seal injection:pene6ation 9 ./m/ yuy 71.ae, - pycn n.;u
. .esagg
-
% ANSWER * f3 ""gp]
.
#5224p gb .
' _
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R k ' Q1%phy
* ,,4 .R & y'p(fj@g$
Qy yy (i 1 s
' . w,q _E @ ,. 5 c- gyne?p **.
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#52$2h)
g e m *I 55' .ae:.emE+$$fM bMMIN 7 L - NEWiOUES. ON I n F a1 ~s !
.,
#e*
Nr ChangetbYn
'EWi
~
$$jean hhfif$tidi$tr$f$5
% kb M
N% Q) ! .
~ '
. ._ .
\ ' Correct - PZR vapor space leak is indicated;
.
trainee h e -
-
<* a . r
#
' - conditions give.n to determine probabia leak locati6'n. ?pust an '
' Incorrect - After RCP secure,d, there will be nRspray flow so Qw
'pfessure will not be affecte p
,
' .
mr* * 4 1,
'
4. .,1, gt
- IncorrecWheaks in this area would cause PZR level to decrcase,
.
q
.
.
3r~p-t y, Inccrrect - Leak here would impact primarily on VCT vs. PZ .
. , 116 -
m
.
..- __ __ .
.
t
*
.
.% .
%) .
'
Question Number: 74
. #5319 OUESTION: .
POINT VALUE: 1.00 .
. .
Given the following:
'
.
,
,
'
* The initial reccior startup has commenced following Refuel!ng
'
.
,
%
Outage 6 s h 10, 't 4pe,r h;GOP.3,,,m (-,,
-
' *
u t'% . .
. * Critical gbeenke ta,.deta a
a,t110% r power.wlth' Ban,k D at 142 s
. . .
m %f efj -
.
% ,.8 y
'
.
-
,
^
Q)' The CRS directs the NROATC to increase reactor power to 14 ,
' ah %
. 3%.
.
,
.
' g")
%,e .
What is Sjeynaximutp;W stable SUR
% alloyyeiay@his point.of bow should
// the star iods gbe ' ,anipulated? b m3 % (3DE& ~jF.M+<J -
??gL.~s > m u ,s. '
'& ' }}& 7 .% .o't .
; - a y
-
,,
,% .3,DPMp.f step,j inc mn-0.3 DPMR1/2! step.increme,,n, (%
-
y
! 'Yyud 4' %, ,y
~,a - " - , ts > " f. , '.i;s : %y n, {~%n., e
~
*i&W re.1 step @anc%&.*h&j{{Q;};e ()
.
m c ,M dgyt,,,0, DPM,u..if
.m -4.e... ,m ._2 -
g ,.f (
..
' , %%, Ej90 g4TNp.,me.nts .an '<i," g 3
*
d. VJ1gDPM,1/2 st6pjrlcrements <, i 0*'T 3w up m:d ewm .& .2 t @l'x/
. /p~, e s
w-
#5319*j 4ANSWE.Rfp%;, f.y p g/p[!J3.+MR5f
%y ;w,% y u l h1 O'~Dt W .
(- .}f. Ly%b",h/th+h([Mt
,
,.
"
(1.f0) (v.I..i m -
;,w
~1-
, ['
('j..i O '. #5319 g/< f .
COMMENTS: rt, % V,.
. a. ,& ./
Incorrect. Not per GO N( g..s W m % '- l Co.rrect. A startup rate of 0.3 DPM is us d for a positive
"in50erator, temperature coefficient. Thei.nitial Rx startup following Refuelin[ Outage,10thas a poshNe MTC: Rods are moved in 1/2 step increments until effect of rod' motion is evaluaia . Incorrect. Used prior to criticalit .
e
_ _ _ _ _ _ . _ _ _ _ . _ _ . _ _ _ - _ . _ _ _ _ _ _ _ _ . .
,
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I
.'Q.) Question Number: 75
'
...
,
!
i -
: #5121 . QUESTION: POINT VALUE: 1&Q :
- .-
'
.
l
. .
.
i . The Shift Chemist has notified the . Control Room that 'B' Boric ' Acid Tank (BAT) has .
'
<
, been sampled SAT and can be taken off of sample rectrc. The CRS directs the AB
*'
operators to place the 'B' BAT in sta idby. While performing an Independent l Verification of the lineup, the ABLL operatotdiscovers a valve in the CLOSED '
. <
position that is require 4to be OPEfQ. Whet,6ciiEJi my11 be taken? . ' 'i < - r is k
) Lw Q l 7
' ' '
' PolitioIrtti's{& valve to theL OPEN direction /and initial the " Verifier's- !
I' ' 4 klglafs" blank o'n the Valve Lineup Sheetq/ ( g; { t , t h. Reposition the valve and have the ABUL opere,f 9torTerform the- .
'
% verificatio .
-
U '
,
- ' ' ' *
.
' mmmsv%i $ $
<-
- I
/
)nq h %) pervisori~andve@positio(jhe Shift 1Su emg,,an M& m valv l 155t dupervisor, repositiond e, valve to the OPEN
%(Q+f
-
,. Infor:Ti +
] - 1 N I""'
.
NQh positi5h50iiiiilIjftiltiiftlie*"Verifie(pNMbsifIriltfaisjblan
.lineufshiisip{
U
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k)
' #512 ANg[ER: f[f, l_
, f.*]$ .
(3
'; 1.0D)' , : l
* ;
[}1na O" ( hlG **
,,,,'
- C0$ py J
-
t J e-t __
# 12 t hh f{ ,
g Significantly modified ['f3evise sten 1(angdistractor b. Also c'haked ~ ;
' ' .- .
y j order of distractors, Modi $. {ron, Obestion 206 f- '
..
.
.q '
.
,
'
f ,. Shift Supervisor must be notified before repositionfrIgp valve while performing an independent verificat:on o <
.-
alve lineu l
- ?l n' correct. -The verifier t aes not initial forboth operator
.
.
. Terification $4
*;xF
?% -
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<4 ,
.
p.f - %,,: . s
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118
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-
- - -- -.---------e------7 '
-_ _ _ _
m . Question Number: 76
- -
.
,
#5227 QUESTION: B
. .
During shift turnover, the off-going NROATC notir ed that his relief appeared very . tired. - Questioning revealed that he had been ahke for = 48 hours due to driving home from vacation. While conducting turnover, the off-going NROATC had to
~ .
continuously r.epeat plant sta.tus ite,m.ws to h,is ~rel.i,e j ei g b pd hi n,_ t s . The required course of a, chon for'the off goin~gWROATC%.ould be to: .
,
~
(Sj\,V " In ]l
.
,
, _
, n'the turnover sheet, to acknowledge that'!he oncoming watch has at least been briefed on conditions, and thertiell the h
,
# *
%
oncoming CR .
,
v) s .
'
Q - . Sigq,the turnover sheet and reemphasize major ite s ith the 09 . '/ f o'ncoming,%.. NRdhT5d _.4$ dRI5![4'] ,:%99ff!!! ^
*.t.)
. , *l '.m.-
%, .. .- '%y y % Not' sign the tLittl@over; sheet until confdrifng with the off going EW (D '
Supe'vis8'rE9 I Wl% r awn;,J
>n sa W:R
'
E2;t; &:> c +: 'w S 5~..m.! c; km
.
, $ot sign. (the,turr o/ehsheet until the/As.sociate Manager,(Shift i
"
~!S O
%;n.0erall8risWAc)tifiddC9i.945@a 7,:
/MP
:.: - G,.y %g u mfp 1 w , ANSWER $fg qq::r.aw+[ w.xe%R %. o ga
#
#5227 fr5 ; g b. P. <
'
rp,73-$ C ea 9 %p g h r
[ % ne u u[I U s{(W k[%N @Y [ ? ).
t be ,
#522h[y\
TNYffWQ ~d@,5 nW
, COMMENTS:
f4 [[. % .pa
'
.
w me = h
[f.c .~1 h' . . \,. -vv ,v'
a> w .
-
% er,je NEW QUESTION f%
s
/<.-)
No per SAP 200, Conduct of Operations for shift relief %>t , . r y~',+ , Yi v,. --
.
,
'.c% .- :x.; . .b '
., .,
pq ~ 119
.
.
.:.. .
-
.
.
.. ;
. . .
-
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.
'
Question Number: 77 [ 9. x' ,
'
i
'
#5228 QUESTION: POINT VALUE: 1&Q ;
*
i
'
,
+ . .
~
MVG 2802B, MS Loop C to TDEFP was tagged out for valve PMs. During the PMs, . :
'
the valve and the. valve operator remained installed. The danger tagout for this valve - *
' -
is now ready for clearance. The actions required to restore the valve to Its required
,
OPERABLE
-, p.osition are:
- .
.m
.
~~ m . .
. ..
'
* *. h ' Le / \ ,,
'
,
.
a. . Clea, rTang g on brea r.r'emove MCB " HOLD" tag, open l
' wa(g,\#p?ta(e* ..'
,
'
-
', " V,/ -
.!
bdlear danger tag on breaker,.sopen
.
,
ut
, . .
valve locallp'solear,f
. .
.
.
'
.
. .
'
dang
.
on valve handwhee .
..
'
'
Qbc.' ,' Clqar tiiksket danger tag on ypj removsk' litRC'$ye handwheel, f clear da j 4/ r/ Vtg %, y -
~~~"jijifidpen$yy$ike, ggyW e '.
% t e lva -m m a
. {n Cle]affdange, n fofrJa onggea ger
)
- handwheelt leavehalve presehf
,
in,ker, cleardag,%Q' , m, G.engx WamcQ@% positio .
.% ww j . #5228., 5 ANSWER;q$p g ;z 3 *R n;s.n)q; j W+ gag.Iy py (w) .
gl>yha gpm t, vw w.~ - -
~m.S. : s ,& aa ku "
W) i#gt ft L, c.$% )$iDN(M00[Wg "
! l11qlNOr g a2Wd$;h' e<, ' #5228)'.
COM91ENTS:d4 9 X 1 LA
/
%/ </
L T'2!@@M&p*Rd@hd[E/AM4e ~h ? R;b
--Q NEW QUE5TIO b' .,
' %
-
%
Incorrect ifnce($Yh!N\h 1 not""' all tags.wo'uki have been cleared $ fore velve b' -
. ^
-
[' .re., .a. .
'
,
'Is repositione s / .
Incorrect since the valve should_ NOT be operated 4with a tag t
.stQ
/ hanging in the handwhee M u TA*
.
'#
., R6 quires e,xarninee to apply knowledge 6fjagging procedure and knowled{e!that 2802B.must be z, OPEN for" operabilit ,
-4 g Incorrect since ' valve must be opened for operabilit .
.
u 120
. .
,
.- . .
- _ _ _ . _ _ _ _ - _ _ - _ _ _ _ _ _ _ . .
.
.
-_ - - _ . -
-
. .
.
.
. .
'T') Question Number: 78
'
#5306 QUESTION: POINT VALUE: 100 During performance of its quarterly operability STP, vibration levels of 'B' MDEFP inboard bearing are observed higher than those allowed by the Acceptance Criteri If the pump is to be classified as " Restricted Service," which ONE (1) of the following statements dsscribes tl),e labelipg rFq'uirerEEntfer'the.MCB r switch. for this pump and
- -
ita subsequent statusi' C, 1 / -
" - ', f p ** f d l
1 C Gfw ) .
..
. Ang}ra,nye o erated if neede R&R markur is hun (g The pump IslNOP ,
- %n orange R&R' marker and a red DANGER tag are hu g.) he pump is .
'
.
Q . INOPEgABLE and 35d@I A cannot be used for.angeason.I_ hd ,)/ 6 OPERABLE ONEY In 'B' I
[c,[*/ An orang @6.iR&R [har@k MaintenandeMdeKWbut should only. tie',used An orange R&R' marker(*l' $. N %
an?"'..]W&$il W' b a' red:
%.d OPERABLE an9 iant MODEfbbjjhould DANGER ~ tag are hun umpis 7? erye$gyy s%'ijua'tior)g%g{y$m,7yy[
f
~ ($) d, k i #5306 y'QdNSWERDQ J} A e!shE"[! 9 [.,., .7 d(e O 4D. %NM i } :h.,fyL x -86 O T tsad >
we
#530 3'{ 8%%(LOO)Mff u.a NePf M P {'%5df@' :
S ,)f,<(?
***
f/} '
- . *,
v
' COMME $m :[,'/j// -
p v-(/,f[y.Significantly om modified fr%,. e
,)Juestion
-
.
'
'f with all distractors. Order of the distractors was also cha&g)e'd
'
f) SAP 205 defines an inoperable component tagged With an ORANGE Qm
"R&R Entry" Tag as inoperable but can be operated if'neede ,
Y , , 4i ;
' '?, --
4 P
~,
*
yn
.
121
..
.
b
_ .. . _ .. _ . _ _ _ _ _ _ _ _ _ _ _ .
,
. . .
,
-4
.
.
. .
.
'
.%.U Question Number: 79
'
#5220 QUESTION: ,' . POINT VALUE: 11Q
{ Pressurizur Spray Valve, PCV-4440, has failed to fully close. A Reactor Buildird
.
entry In Mode 1 will be required to check the' status of FCV 4440.- A Standby Tearn * has been. assigned to assist the Entry Team, if required. As a minimum, who,must accompany the ' operator making this inspection into the RB7 A 3se, j cond d'g Q , g y
.
,
,-
a.- Q Q('tiver /e/
.
,'
.T %,.?"perations repr6sen(a
.
s - ' 7' .
'
.
'
T .b. , ' f)/ealth Physics representativ : ,
%g/p h J[A,
,
.
-
Any SCE&G employee who has completed SOT . *% 3. -
. . ny ,
.
,
-
.
'
.
.
Q d. - repIonent.ativeEffs
. Qealth Physics$2rep).(ese0@tative i@fW di? /'
s' and-a sec vt9 e
. 3rdpBE%.*g n.%%3h g .p siag g: M g g$n #522d cydy * -
e% ANSWERN q wmr{p &pgn' 4s Mrm;p.> s '
, [( %
U kb h % IGl
' Jphi$ 5D h$h . ^' . ".M I-= -
COldMENTS%is%j@gh $B M
-
gyl 7WI %(*") -
' #5220) -
U V&rfj ?' sis 2f" did F
#3 Sidhifdan}0^mo%(:?;n %*"
r yA mg e . l
[ y. g , $;,' rid all1o#dr s
<
=
$k dddifi dIt $ p r. e*ek'31ce b, * esignates%,attw
.
OAP,408 at poweEG IttOlii6Efl hiil b61ijira"el2)ifEP)ysliIs#:individ,ua representative.' N' . .
~
# '/.j/rV s r} e-4 Ji
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122
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_ _ _ _ _ . _ - - - -
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*
Question Number: 80 9. .: .. ,
'
#5126 QUESTION: ,
, POINT VALUE: faQ
.
.- .
-. An Alert has been declared due to a fire in a CCW pump switchgear room. The .
.
Control Room has implemented EPP-013, Fir'e Emergency, and all emergency '
*
facilities.have been activated. Under these conditions, the Fire Brigade Leader -
. ,
should.make his reports to the: -
.
-
.d > k .qigL.,
* .
TechriTcal Support;Ce%m ,%
? -
' nter.p m (" % ,
',
.
. ...
. ..
;
-
, ,
:
'
.
_ v* .w Q (/){ '
'
-
.
'
. .
,
. .
Syl 'Supervlsor's Office. . %. ;
*
*
*
. .. , -
Emergency Offsite Facility .
,
'
$$"'
'
?
k/ EAic35,h O$$s5BC$5f
.
#5120s
.
ANSWERNfyjyr"u; sh Vd lfl 7s [Dp{jjh.Jw' ,f ) {IP If
. - - , "
fS-
.b COMMENTS, b 3 1h)f ()
py $"?wgf{lj/$gyhi0 f kbg k f
. _
"# '
'U
#5120) Ql>j j Sigh lfi# anti /modifis$;ffontQdest;Yy&?&
, f,h
'
ion 1787. Re'viselfstem and dMtractor
' ' *
a. A)y&I: hah ed bajmy ordsOf[ 1 ww% Ira ^cfor dis' f . #F#
\ >%\ #was,
~%ny C~;ac gr pp)y874%y
,%
s Per EPPS fot to OSC. Fire ivahon:-al B'rigaddfe'dd5Hrh'p(keams7nciddin e o'
-
._ .
*[ activate l'(i.(f)%rts:topontrol P Room until dSC)s
. ..
.
.
g-n/ -
~\
k# m e" 4L
, '
3 },q
.
-
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,
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t
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-
123
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i
_ _ _ _ _ . _ _ - _ _ . - _ . _ . _ _ _ .
. . .
.
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'
Question Number: 81
%... -) *
,
. i
#5230
' QUESTION: '
;
-
. , ~!
All of the following are major assumptions made regarding Fird Emergency . ;
-
Procedu'res implementation EXCEPT: ,
;
<
e
...- 'a . - The fire affects onl
-
-
: r- '
.d
'
e '
*
i., 't .
, i h~\equ,lpme)%. c + y 'A
.
4 .
*
.
' All , j ntd opers% ible orf**ds[st,eplac,ed by swing components. . . , i
-
,
.
f - 1,)/ 4 . .
, . , "
I' ia'Itions as described in the proceduie<.canig'perforrhed as - writte /g; ';
-
. .
. , ,
'- '-
.
The only accidents or failures'that occur r aused arebythosa,c% the
'
'
.
!
-
.
#5230 %/ / ANSWE
; Q$Gt$$$$$h-M dh? *
i l s 32gef g 'Ogi A;ki 4/~[[ 4./ ug$ ] % w#5e# e
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R$ik}=mq'iG8Dld7 # #;!sgy2r %
. 'TO3 ; 4, " .. #'52'302 * . -
_ COMMENTS %g NE
.a ir$4 QUESTIONA d;;;M
.
..J n
<w e !yd mygg p;w 1%gg
:sst in ., /
i ()=)
===
.
i
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d
g Wc dsareNg L6A a. Corre,c&g:^5 sted t M F E s ,rare a6na'<}rf}asskmptions aApE r Id u u. y tien to.Jegpond tddires in either tra. ~EP-2.0, 4 lo, iry@ 2.1 - Shutdown nd c[ j [ ,. _ .. " , /,.3.0, 31 - Shutdo{wn an,o)dyr;fth'd;pla(t sin f d*:cooidown-vv thh plant using 'B' Train equipment) = A, . , . . . > ' / ' , ; . N*# - %& . p ) k . }}