IR 05000395/1997300

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NRC Operator Licensing Exam Rept 50-395/97-300 (Including Completed & Graded Tests) for Tests Administered on 971201- 05 & 1212
ML20199B314
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
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)


Text

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- I = LU, S.- NUCLEAR REGULATORY--COMMISSION.

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REGION II-Docket No,-: 50-395-License No.: . NPF-12 , i ! - Report Nos.: 50-395/97-300 - Licensee: South Carolina Electric & Gas Company - , Facility: Virgil C Summer Nuclear Station >

Location: Jenkinsville SC Dates: Operating Tests' December 1 - 5, 1997.

Written Examination December 12,1997 " Y dda ////[ff~ Examiners: e , ' ' JohnMunro, Chief %1censeExaminer-Richard S, Baldwin, License Examiner , Ronald F.

Aiello, License Examiner Stephen L.

McCrory. License Examiner (RIV) Larry S.

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 .

POR ADOcK 05000395 ~ + + .. ;V' PDR j.

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i - . 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 S55.45.

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

8 100% Fail

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

' .

The examiners identified a generic strength in the operators . implementation of the facility licensee's STAR program (Section 05.'). No violations or deviations were identified.

. \\ Enclosure 1

. Reoort Details Summary of Plant Status During the period of the. examinations the Unit was at approximately 100 percent power.- 1. Doerations

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 atmosphere.

Communicatico standards were adhered to and the operators appeared attentive to evolutions in progress.

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 tests.

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 test.

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 remediation.

Enclosure 1

-. - - -- . .. ~ -- .... - - - -. _ < .

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 process.

. 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 8.

(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 weeks.

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 noted.

Enclosure 1 .- _ , -.

__ _ - .

(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 terminology.

(b) Eight questions contained distractors which were potential additionally correct answers.

Four questions as written had potentially no correct answer.

(c) Three questions were replaced for low discriminatory value or significant overlap with other examination test items.

(d) Technical errors were noted in four questions.

(e) Approximately 29 questions were reclassified from "significantly modified" to " bank" questions.

(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/As.

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-301-6.

" 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

  1. 3 credits the BOP operator candidate with performance on all six Enclosure 1

-=- - -. - .

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 - 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 value.

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 revalidation.

05.3 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-1021.

Forms ES-303-3 and ES-303 /. " Competency Grading Worksheets for Integrated Plant Operations." were used as a basis for the operating test evaluations.

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,

  1. 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

-- - - - . - - --.--_- -.- -. . . - .. - .

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 II.

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 Building.

04 (5101) The preferred method for tripping the reactor following a control room evacuation.

11 (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 designed.

12 (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 closed.

19 (5326) Status of the operating systems providing cooling to the Reactor Building with a Loss of Coolant Accident and several emergency system failures.

21 (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 position.

40 (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 Pumps.

45 (5356) Method for refilling the pressurizer per E0P-2.1, Post-LOCA Cooldown and Depressurization.

Enclosure 1 . - .

- .

58 (5131) Required operator actions for failure to achieve criticality by the desired estimated critical position during a reactor startup.

Oneratina Test The operating test was administered during the period of December 1 - 5.

1997.

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

  1. 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 actions.

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

  1. 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

  1. 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 overspeed.

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

- - - .

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 SRO.

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 average.

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 identified.

Enclosure 1

.. . ..- .. . -. . . .! 8-PARTIAL LIST.0F PERSONS CONTACTED . Licensee S.

Byrne. General Manager. Nuclear Plant Operations R.

Fabry. Training Specialist- -R, Fowlkes. Manager. Operations M Johnson, Control Room Supervisor, Operations D.

Lavigne, General-Manager, Nuclear Support Services A.

Koon. Supervisor, Nuclear Operations Training.

T.

Matlosz. Manager, Training A.

Rice.; Manager, Nuclear Licensing and Operating Experience R.

Quick. Senior Training Instructor

UEC: , B.

Bonser. Senior Resident Inspector ITEMS OPENED, CLOSED, AND DISCUSSED Ooened NONE Closed NONE Discussed ' NONE < Enclosure 1 .): -- ,

-..-=_ . _.. - ... .- -.-- - - .- .

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- , , ,.,., -w- - .,

. . 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 ' observations.

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 scenario.

During the second run of scenario #1 (no. 3A), the simulator computer . locked-up.

Enc ~;sure 2

- , V.C. SUMMER NUCLEAR STATION ANSWER KEY . LORT*RO-96-01-FINAL (NRC) LICENSING EXAM FOR RO-96-01 Total Points: 100 h .

.

._ O Question Number: 1 \\:/

  1. 5303 QUESTION:

POINT VALUE:.LO)_Q Given the following: - The' plant is initially at 100% power.

~ Th.;. s AO reno'riYthat IIliaiWacuated the TB due to a large steam leak.

TB

4 y~t p~4 ~p (f '>f g u . ,. , 1.<- r ts , .. .f otal steam' break flow is 12E6 lbdi/hr././ . . T -

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%g.) The following protective actions occur during,tiig event: o , v . u % . y.

\\ Main Steam Isolation (1) av, - , hj % S u. Safety ht..-e(2]p~%WbhEE~ - w w n 72" 4 r/ nr iq e.

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  1. 5303 COMMENTS:

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. m.a . Placing the steam leak in th:3TB will help to eliminate the possibility that the examinee will determine thai,:SFon IIiglisteamline AP will occur first.

n b.

Requires examinee to determine that a steamline break in T3 will cause steam pressuie to decrease to 675#, and apply knowledge that this is the setpoint for both SI and Main Steam Isolation.

-

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m 4.y} Question Number: 2 , e.

'

  1. 5094

. QUESTION: POINT VALUE: 1.00 , Given the following: The plaat'is at 100% power when a SB LOCA occurs.

- RB pressy,re/s 17 Tand hEIwly~"Thereasing.

i ' - The NROATC, rep (hps . - Le N. ~L ysj r 'I f f . -, s ,

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orts that neither RBTpray,pufn.p will start.' ' - - . d..J'# \\ 17 g ' ' - W. ARD recommends shifting the running RBCU Fanssto fast spe The - . '/p Which ONEYof the followirig is the consequence of running RBCOs,$ fast speed? , (/ - .h.

mcW e . Hi hlco tainm..en_tle.m. p-.e._ratures.y'-will<o.,verheat the motor a. d cause . a.

n Ie gm , . -% ya 4/ / th Jtis t, ion to,:; burn.

ee, p-xim,

d%2 mfg 1 y % %g Excess &,P@yn f,-t humidify 4Would result lE$%l:. Win; ground i % a.

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ig %, windin$$$$$J )CS$$NM h, /Higherp$M$i$dMM,55$$@l. bus overcurrent lo(c@ h++ A $ . ut.

e.m c.%y#:W i6b current wilFeause a vita .ct ' 4 %m%rcg%dW!yMR fV! P' tad,t

E d, %<zO,H,iyit,s.e,nsity'at,mosphe,re'would:gy$. k s

A MW ys m s . ~ d cause overtieating or overcurrent m c [sy}t 9tn 'due to hJgh.m<otor curr..r - w %. m:,f),~/.9 e c-e, ent.

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  1. 5094 [*r's.

ANSWERG @t.([l 'in (%h,W C% , . , . ' d.

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  1. 5094

% COMMENTS: h) ' ,/ m.

A 'Significantly modified - Changed stem andAistractor d.

  1. RsBrdered distractors, 4..cs

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jW " Motor widdings desig6Bd for higher atmospheric temperatures a.

and insulation will n'ot' burn, b.

Motor winding insulation is designed for high humidity (E.O.)

c.

System is designed to trip individual breaker before bus locks out . on overcurrent.

.

.

. . .

- . d.

Correct - Extra hurnidity, increased air density, excessive current - Requires comprehension of background information for EOP-1.0.

, , .

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4, ? ) Question Number: 3

' '

  1. 50951

- QUESTION: POINT VALUE: 1.00

' 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 - " - HQ operator action.

' , ' ' ' 4.

Clygrging lige flo%decr isEs}ecause the lowering VCT level ' ,. . IIstrging ptmp>NRSg . . . de ea , ' ,- ,. _. . , Ch'a'fging flow decreases, so less flow is'availib(e to the' seal.

L' b.

. En[ection line.

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. , ' %'. - , 'b ' ' t;, Charging flow increases, diver' ting flow from the se,ah. Jection - - . & ' ChbrgingIfrow(in eases, increasing &$&hb agff ZRijevel and pres}sUre [,,['f d.- . whic i,de$feYe sealdnjection$$g$g]fdE8 f ['% We y; %,s py q Sh ' $ l

  • ' ^ a?

/ '&dM*S% MisWS& (?) H A au,:) . #5d94 AN W,. *

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c; y ,-? - - - h .j jgg 1.00) jl

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  1. 50 COMM f

- e.g. . Modified by resequen,cing c ice,y 4.e. g%@- . . .M G** * ', % T;vH Wf 9/ . g '- . . .r a, ' charging flow increases ue to level error r=. - . g) incorrect since'sealinjection line does not come<g . ,B off.,same line as i N / charC n9- "\\ - M .>-s h1 'Rpiquires student to analyze effect that fdilure has on system and c.

., predict effect. Student should dMermine that FCV-122 opens = increaseicharging 5tlJthat hiih" charging ilow is a possible ~ cause.

- ' d.

Negligible immediate effect on pressure- -

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- -. -. .. . _ - - - - . - .. . _ . -- _ . . . . ... -

. ' . . - )- Question Number: 4.

' '

  1. 5101

- QUESTION: POINT VALUE: 1.00 _ . . . Given the'following: ' . . . , ' A plant startu,o per GOP-4, Power Operation (MODE 1), is in . ' progress after a refueling outage.

- . y a p,t y - .

g..m,V%

- . y . React a* .n ^ i /, powetis at 54 5 pu op - -- . -. a rfy .. .. . . . bep - Tp'eThlft Supervisor has orriered sn im^me,diafe qvacuation of the . , . l' .s , ontrol Room due to a Bomb Threat.

F,e s- ' , ' d, \\ ~

  • g*j

,

- . , All AOP-600.1, Control Room Evacuation, actions,mus be done

- Q . ' locally.

  1. -

' gg khk QG$$YM&e$lMgY ?/ -. _ _, t - k'/ - inal36Ess/i@ ann 6unced that all. card rea[dd Securif9 i6lf-}IDeIto. sabotage.$9$My# '

' tyk Q1.?a = n %k V. ine?w%%s (% CET 1 ' ' p n n + (& rip the;Ms&jto trip the reactonWou b, The 'pfeferred (approved)]pieth ' NA JhSh hrddf:ftk &5$N5lh Qh - .n df 1$0

in#uMiiie fioin tETEfonUStandard.- b' b.h. k 'kMMN8f$iAhy9%f 6l$ [J a.

'

gpDeenergize ' Buses 11 A, I1 B,[and"1 C.

[hK7 b C+7%5g*[&;.s Ni AN>} " ' r and c.

A % -\\ ' ' ~ '

rw u.

q V .d.

Deenergize bu,se,s:p.qBih JC1)J h) e <. - /- - g ~%Mi(V.\\Q-7r - h).

\\A,. W -

,.

- ., , jV') ANSWER: D / y

  1. 5101

/ W.

. \\ 3% (1.00) y a.

.. "Y ~, . %.x '#5101- ' COMMENTS: _ L-f.f ' y- ., c.; y.\\ - . ' NEW QUESTION a.

. Correct; If not trip from CRDM SWGR Room, then trip Turb' ine.

' _ . b.

Will trip reactor, but also lose all secondary plant equipment.

.. , .,i

, ' e*

.

g .

_- .. ..

_.

. 43S ' c.

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 action.

. . . f .

yr** fil P'N , ,

.. i, je ,

~w f6 L '% Qf fy

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.

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.... @(f'YMu W '74; w, _qw. .i f

  • )Qp3l, GQ@ (I 529Ed a-

,i MMTdY (D (% w@G G A A a x6J E C Wgiy%@ easa s se q, M ww; /w4W gew r* U x e C~ Jk, 4k%w%%MM&W,w - a%> t,,],,s w\\ r~*,g,, 2-m uy : *. a. m. ue w n.c w

n v r

Fq r pf. ;,m eg^y ( u. [< { h f' %*,r 'y4b. AoiXC3 e N@.. s W'/ j.,5 . D , t-a a' %s ths._%* m. W $ Ye- %,(l$. ml ~ h..T.N P %g'$,C ':~. %... h,( &m f,, .N b V. Y p?t.i.

-

. C .C m

% % 2c QWP i $, $ s.. s&hlal L:h \\QQc. g64.;;;;~ W.

ris ilfh'r.'?f.>.%lllyyyy.,p G.'s]_[.y;s Y r . >

.

tw' t %*6 W g- ?~ *N+%, . % \\ W9' w ' R f**,h,

' w,, E ' $ f " r %.? ~A:= . )' e t k.h / / j '.7m /.g ik V %gs %./ - in $, i k '.g& ! s w Y,,g 'f.. 't., 4*' , t~ g f- / v v, h.

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. _ .. _. _ _ _ _ . _. _. _ _ _ _ _. _ _ _ _ _ _.. - _ _._.. - - : .. ... . . . . - .

. -M' Question ~ Number: 5.

- + ' u- . ,

  1. 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 implemented.

, > . .. ~ d-fe83cU!!nglhad to be implemented because:; ' Based on the'above a3,tions, blee n - - . -

  • p L

k. 3 p v s, ,* . . % %#. , . . + . (assurne all EFW ip4:6avallaN.)- (,// ' , '

, ' ' -.- yV

%%s2 s . - . ., . . . " ' Interlock has prevented a Condensate pu,mp+from being l . , -started.

- - , , . .. , i-b.

A FWBP could not be astartep[?lg4h 4l - ' R$5$$fh$l$i N f .f.

- + . cotIlb / c.

T Mwith Low T ".% ME ikNW5h k,not be reset'rluetto +-aq , ." v m n,r m - [% - N. ~nq pt thpp@NNk

e Thet ondensatelpump ke.

d.

C ngtoniDAST hl leve. l.

g . f 8 ' NE j )W$RhN$gdy (j.,=j e%.:,p~.

  1. 5223, ANSWER (

g li y . -, i y , , -(J. k,. < mu ,.

-- .. D.

y q h ~5 + . _ %[k02m, b i '

  1. ['

. . %g2

$I N id W ~ ! r WCOMNJENTS ejl

  1. 5223*-

NQXffff)P D Y L-

Nt Le -

\\M NW OEST j) CQ, <,; b Actioh \\g- [,. Risk-1mportant 05erator(w -).is inco (REF TWR TG10894) UaQ - + - , ,- .m.

. .. . ' a.

started.

~/D . km) bf is correct because FWBPs are unable to startduesto'DAST low I ' level, \\ t. [ . ,-

Tavg sh6~uld exist fott,fiese con {ditions, MFP

' c.

. - , ' signal, d.

is~lncorrect.because the DAST has a low level.- o - '. :: , .

e f . e . . .

e

, M 5 . . .2 > -- . ,- m, -. .-m,. ,.,, - - - - - - - -, -,.,,

. ) Question Number: 6 '

  1. 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 Duilding.

. a.

Aux Building Lower Ope'rator and the Aux Building Upper O. rator }$ "FeIopt ' ,8f

pg p j '2 rf

-

L+ r t. ' ~* 4 / . b.

Control;Buildir g Operator and tiie' AupB0ilding Lower Operator - ' - . a . c .. .% .r; - u .e . 'M% L p%%. / ontrol Building Operator and the Roving Op'erator cd , / % . t s.

d.

Aux Building Lower Operator and the Roving Opetat6r, - M-C]f.

A,A & u.;m t cC53.L.= m. #6:mnt.., .en&.cf [ /. e-c.e-ene ye . f . ANSWERb..4,A,s.. h C@' umow4 .K NXild42 "f.;4 / ,- . f-e%

  1. 5103s/./

W.S ' = A & @rM Gia25409 e~" A 'GdSp5h i f N e. (.1100)yt. pp,1ce,c,,, g' vi genog . g.g5%etcg' ,rg % b.

e 0 t e.m.

..:, o

COMMENTSiq@~g:p,g/.u t'.~.m.m ~ ? g a.y wc;: ss,.y - r% ;- _vm1 c

~% . ~qf a ? g!&.w, W ' N:.? ... ' = I p 9:4( ;24 sgdt(.jn'*y.g (w} " . .

  1. 5103.,g

,. ,, ~:;,'.. :a a we wn e Significantly m(AfYT'I.. +.h?$m,nx mw.odifiid.AChans.hd.

.'E ?? h5 -b W * &.Y $ N O 4.r%

    • w~7 ([)

. - w.., . s,hoicese u %s .g w.

,- y e; ~ /4s,;.4 four;W;w s)r >% gin % gy (ks c r c* - 0 :%. YpH"'f '"*:n W (a w uv new %' -r1 s ., asiocated.;.a,:r:m.w u;q.n ; g..rfd Building Operato.

EPP-0131reqdirestContro.ll s - . lidirig'Op.eratiiria re . #- \\\\y a where fire..m.n.. y u;r, m : v n e e J a ('i v[;jii, ~:m m(b y ;;(x/.' t [.r. - - 6:k U' Di % "[ tsr x: . ~: y *g , . a V y A..*Q;%g& i.

%~ v

. )#j?

Q l ?< . - A.

g n

j f"% Y.n, &., m : ' f

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y , _ ~ 8%}

i . I

_. . _ _ _ _.

_, _ _. _.. .. _ _ _ _.. _. ._ _ .. _. _. _. _ _. - . . . .. . . . HQ) Question Number: 7.

' .... -

  1. 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 based on S/G heat transfer rates.

m, TubinejoahnchI dicabyIfi[hslah [p essure.' b.

^ -, - . - Q pa M ' - .. . . . . , .dAjficiency calculation based on'mairisgengatgr electrical - ' " c.,J output.

-

\\ IA - f , T ' t.

- An average of the THREE (3)' Loop AT calibrations' - - .o . ,,- , f jf*, hNh b f,. f f - %> ~ I$E% %*i f@IEB?dP ' ' n4g:g'y!W

  1. 5105~

ANSWERvww. ;b.m, %-,$

Ya17

- ,: m

  • )

- Q%l$&W ' ggga$ay e a j,(j]@ A r/ $,h y 9~$' V,m) - $ a.

j hj& ww-t L s

,M.

  1. 5

SI h - i $$)

  1. )

D[COMfflENTS $"Eph4k.ph ' s$$$f [,;.d [ < ' - M yiresequencin{giall b orce374Rbplacidsdi'stractor d.

"'-* - %Qt.ddbh W f ~~ WM ^br vacuum, e h dhk {*- %: , ,, Does'noticonsi er.effic;e% -w nc copdelis \\"\\ b.

turbine sid,am foASE } \\y J f /e/ gp m 'sj a7s .. \\ *.e % ,, o '.

,

c.

Efficiency affected y 'of FW heaters in service, etcf) ' - . . . . 6/ t - A.

AT readings don't intrinsically reflect thermal powero ~3.,h f kA - "f z*. . D,a ,

j '*

q Tp %-::

aq

-

, . ,..., ..

. o .

, gi . , - - - . -. - -.. - - - -. . .. -. .- .. ... -

- . -._ .. _ . _. _ _ _ - _.

. . . ~ . < . - .

%;.) ~ ' . Question Number: 8 ~ ! '

  1. 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 ' Co?h. s h.e - ntinue toinclease for$ ?m> bort time,.- ' . . ,i t<4 D a and then 1stahgphate should gradually d$cPeasef o,zero.piat $' - a.

"

' ' t . ?- l).

' ' , %,,,J.'f y. _ '

' ' .b>g Continue to increase, but at a slower rate. The,4tartup rate. -

. , shculd decrease to zero at the POAH.. . . ' . Sto increasing 3_dsdre,55sif6]Srd.d stagjliz p rate' ( * c.

tartij , uld4immediat%I 68#

s , - vg & , e m ~ decreas}edo,;zero;from a_q,, gattvilvaluerde,c ( d.

Begligo n . Y 75? g[geg$WyB %kfN {d.

" e l >

~ p&

  1. 5107-ANSgR:

Q , , - ) a.Y $ ? .. AiFikJMA %we {*pE- "f$1 / A b=ss&?. A Ej 1 ys a c v % . " % W BA kf[ $)d

{' f Y

  1. 51b7d COM$lE S

i Y Significantly modified <($ n , ,, order pf choicest. anI' Chan,ge 'I Ym.and distractor ,* r rv m- ~ b)%- - . Requires evaluation of criticality condition of reactor base 3%ri'MCB sifEiications (NR45).

Qw/ e j %, b.

'Indorrect since this would indicate criticality.and reactor is critical 'hsf6re thef0AH.

%A . . . T'b _L /T " _ ' ' c.

Incorrect 3ince indrease~d time to^ stabilize counts when close to ' ' ~' critical.

, ' _d.

Incorrect since SUR should not be negative.

. - . , , b ,

. - . s - ea t w y-:+ i' < -- - -,

-- . -- - _.

- --. - . - _ -. . . - - -. - - - -. -- . y) Question Number: 9 +

  1. 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 PZR.

. . The, plMt Ipo,. Elperating,k.C r% ' I' '

b

. at:100%'. 3 I*

"1 Q)/

' . \\ k,., y ' loss of the Reactor Building Instrum <

. + . , . t/ , Which ONEs(3));Ghe following resulting component failures will im' pact ~f3CS' pressure control withi'nahe first few miriutes of the loss of alr? \\/ . Zi&PORVs fsilIn%h3~%wNE c4N / ~ a.

//7 vnwa 9 g g.c4 ,% ~ %'s Wrrsh J .A w v i b.

LCV-459 and 460 LTON LINE'ISolz,laillnh closed.

< PZR sp%vamyQ'.y ;rayyalves fa%m _ USlling (*)- 5 % - m w.

%g p

%..- d. auxiliary spray valvd; PVT-c.

L j !)145?unqc ~wu. ope ed:dukt6 b61ng. failed closed, canrioi be.

t'

/ p w w?' 5;e.a b/ - n?

d.$%ZR s;.QWy:ivestfailin[;#:yyb j' E16heddand~pausil m - Q d; - 0 il

-r h%,I .; r49Na PVT.

" 5;T145)fallinf6)@ien.$ ! L 8 @kb c/h ?' A657

bb d l bkk [] . &&E5 h $$5.!$hl Y

  1. 5300k'-

, ANSWERb:h h// h I h ' f,q,q P 9 ,Q - , , v- . ,, s,.. (1.00) N' ' fcD NV '

  1. 5300

/ COMMENTS: 'tA w4 N ,, /% .> * f SignifiU~ ntly modified - Revised stem and distractors b. & c.

a . 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 open.

a.

is lacorrect since PORVs fail closed and since there are accumulators to allow limited operations.

. .

. $ . e <, -. ... -, -, - ~--

-._. -. - - --.. _ _ - _ -. _. - -- -, -- - -. - _ - . - - - - . . . , t . .

b.

Incorrect becaure this will have minimal affect on RCS pre'ssure.

[ Y. ',8 - . . -

c.

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 open.

' - , ' .i . . . . .d. Irgtrept slpyd Le7~PF-8j145 l airs plosed.

, , .yg

  • ~. Qt / j f

" . , - .. , , , , 3 J [v %d.g .~' s,, .

.. .

  • -

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- h5 - ,,Aj T uaf ^ / rGfmfl'i$YMkh;l,l'

  • n[d$i:;N,flpa r

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6, g, boy; 8 $ y$ h M I@+ S %w 7, g g.2l d d k._1 N.edd fM

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ew gp tw p;wy d a , %$&y,6 M,,6 pgfnyw';eNigh,Mvhk' yns%Mi.h e, 4p, 1 % 'h 'J id

  1. [%

hG ?.OE W.hi

f "** D VW flic

U) f i i 4f y!$sp&.,;*% e6.4. w i idf~2.> c

e g i W l u % nier4 ' N"?,~ h_ 'P'

g

n?vN { }r gQ yf Ws{4ff,h

$ y ref*hw c l ep

  • a % a, e s

sy yb, m. v w h, k w$~ f~' g6 f;s m n \\h }e\\ - v,- s vw.r m,- . . > - . . v.

..r g.

ye . . . ' ,,, - s \\ %,d p.

s c MI, kA

9,.kg ,, s s .

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n

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- . . . ..

m.

s u ,.-.-.e-..-sy -

.- .. _ - _ - _ _ _. _ -.- -- _ . - . -. .- . 4) Question Number: 10 ' '

  1. 5308 QUESTION:

POINT VALUE: 1.00

t ' The following conditions have occurred or currently exist: . All' controls are in automatic.

' - . . A..,_.

, PT. 55 PZi3 p,_,e}sure,transgntter, had previously failed and all fu ,r - actionspf OPr401.4 thaw been+taKen r 9e r - . . a~ ,/ %<r ' -

, $. '44 falls high.

. %,,g

'

i , q , f s '. . , A Y. The PZR PCS operates as designed after this-fallure.%) , ' Which (1) of the following describes the resppnseof the PZR PCR, or this - ve.s w -w.. event ssume [LQ erator actio~ndg~Wwiw,p.g .

gnb_9, y .y; w n w.

PCVWAB'o%,n%i r r;;cQ 6.w::: deerEhdind$ pens, then. closes.at1985)M' actu - I sig a.

- b* Sif W i"ibb*f I M Fu A Q@$,.M >P ( )

  1. m M.k,.48 v

%,. <. s v 4 PCVMWcE,epy' sin'g%8%%4 then. falls'n,toicloss'ati.1985 psig actual PZR lw ' b.

,. @S k[%b.

press 0j"e?8Ecrea

c. WPCV,44,5B a@nd, CM.$ Mh$N [$bk ( d.

$ @$ I . 4.4B opens,-then,, closes at 1985 :sig,T,.,etual y 2R ptqssete? ocreasing jf - . , g,s - ..

  • T q#

, M 5 h ?h7 N ' s. 3 d. N h y/A.3

} d.

actual PZR prdssd'r'el' e(cr; easing.$tfjen' f PCW4458~and2CV-44 B openy,/ L~G V 9-x;;-hYtw .. (fi 4- . #5308:g $ ANSWER: ' s, v . . ' phet - ",i <* sa. ) (1.00) - s / s\\ s

  1. 5308

' COMMENTS- % V _ f,j... , , NEW QUESTIONb

St

.. sj .c3 mc q Require.s examinee;to analyze that PT-444 opens only one PORV - a.

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, . .

, . .

- ,: .

. . a . . 4Q Question Number: 11- '

  1. 5207 QUESTION:

FOINT VALUE: 1.00 ' Given the following:

., The plant is at power.

' - . - , TI g, Service Water Syifdm"Fi(~.a, normal alig

' 3 C htO 1 1C J" j ' Of ite' power is lost to Bus 1DA. [f.,f f t ' . . . . .

. .3 -

,3 .. . . fie "A" D/G responds to the event as des'idi)'edhi h.N' - - ,

"Y

M)

.

Offsite power is now available. to Bus 1DA.

.

ain after the fo,ss,w g de_n._e7.,[b7pp,'Ei$bS$g_hdN, S ' ' ~ , (1) of the f6110 win ft bter Which . q u ~ htzi.G pf;_ power System.

+ ' g n%,m.?q. w .?c,.e n% f* y us n '

gy

ThefAfsW! Pump,$~ke,r willinpf the "A" SWP and ths,., y . 'brea "A'l a.

NT.

SWBPMillIstift oncEthTD/G fids c6iithe b i can [d b st an Mjj% I 4 e s660Iedjxu %y;iirneg%ww . , Sg %d b. ≥:;p:.4 "A 'SWJ>wyqQbq.,@;g%w..M. q i tv. g% c 4

y g; y

iC

.

(,f)\\ L ill:NOT"tr'ip;g (SWP restarts'o'nce " The urnpgea e ,.A.

, hiidjthe A',SWBPjvill start.

T$ifisjD/G tieYdiitolthe;b*uE'nedithe

t ' p$ M hf M ;$ $ M N ;I U;) N i h M f SWBPjcan befehYredio cP

aM t \\'$ c.

The~"A'fS . willin,pptbe "A" SWP and thD'A" PUnip6djtbreakdg/G,tiEN 6'nto the bus. Th J SWBP w'iliista b \\,-I,,. be securdd wh@en'5ds'@1DRisidit6ted to on D

- ovv w . . .,f[c.

v- . ge.

. ' ,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 1DA.

@~- 'Y v

  1. 52.07 ANSWER:

4i R a ...% ' c.

(f.'00) 'M Y (#5207 COMMENTS: NEW QUESTION a.

SWBP cannot be secured entil the DG breaker is opened and , , ;- .

. . w

... _ - . .. _ _ .. _ _.. . . _. ._ ... _ _ . _ .. _ - _ , . . . . .m-il.g) Output 3 of ESFLS is reset via Block Auto Start Reset.

. ... -

.

b.

Incorrect since A SWP will be tripped by Output 1 of ESFLS.

l , . . c.

Requires examinee to comparo given conditions to know8 idge of ' - - SW pump trip ano activation signals.

- . ! d,. Incorrect since the pager is< restor,ed. S. P. c..a,nnot be secured immed . . ito t u. bus.,,, (.<AI1. Jf /' /,,j.

- . Thj"'tf L I ' ~g .. , , , _' ) / < ~.,. . ,

j

(s j.g

o , . a/ s+ E , hl.

(*s\\ , , s.

. , , . ! % h ,., l. A n._(n.a._ j.Id$N^NNq).)8,)G'g $:bfm,h(N;" - b*;i.

  • ['fk?,?i

? ,

F m aw m s n.

Y 5Nh$ h J "h$b[85,% hN - 1 w . , be..e m.;(-g$$&,&e;C[ *' b$$ h ' m

  • ***

%s(}.z.$Qi

t A 1,3 c w.c l)

k W wa-sc w e m ,a t(..: s,.,a; oi..

ww +,o

h M)*%

    • p 11r4 ;-y-~f

..*),, ( f e WJs. ?? ?$9 4;.$

t Q ' . ,.,. 9 kfm.;:pl)a mpm..,,syW) Re g- . g.n p ,<, .IQ

u,.;v vv,) y - ,q s \\ p,e.

. . u d- .,, s, . . .t l', - , , $de /% . . / h '%

  • st.9*

,/ ' N'h \\- u,. y.. f - .. )

g ' si. * n, e - , ? .x <^ E*'. ,+' g o.n

hl'%f

. +

.. . m -. _,. -...,. ,.,-

_ _._._ _..._._. _ _ _ _ _ _ _. _. _ _ _ _ _ _. _. _ _.

. . - ,

t . ' ! i -

- ' ^d Question Number: 12 l -

  1. 3345 QUEGTION:

POINT VALUE: LQQ i , 4em t}$ allowing: -

, l - . ' ' Reactor trip breaker "A" falls to open when a manual safety ' + o injection. is initiged durJDg Q/G tube rupture.

.. > , ..i j f g b 2.

mt p, f% " Tri breaker 'B2 Iridicates opert,and$ rods indicate on bottom.

. . + .

' + h., V/ ' pressure is 1800 psig and decreasing,:pnd e [ ntQ,j . . . . . . . , ' ' ' " . - decreasing normally.

/

l ' - %*% , , . A

. . '*O - fg , % The decis' ion is made to leave RTB "A" closed f rd ' ' . Q oubleshootin . IkW ani!,i ' s k!d3[$$"RBSE,a,T.p.i . /. ~$h

A / f . TheiNBd tesets _p.lt1 SI 9 RAIN A(B) Swit Fe's, + s ?n$$ecMR etp .f A?G &, T' q ' < j-,, , Next. 'e:NROATC'dep es,ses $6tkRESET PHASE A TRAIN A(B) .. . %~ CNTkltl500fpushbbit{osIWpFMEjs 'i + ' . , Ob Un hese condi $ns, w $[ll t describes the st iu of 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 + /

iPhasiePXwlllNsNth;p$"@L p$ ;V "'D W m~ ig g, ,9 % a sp.

en /~fy . Both Tralrii"A" arid B' 'Sp ap'W - b.

both Train "A" and "B" Phase A ,(,,, ..will reset,% dt h - a sp,,-. . . . / ,. . .

. tf Only Train "B". Train Sl will reset, and only Train B"' hase A will

/> reset.

%= / y A.

. 'O$lv T i "B" Sl will reset; )_o_th Train "A" and "B" Phase A will j d.

ra n Te' set.

4i ' M> e ,.A... <;L v ' -

.

- #5345 ANSWER:'l kg P ' d,- - (1,00). , ,, . _

  1. 5345:

COMMENTS: . Modified by resequencing distractors.

, ,, p,; . ,

. ; ,

4 _ t h w.

> _, _ _ _ _ _ e vt 1, =--N'F M Wtt ' e3e9F m-=1=-9g 3-gl-,"v-- t4--g

  • +m--y3 y

- 1r gy+3.pq g 3--*=gv+--n---+-Tv*wv-!* -gewy ---e--s-e +----6r c-w 4wrr-'maf."w 9e-' TT-tP 'ri** y- ' y'grer y 9-mi '

__ . . _ _ _ - _. _.. _ _ _ _ . _ - _. _ -. _... _ - . . . . , > . , i - ?

%m) Requires examinee te detennint. that the corresponding train Si cannot j

be reset w/o P-4..

~ i .

4 e e a .

4

-

,W M

' } 4 4#m . . oh % en, k

  • q, / 1

,g f, + . r ~)%y',[ u t a * ,. , , , , - - ,. m . . . Q % ff '. . ',% x

. , Q~ Q, L - . . . . . , , e. *Yb Ah ' * * s+ ~+ py;.::w;;,;;. -. fe a M -l?h> l c b y, e~gW-Q'htrem. @,w.~e w &a "

' t e, n . $ ':!'bfhh.ffRa6. N,4 4 m A&j' %lgl0,(hf,:~sl$ ,

s o . . e.w.)

h,,2 g me c , w , .kI]- - J Jt 41/ ~ wu' a , r g. n;a w .,ea a , g3, Pa r e.A sq . , . -g~ q $ r $ f f $'?)A F),5%Hk f$yde h @,,w%9lh

(? & %h04$ % %f:/( r ~ ~% V ' EG2? ,N k9% M@!/ljw$YfO yO . gg ,- v.. . . . . s .,,f.e.

- . s/yl<. . . . .. . . .

  • l r

Qv)< / / 'Q4 . N ktf s }h 4 >% q 4.,=,t,f" m,~*. ., 4; g, h I u'

, ) A o-

        • ,

.x 9 g5' p,f hoh

.

, (

  • 1

17 . S

4 o ,.... <,.,.--,~....,,_g .,. ., - ,,.,yc

< , . , , , - . ' . M.- Question Number: 13

'

  1. 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(. 'CBS Iraplemented DOE 1.D and"theplROATC & ARO beg . - - e " . . <fo pgbrr# ihcir immediate Opelsiof. A6 ions.

' ' '* ' .J - - , ,, ) %48$ , - .\\ , ring the event, the NROATC reports that ong PZR PORV . . . , , . . opened and that RCG pressure dropped to 1825 ' . Espd the,openh0RV.if ' 6" ' . The NROATC then . ' v W:% 44%yun sg.

act$nYkaYh ee?

[/f.

NkNSErp$p&N W{f{fNrdo this poln N era

Plant conditions ar,einEw,as foilowssy;f" (*] khb} y.m & ' ' . (yNp(I@jdgngh$01sig,Ih-Y Chsf flowTriIli.12fii'55 F . w - n Qpm (k - fi - ~3.. ) @! @ghy,, . Chstgingpressurea,psQangine 6.%passuragie Ing -

s2735 Rsig

' , gCi'levelIs 3$ r[h statile. d

. e plant co'n,,lespor se' h o}f foil ing describes tus Giv equired crew .iW andi . . NOT initla't d an

NOThequired. The crew shouldTansition to y'[p.

- a 4- " 'EOP 1.1 to stabiliis hie" plant.

(./. - - . y~ A.. Automatically initiated but is NOT required. The c(re\\ r ~ - w should s manually initiate Si and continue in EOP-1.0 f!ntillSI can be N ]erq11nated.

, Automatiddlly initiated and is rejbirerf. Th'e crew should manually ' c.

initiate Sl'a'nd coritinu(in EOP-1:0.

d.

NOT initiated but is required. The crew should manually initiate Si and continue in EOP 1.0..

  1. 5321-ANSWER:

.. g, , - .

.

. - ti.

. . . . . O' '..a.. d.

(1.00) ,.

  1. 5321 COMMENTS:

. . . . . NEW QUESTION

- ' d.

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 ' au 6ntatically%w te; nd.. app yl< loaf Sten 5 of EOP-1.0.

ptua e ' g - t,e j,F .. %*p i - %y , - , . . , %3 . . . , m\\ . n4;s - % y n . , E {r,KC*"} . . ' %sd ' 4.,

. p.

. n&.uh $u $m$ a.,,,.. s,. ~,e f,) b 15A? b_.

,f . ~j.++.,, yg k - %. g.. - + p g.

73 ~- g% ,, F.g ,.y va

n%j Qty 't '* h(a,% gWl' ?Ir,1(r.+ 'y ,.,sg,,4.

.

. s, :.

- i; W g Gkhd$ h"%7; -[.)n[.,I DI (*), f"%,. ' y ; /qw-m g-2 a;. n.y,.,.,,.,,,; ~1 m,., t e .- ue ,,,9 r, y. y;;. qA .

  • ^

,% y. a.a.y. s.,, r% W l,.1+ Ft . - v/sej,..wp %? h ; s;. L"' r Ph y %,,g -s ;, >@p,.pp't 3utp..:' p ;., ;ff,5 ' f, Wa , . --

n.

% , ww=1, - A.y;+a 1 % m,p

  • .0 ; g.

I d (4 ylvf,. N .

  • e W :+ MF ~. e w

'1

V fk ' .t h;Uv d!N.;k k '4 'M. -, '. ~. '.r 'r4J@),9+ d (, Q*g'f; /.?g5 M) $ d.*,js % g,4j.;y ' ?.} ** [g.,t /,.g "g/ u.. pl yMk ,4", , %) . ' m"? * g ,# y ,%

  1. '~d)o v.

, _ n .m .. a ' r+ , ~' , , L/.37Y. m.

n"h - {

  • e-

'" ., 7, 7 L' y mwd lk,,.p.h' =' / ', w: \\@'w/*W O v W g.. . i.

- t r">

  • %.,,,

.a q -~ y,iT.

t,. p .,f p 3 mJ @'N .i.cwO/My/Q?14f f,g{,;$g;;w. - Up:p,$ry'*: f.

' ov ' tv

f . 8W df Q M '5

6 %.,. W wpw . j

- u s 4 x-.. w %' g,C ;F ,e%. px~wo% U('Tl,l\\\\RM. O!~u LQ ' (\\ .- /.,, - _.

w cs*s

.a<.*. br= w,t j%,,/g~-nn m.: -,.,. . w k [(' (s k,.e ~ g7 . 4,. g% ~. . v.

. < s,, s.w e (, A a /1 s%e.

J . % .Q, %m .

%d - / , *, s.s (% ,..: 4;. , ., , ~3.- , p.O - ^.* ' .N f " 'Na s3 y

f - k '.

19 . .

m ww ,y.-y y yah-- - w -

_ --. , , l - . . . . . ,

.$~

Question Number: 14 " f ' . ,

  1. 5209 QUESTION:-.'

POINT VALUE: 1 00 ! ' 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 Ty.,bingTr' &}s N;{ '

.-% , ,j a.

, .,,'d, fy/ .w , , - .' b.

MSIV Clos re ' - - i . " nt lied Blowdown of the MSRs . ,

e*d.

Closure of extraction non-return valves.

,- . ... - k Q A Q3W--- % mag $e % i ' .

h gg " O'%f - - . % egif M p dM9WW4 f . q' ANSWER:@gagg h r[e g h st s efdffN

i hkEhN[ ' (*] P"'* ' s ,

  1. 5209 jppg pg@

Q ! . ., . k) h h % "- CO MENTS7 th /,i MS L{ 'EWStr$.#ri -$%if tEMA@.F@#

  1. 5209)-

b_\\' NEW QUsSTION**"/4 'd % Requires'tfie e(xarp nee $;\\'idT kY ' % f7 , V. a.. to.detsr&11ne that, if turbine did' mot trip, - Yp[. ' the RCS could co6f 'd6#n excessively and this, in tur'p[ 4-- '., - c6uld ' impact SDM. Also requires application of knowledpe t / g p9 trip occurs oil a reactor trip.

yh.f ,' / Rm . b.

.,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

, 7 y

. , . ^l - Controlled blowdow;n of the MSRs is designed to prevent turbine c.

overspeed.

, d.

Auto closure of extraction non-return valves is designed to , prevent water induction into the turbine.

.O,..

, , i 20-l

. , .. , j p. * ]

-- -- -- . . . .m "'e) Question Number: 15 '

  1. 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 start.

. ynpd m%: %~.,r% ; . ' .o 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 The IB Operator reports to the Control Roo , . A than 50 RPM and slowing down.

(. . To stag l.AfDG, the IB; Operator mustloca)l93,@hpro Tk ~.. - - .- - . r/ r e ifj W,if%.Ms.

~.,rx U ? A e y uw a -- {,' a.

Override the' Governor. /,?c",id # ' 'f Me.GM MP i [, a 'C' (R Over' ids 16ellain AII5ta'rtNalv6.? M b T b.

r .l)J c. dg, lace 1,h'e;LOCA6 REMOTE /,MAINT, Sw %dN4;w,W.. T "

",~ !;It th), Qb momentarily %$ press the 2e EMERG;S. TART.pushbutton k { f E (&.c ' .lib-Q &( %QQg) the GEN RELAYS RESET andiffid EXCITER RESET ^ %? Depress ' A d.

  1. M fpiisiibillionNtheh'0e~proks'ihe ENdlSE' SHUT DOWN RESET

t.- pUiESUit

, ,

  1. 5012b

+v!s.-hw T / \\ f, ANSWER: t - - w- - - q,)e.

- -. - 4,,, . (1.00) /T, ' / b,) &J f

  1. 5012 COMMENTS:

'@ u, s - ,, ,. Significahtly modified. Changed conditions of stem and reformatted.

. Changed one distractor and esequended choices.

. l, , > < ,.y a.

Governor cannot be adjusted until diesel tied to the bus, ' b.

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 1.

. . . . . c. and d.

Incorrect. Neither' pushbutton will correct failure of Low ' ' Speed Relay which prevents air from rolling the diesel.

- + . -

  • %14ar-e i

, , 'pr1 ia;r L % . , , } n s eP;g.

s4 r t*Lu ' f f-a % % k

  • de

/

\\gv % /.

.. . . - qv . %,.agg,,. . . , - , , . . .s ,.

,D , y

. y, % . . . - g;. m.. w, %u g@R m. T 7 x.,3 4) . . V,gc. i . m i e,sv hp!f.w,g f f g ;ANLw- . L,/f w w za m,3., v-, ,, g r.- , -. - pm,&g ,e,~ . m ' e.

5-ffe,c_.,C*.n%.$ 5k b, (' l Y$ <~, m. m , %y*, (win p. d , r . .~ e %L . Cs o.gue 6 p% / ,w c & 147q:r sw) g%,[yq&..a ~ Q ? t"%<%s>ry Wh.5+ weg, %1Qj;;:;f;;yyn %~t * ; r 4

e yw /

  • m y

f m - %g b a X ep?h .. u t +.:05 eMy%h:GA%3;fG.$ Gge:D:S /qg') %s',- } n&.;a;% , >

.

a y % W ? l:' 3 MP ' hw vg% e 9 pne /py^?. WM%wW W56t i s n$

~~ " * hh

D* s ;- ~~a .r.#e.r @w..* a# w.v.N y ,? 1 w.w - -a n m sr kp2g#s . ., A ~ 4 + PM<.,;. r pg>y%s.M.* %,

wl

. d \\\\ p p** s 4 f m p.~ g%, fj/ ~ m:w e-

. (s $ll 04\\\\Ig , W*"l.

.

i r,,,- y% ///a ..:vv, s a w LpJ.

- < /;,. v y, '.[f.

?h , .

,7.

y$%, /

. / .e, , \\, . w4 p.4 , s,. h

N n r.dw ,

4 b b W L.,* x s, > . %_ . ~, w.- <*. ,=' g* .g 5% .

. ' $ . _ - . - _,.. .. _, ,,.-.. -. -. -.... - -. - - - - - -, , ' ' { - - . , , ! < . . l O+i Question Number: 16 ' ' 0.

l , , '

  1. 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 increase.

! . .. ANUr6Ine loadbeing a ad[ R TC dei:ldes to allow rod - -m$ti,opo c*ompensate for changes I'- i ' '

,. , %,.8 9 , ) fore rod ' motion, the following Bank C rod poptions exi ,

' - . - < , ' A e

, %4

l - DRPl: 186 steps .. ,, ' - N - - - -f[$iin?h(SW^$%uhNe

' ' Gg f . . l Ad'/ kIIf ,dhlj " s Group'2: Step Counter: 21851skepGt

- klMI b AfteritH' loa $$f kd }llowing:khh$$'nk D tod positio ' 'Q $$@&increaserthefo e d Ba l . A.2 h(g@g.{h

  • RPlb192ls#spsjA)$h,18 Tj
  1. umdWW@J (".1

.#) 'D t y Eh / %h { l , M.

@ vfy; gteGroup%gQf#'fqs;tistp St Coun sKf - C a ww[vnu51 h$893fe Glot/ 5p aw m.

, - . Based'on,these indications ONLY,@h DN of the following explainstw@t occurr'e,tfin,the Rod Control ahd Ro'd', [sjtioj.1 ibiIion Systems? %

, . / x y ?. v.

. , . ' , f4). should have actuated. Rods actually rpoved and a "CMPTR RO / @w#

. / pt.

' . i ' b.

Edds actually moved and no annunciator-should have actuated.

'V" $4 ., , , - c.

Rods did?NOT move and a "CMPTR ROD DEV" annunciator should hTis actuated [ Y , d.

- Rods did NOT move and no annunciator should have actuated.

, . .

  1. 5233 ANSWER:

, b.

(1.00) ,, , - .

2 . . - . * _ 'p~., u u -., -,v.g,,-,,,,-m,--,w..~,-- w ,L,.,~n.,- ,--,+-www- .g w -m,sm ,.,,,v>ym,,n e

,w,., a..w,,-~ , ,-:-e , - - -,,,

. -_ _ _ _ - _ _ _ . - .- . . . . .

- , '9)

  1. 5233:

COMMENTS:

... "CMPTR RbD DEV' annunciator doesn't actuate until DRPI a.

~ deviates from demand by > 12 steps.

. - . . . . . . b.

. Requires examinee to ap' ly knowledge that DRPI is based on - p . scrising actual rod position, and the step counters are only r demand. Also,,re. quireppplic,,ation.of knowledge of alarm . . . 4'rJ set.polnis. gd { tJj ~j. /3t c s - j K/k* Te-"014K.02 - RPIS Indepen ent.of de, mand

p ~ . .. " ' . - ' "

%g . u /, . . g t" .(#%

. . ' Nm,%g_ m M.Es@W_'ysd h) 9~ ,

, - nA y ,4r L a. v rQ b;t.

- q,, j

  • Q fj";; W,[g

'm?g B Lll:k

j%r %m&. g*end$"; g,(q/[l [[ SINH,n r; tu [ i (*%.s <; e n.r e / g?pg &c,.o,y gf* *. t ' g; :,3,4%w ~:r

cW,1"rc #p ,% 6.

em + g e,. m , ~ s $'J,17_bh.! t k.?l(kln?& ;%f s,[[,.;y v,3 2 4,ga f, d * ' Ul. ? [,.h h. + g %*st i i' ci We ;,*jC-a.h(M,f;"}$h}lA h5 fM ( y* '_

" cr 4_ N}[9. nm.e..[Qq.

() 4rw$[as[$p.E " '- e.f,s/ m.

_s ts.

,, t 4, 'bM@$g+un.Q, 4/,f e., .#n y % h b f ? fM j a.nE# of.k' Da

Its) g ~9.'3n $da h,[f - i R - Nai m k N[Q#hy *"" mja$h Nj \\N x m . w,v v,.Gs a t.o,jg%g\\ y < - n-y - p ,. - . - ,~, /,s . . v.

y s.

. . .. ~*fr j**T "t y!) %

. % \\d ,,_ e qn d %.h % f.

Q,'k >% C* %

9/j i,,, V .. k.,

.,.4 > ,. t.

. ' %[ ^ . + .

. . .

... n , n ,.... - - - %e., , _ _ . - -.

_ _ _ _ . _ _ _ ._.

-- - -- - . . -.,, t

Question Number: 17 '

  1. 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..d.

' ., ,,. . u ,4 wi . - The rl 1d lyottage con Itfo %has blested.

z., .o .s ,J~g}d.une.

  • ] (.,)/

/ - - ' . ' , , je# " Reactor Operator has been directe jo (upply Bus 1DA

'

A

l (. oi XTF-31.

t,,, , y . j% ,

No pro.ctive functions have actuated or "A" D/G - s . huma,t ARd'e~o SbPis.30E.a."T"[dEt{siid)"$sYIlta e1En ' ' . f . ,A/ /

  1. M U

^ yy ; . , a g.ga , 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 ),? %'

qs"'Ihla.j.f,gggjy$gg;; RT; place the(*DG A % )

I " 'a MomeY)t a.,h. 9,sC SsDSWif cb t ' ST Swi 6 to)GT h . " i 6 [@WC /pM'libutton, m B , N the'rFciosed el.1D/G breaker [ Q g "%d

p c'N b. \\! Depress the,EME iS RT>OVRRIDEFys hM Splac'e't fEST it5h5 ' RTdM'ifthe DG A SYND SEL c J ' \\ '), SWitEh! N'ORifiheWc1 y {\\$\\Q.) (/$' fb'reaker. (5'$' h5 D/G 'f Momentah y, a,ce' t REST pitch to START; place'the DG A ", - &- /. c.

' SYNC SEL/5 witch'tifEfAERG; f n close the D/G brI6$k$r.

' - . /'i j (:. Depres,s the EldERG START OVRRIDE Pushbutton 'd .. place /he TEST Switch to START: ripce the DG A' SYNC SEL 'SWi .. ^#jch to EMERG; then close the D/G breaker.\\ , _ V.i

  1. 5324 ANSWER:'!.,

' ' .. b.* e., . ;4;. . a , - pq s - d.

(1.00) '#5324 COMMENTS: Sig ficantly modified from 568. Changed stem and all 4 distractors.

( Tch% {QMr hC. Qu).Sb ' Mav iC ecl-v h 25 kc. Jcw kL^fb \\ o u p r u u o p t %.I tn d 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 - > l D U NQ WM ' Questlon Number: 17 P# I'0'l~SS'IYWII

  1. 5324 OUESTION& '

f4" , INT VALUE: igg ' Given the-following: '

. . , - - , i . Bus 1DA experienced an undervoltage, and the D/G automatically - >+

.

.

. .- started a. nd assumed load.

' .. , m y, < tty)grIufe oYfage nht[oo h)sicleared.

' ! ' -

  1. y

>uf - - -

..,. . . . . ' .

'

I . g A" Reactor Operator has been directed to supply Bus 1DA h.} 'om XTF-31.

"7 ), y ' . , - - . . e .,h.

No protective functions have actuated for "A" D/G,.. . - , idtTsita e"d$d frequ j IAW dme,the ARDW~;a,dJ[I.(;g[ jib + 4. / , S (P 506: f E8 A '

  • %

fpm - - aa Whl5 i dNE (1) of the fol_i - "@WW6?fyI ' .,, actionslKs6eMary to synchroniz~eh ' . acr6(5nd close the "A" \\' & Bus 1DW " h.$&$ tp('N . ' ',' M a.h(I5VNC5^fMome(tsii lSEdtieiTESTiSwitch to'S R.T; d fhfibMbF0Ai$Foidse dYd2g#GA T h b. YI$MG Ndk $ II E, NSY <f " $*" gDep,rps,theJMERGjS,TpRLOVRRig$$pje~pp shbutton, morgestarily f]

4placedhefESTsswitch to STARTtplage r v SWEfMN'DRfi 18$ths.QMNiedk'eC % . $ \\'YN QUEAak O h) ' ^ Momentady p[ ice . EST Siiltdh to START; plage [/ja! l ' SYNC SEL Switch fo'EMERG; then close the G/8%6lJi QG A . c.. - , , &ker.

v- - .-

  • h'Q Depress the EMERG START OVRRIDE Pushbutton&W

. dbf ,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 ,

  1. 5324 ANSWERrh (

Y d, (1.0) b ~ b ' #5324 COMMENTS-Significantly modified from 568. Changed stem and all 4 distractors.

.

. .

' . . ,, t- , ,-, ,r--e , e,,-r-e v ,,,,-~,,,,-o.,- , ,..,-w..n ,wr-wnn, - -, -, - - - - - - - - ,--,w----,,,---s.n,c.

n ., -,v.

---m---.-,,,-m,n m <- -

- _ _ . _. _ _ - _ -_ .. -- . - _.. _, __ . ! . . mj) d.

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 reinserted.

. . . . . NOTE: Included "No protective functions have actuated for . ' 'A' D/G" to prevent having to include " Depress GEN - ppusQbuttontis,d, T Pushbutton"in choices. T REL AYS.,RESE . . ypressed in SOP 300, Section V.A.

. i, j

  • \\ \\e'flodhe eJeni 6 sig, palls' generated spuriously.that

' ' - u . ,. ., would trip D/G bredier wfie'n in Test mode.. ',, ' - s- % ' 5 /, ~%,.Jh . .

rg s . k,/

. . , c-w<4M fyh,"9MLdd3i%,,' ',.'s y,a"*~ .- x .. . , f t A ir ' 'm Qr y;3@.9% ya gr:~ c ~-a. g; ,.s g m.u glf$%f. haQ,(F) y;;;;;~Wf

1% ,s p , E'me' f," n n..p$ ' ;,5 i eM 'P* *.'.h.u# V L # tV %,i??[GT(

g %Q , /

  • y j

p t,, .. Nm, A wave,&/}?[,Qff(,jfh(~l.ll ( d{ !S*I e..o i ma up e x,m.

.~ w, m {'d$ f*f%

  • ib,k.N b,

.

  • $!,i.? fk$ Q&;&f $

U) \\;p%p L;Q?.if,a'g 'Ml.9;Q ;& hllel l'y * '

  • m'c

~ 1,;f C ) " rf . g. : y&.fg .p6, s a-w

w a i u. m f t. Qg.Q i - . s.t e.

w 'r {y%.N a s ~ ,, u ( f U r

  • w *

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      • +a.4, pc' kNf',

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~,-

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A

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    • (

- ? os,. k j **s.

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r gg i e . . ge* y.

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  • -

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4

i ., -.. - -.. , .n -

_._.. _.._ _ _.. - , , , . . , . j , , Q Question Number: 18 !

' - - ,

. '

  1. 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 Q.

, Bus 10A 5kBXiLockout Relay ' *\\. - r I-

a.

. (p)niGenerator Lockout Relay (86)(jf Q

, .. . .- . l -- T b.

' Dj6 (gffg '

. ' rss , , ,

Diesel Generator Overcurrent, Relay (51v)

. G d.

' ss of Diesel Geneg sgal . .

  1. 50 f,6'.,,/./ - - ANSWE hr

'~5rdle@n

w, s em a 4s4g P affWi. ' ' ' t n COWENTSl $f$pg[4pyggj $ T !! i

  1. 5p6.,

Q AY,) @ , , n'ti mod $bbkd$stenNN strsNtoTa.

F Sig W@%%h.ds %T.

{!Mir9 g ' ',-

p

j . l,- ' a.

IN 4 correct 51BXl oko sg.

w . , s ss - ~ r c., lay.WiPi() t trip the D.G. Igea,ker if .R.e - thE6idi(nisIdfirijripi"%^Aidehch.ino'de.

[) . (Vjjji \\& f/$ ' %r ' , b.. , Requires N, amIneg o,,terminEtilat D/G is in emergpcy start [<f * - , . which disables non essential trips. One of the trip signals ,- - . - e - ' k/ _ available in emergency mode.

f ' N/ ! Incorrect since this signal does not feed directly\\1o'the D/G o.

'pthaker trip circult.

. ~Y" '.i . . , d._ IncorrecCsince this will only trip D/G brea er in test start.- ! ,7;m, y q . , , > - b g ? . ,e .

. q e 49' t J _

. - . -.- - t . - . . . !I - , f !

$ Question Number: 19 ' . , I t

  1. 5326 QUESTION:

POINT VALUE: 1.00 . ! ' . ,

The following plant conditions exist: } ' l '

The plant was initially at,100% power.

!

- A Q'BA iOCA fiQcauhd DByTrain Sl actuation only.

~ '

- g.",. \\,\\,,/( A" Tfain $1'his falleb td Actuate;)f ff ' , I . e .

m

- - y . , , Q(B) ESFLS has failed to operate.

\\gjg '

- y

& ("A" ESFLS has operated as designed.)

  1. Af"

, An XTF-4' Lockout has actuated with the DG reen(e ' h-i g the .> ' ' i

. . .,/ * Pnonto)hiev@eEM$[[$Efff d@$ I i the RBCUs werel.n arnormal, at poWdr lineup.

RB pressu$m, T';/, W,ogg%2@ og !% mI$ PUS 0dkr k.

f'

re;is:25 pgg yf3 f) - - ,g NNM s h rN ' W S B b A #{ft.N A d d;7.' @ -@ L1 - - ' tion, <

  • n;0 With NO operato hi6h:ONE31) 6fi$Efoll6Wirig' hscribes the operatl.5$

~ c

sys'tehd inat ardi DTOALO(MitOVIDING Cd60NG td"thefR'eIactor BuildingQB)? ? wtg g g g g g;pe gg'f q= r 'e gg"B" RB; Spray Pumps deliveringp/2500 gpm flo FA}apa ch' to a.

ND7^kw )!RBCUs;3, the RB<and,;MO _ running.in SLOW.

% e'h . 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

- . running in FAST.

g*\\- 7- - - - 'l/. tQ "A" and "B" REi Spray Pumps delivering d' 2500 g("m flo p

the RB, and ONE (1) RBCU running in SLOW'hnd+TWO (2) 'RsCUs running in FAST; '* T' $vk . s , , d.

ONE (1)lflB. Spray.Purnp delivering a 2500 gpm flow to the RB and ONE (1) RBCU, running in SLOW speed.

, .#5326 ANSWER: - d.

(1.00) -

  1. 5326 COMMENTS:

. ,

p

.

.

e g.. 4c- -, , <.,,v-. ,e e v.e-, , ~. -, ..n.w.---,--na ,,+,-,-,-,,r- -s,,,=.-, , <, - se-., wn ~ - ~ ~ ~ - - ~ - - + -

. - -.-- . . . . -. - . .. . . . . . . . ) NEW QUESTION (9/18/97) ' d.

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' e "B" Train without a slow speed RBCU. (Fast speed RBCUs , - v on "B" Train that wergj'unni prior to the event will continue to + . ' rtu3,witttno?qooiIrig flow /as' dustrial. Cooling Water is secured.)

The, XIF-4 fod.o6t With D'GJdene'rg'izinnolaffe'ct'6I f ! u

' 'as expected.

- - - tv

  • ,A

' s ,4 . .. -

. N <%.4 % %. ( % o ' ? x J, . - . . . - C_fg, m gs@ m$, f! ' _(f ' qg%shh,We,1 Ni @ . i-Q g a %m ! p / 9 4 7 5 % q wya . ,T $$ %. - esAww nmp \\us.t . Ig.

. %gwte u . ,

v. ;. y egh %(? )pe$$c. plnuq.;q l 8,Q v$lf , s Qy@,,0 L$ l O ([ e[ W

Gli;}r2. J ;% rq-7 ra ww&e , o , , /,t W > p.- h' e ~. "Q

c;

  • %

"'0;$%9f(AQ,T',fn'knGd}nff ;% c ~~dt c.

if .res s Q? ,. O , a w: . - "'

  1. s b

noa a - ' N- '" ), p.,

  1. '

) t , , <. ./. ~, . o e

p= " .~ 9h p

y' g,$ .~h,'. , Y.

p.e ., % r,, 4 1.

' ' lt* h, V ' ", ' ' ' '

  • < b;,

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e ,e

29

4

4

k m+ - - v-

e O) Question Number: 20 ' ~

  1. 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 10.

alhreact9ri[TsiniEiEllyoat12 Th - 15% power with

iftitial chnditio'nd ofi'GDP-4, complete.

t c '*,, - -s . . .*8 e . \\(\\s*TheiMain Turbine has NOT be% d/ent: rolled to 1800 rpm.

sk

e - -

^.4 %. e 9 Trips associated with Permissive P'-JU'have been ' < -h.

blocked.

\\

  • /";i (

[7 A,%circuitcardfailurecausesalosoof#$4.'

d5 V,& dipw5,?%pw ~h. ~.p s.~ s <7" A.

Assuminct no operator +actio.n ~'ciho:ose'the statement below.w/. , r w.

. na, hich p,nsthe plant: .Al wf-describes the ef fectc o Thelrea.ctortw11L trip,fyom_, Oc,,, (;%) n - +. yQ2"g;,, f t%-.'t iL,, . p [*%m f0 TAT.

a.

w,a - ew c. r % -a

W

  • 'o

...s f r ' < J.. p.=2, k,,y b.

_ : Nw:etpoint';Oillotrip'; fromiNIS PR High Flu 1The Yeactor w , C.g I d! 6S vi, Ag-W;;%9 2 u6 V Q^# Ga p, - ~ g- ,A,q s e a.: sq f t, : e a . c.m e : y c. M RCS,. temperature'w;p.n x,l'llfincrease,untill auxi] iary's~' ~ y st.eiamiloa' s.idnd h di~ lit 1osses[6puhl RCP heat.2

d e w&;h /?0llp{$W nf.&^' c[** ?w h .m.m.

.m a q\\ \\ d.

RC& temperaturg.cwil: Nincrease' until steame/7 ' \\M generator ssf6'tiies?,r\\ I ( Q;PWRRELIEFSopen. l"[ _ & &! 'f *' " - /r V.>. "

~..

  1. 5325. /j'N4SWER:

ph,'N ' /) N(u g di (1. 0 0) %'h . v! \\ ,3 ',i

  1. 5325 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 trip.

a.

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 transient.

.

.

_.. _ - . . , . . . . . , 4. '3 b.

Incorrect.

Power defect will balance Tavg

P increase before power range trip, d.

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 RCS.

Heatup - adds positive reactivity (due to +MTC) until

- balanced by. power. defect.

PZR level slowly

' ' increasing.itrya sgptom [ g~f" >,f Tavg increasing.

+ , % o, " %

/ /f

. ' . " Vi ~ - . . .) s/ . . . s,i . . . . . %, g?. . . . . '

. -.. g r,e v

. . . @ O ' ' - . . . O ' A ess e s %ap# % ' < f// WWW$mz3 .s-:hM t . a 2'q,y)hi? hf.c,} . 'NU%e%$,$p (" )- - . " , hQ

r .t c 'h:agW ' sp w 4}.2 % e# t- , %, .a % Q Y9 W

  • %: jh %mllf&Ullar;lA.iN5&

e), k Zh n. o,, j~~n.

A ' ' (n gn asan m v

-- ywr e n wy a "m., ,a n n'i G GWW @s w a,J J _% w f.

s'dDy.jk,3 [[w%'(u3 .

a dp'^*p"' id,b

'

' i o . 'j* XJ$

i

y 'f-i [ I $ 'gM ~ A + bd W H hl a y g. * <m '

  • aa. 9

. <3 a - .ge LVj N ep.~3*n w WAND {,ghrw u . \\ % . Nh w._, h.Y g.

.h. w.

\\,,e \\ - m.

. p.

. . . j[f g%, t . .. V % W ' k .F / 'm . 'bd

y s . ? b-ft ! V ~v% i s ., ..., , t..,

!~4' 'f'y Rl s z j .

>g r

. I . . .

. . r

.., _ _ _. _ _ -. _ . _. -. _, _. - _ _ . _, - . _ -,. -...,.. . _

.' .m . %l c) Question Number: 21

  1. 5214 QUESTION:

POINT VALUE: 1.00 The foll.owing conditions have occurred or currently exist The plant was initially at 100% power.

e e A malfunction in the MFP Master Controller resulted,inp(a)resy'i fn ftor" trip on lo-Jo S/G 1evel.

4' p._ , t e a: Subsdq(eit'TailuIed lii* tie' ;5F,P's-required the crew - ~

. 'fof' implement EOP-15.0, Respons6 to Loss of ,Nke,c6ndaryHeatSink.

V7g . , , %,g ( /5 , 4 ;9 A high-high sump level exists in ONE l(T[) q 5-Intermediate Building sump, g y h*.1e '4FAS/G has beenrdeterm'inEd5to be!the only\\ , ,/* ~ .v ' INTACT - fl,d CWA s /y v i - m.,, E.3ds!hR~,*"" #y ;4 - / e

,e. '

- z%. an, .., .. o o .. Af to'r,'cc the key switch [es) ifo1,doesEOP-iSIO$dhe s'ecuring thdERCPa dwh ct the operators to pla 0XVG-01611A$(FWIV) in BYPASSh

E 'i.

3:MZ'c~:-y % *'

' " rN This : willvblock', f eedw'ater. isolation signals"(SI, a.

td(P-14hanePj4(w[thflof,TavgP,(allowingafeedj n ["~~' 'Ny-q supplyJ.via(thelFeed.iRegulating, Bypass Valve 7 V/ ' V'.s:(FRBV).k FJ' :y$[Np NIrisokI[y4$nsig

AA M ^ 'q!&J ( uH.a p., . c.;hinfdillbkiickfee ,c m -. .e b.

t h) . IPf.147,and?P 4%i'th/lo}Tavg)$611owing a feedh

supply,viaithe'iMalnge'ed.jRegulating Valve j FRV). 'l},iL ' - [ , g.tll3. %,,.f p . This will bl6ck('bkhYido'lation signals (S1 PL14, c.

- , (,,i. .P-4 withilo TaQg)1'and the~ existing isola' tion ~ signalfromth'ehigh-highIBsumplevel-[(allowing

  • " "

v- - , . ' /,' a feed supply via the FRBV.

(*% '

/

.- ) < > 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 h-high IB sump level, allowing J a'! feed,s.upply via the FRV.

~;." 3,.

. -

  1. 5214 ANSWER: i

,.F ^.~ a.

(1. 0 0)

  1. 5214 COMMENTS:

NEW QUESTION

. . .

! - , . . .

$) a.

Requires examinee to comprehend reason for BiPASS

and relate to the subsequent flowpath established "- in the EOP.

. ! . ' b.

' Incorrect since the FRVs do not get bypassed bp . , ' key interlocks.

- .

c.

Incorrect.

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 ' - s1@ngle,J~the'coid61dehrd,'lYOp/ isj2/3 IB sutops.

The swf tch"doePNO'T rerdo%' 'On Fe (1) spmp's - - . . . Ts61Atfon signal.

'%

- . ,, )* %,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 FWIVs.

' ? L ! ~ s. n%gM, @,(- jefWM % ' khs% ea. d . ' m gg ep} gg.WW , . A<f%- / arky p.wk.w,ty&2 ( <) w " k M cd ~ T:y,;;s v.

tp.e$,$s,,0$.n. n. M9fd,p uh?2.M. w$:} @;,,;- (-._) ex h., fs > -

,.r a

v%pk w, w.}Ijl.(fh5f, s u i. ' $' { O.

{2 I

n c dyr csn s . Myw

i ! i n.
  1. 7 9^

> O.

Y Me-Si@e v a,%)3F A Mmzp':phjw% gay Q..rq a s$/ p

gs Cr, . > '. y/,. s g - . - . . s s.

.. . f p% t ., M e p %d N i

s

%, -. .- t 4_ y

      • %

<f, :s.

  • h,4

': $ p ..e F,y

  • T,{, g*y*

'*"p,'

  • M

- . i ? s t i

.

9 h--. .wy-ye-* -c me-, nr.

.-%- -ws- .+ -.- , s,,.~ ,, .,n

i ,,y) Question Number

  1. 5309 QUESTION:'

POINT VALUE: L.Q.Q.

' Given the following conditions: ' The plant was initially at 100% power.

s , All systenis were in automatic.

,. 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 ' ' " ' b ! T /.,, - f~5 1,, . I&c.haA'pdetermined that it will taEe.ab8ut 8 ho'urs to < +

i fix.%)ie problem.

7,A ' , Y .as . t p.s WhichONEQ1) of the, following is the' latest timeby,,Qh,ichthe associated bistables must be tripped? ,#\\ ' wWm.h@, ...g %J Vj' 1500 W :.s 3 'in gC g. # w. e.., & F g.;.; f,. a

- s, ,,. r. g ,e e.... [aA

Q eML fW

,,4,,, s,t,f - e g/~, V:n,s, ...,, '... - s ,.z .- : :- s .g g(.

Qg, e

,, & b,. 1800 - W c, M tr, y.<u. u w/.,2 !., z :c-~. ~ ;. ~ - s 7

p 13P.%. s,.'?j 'O 'Yh. u.!_ j,s.,;7;.o..,h, Q () .a ,%g,c.

,.. 2000 4- . , . % -.g: p.rq... >j< r,,s.c;..C, ;i, 5, ,..e m

- .. { $ .%' P"d. 2200,5 & lki M: * C5.A?' R$.: %# - '- r() Q601 ~ W~ Rih.;., Qi . Q M QO'lT 997,%.>;lm,.D,@9 (m A

  1. Sh09

' Uf251/SWERI Mw~[: Q

~

ef g, Q'1c/M6,.4N d, P h. }g p[.-a..sM#w ~.h p y;p%g f V.<' 1. Op)k. r g - ~. . r, g p.,. g ~ - - ,/,,;g e g* %,,,,.. h>%

/

c.

. p t... f, . l/N.

  1. 53 9\\

COMMENTSh.ed $ 'i * % d p M % h Significantlpi modified,,\\{'&,.. .f ("p MQ ,/64&? ' * ,~ ' ,\\\\ Changed stem and reformatted.

g,,- ' \\/ Reformatted choicesjandfreplaced distractors (a/and d.

.e # ,, - ,. . W .6 f %

  • f,sr f%,

s $d s#% k N / ) % b/ / N / '2,.%g, s bd N (, 1.

p.%a- ,*(- - - 'N

    • g ma%

ew ! f'

,, .

. - '

s.,\\

~ .

. .

. . m]~ Question Number: 23 ,

  1. 5328 QUESTION:

POINT VALUE: I,00 Given the following: -

A reactor trip without SI has occurred.

.

After successfully performing their Immediate OperatorActions{'ere'w&ORANGEpathonSUBCRITICALITY an isonotedlandr6he, tr'shsitions t'o the proper p'ro. cedure'.M '

  • A = 5..'s J j

.i . y.e ,.e s p 'v,.In istigation into the loss of9.subc.riticality , -

g%-- ab .

  • .

y % reveals:

  • c

,% / pu ( The MSIVs are open.

Q - , b r t,/ D.k"A" Re. actor.rMakeupt attfr p, ump is run,ning.

, "',,) W . - m.,a - -,. ..x s M ;'$w&uisd.O.ifdi'"~g..r*'d Ps, y +/ o [. (* *7-k:1f%XVDD8430) BORIC ACID BLENDE.R INLET ,J t [. / NlVALVMf is CLO3ED. 7 * 'g w & 1- '

"

,Wkh iXVD08454',fQ* ) "* >% ,i % ? laVALVE2 is(CLOSED n i"' ,' CHEMICAL?MIXERLTANK HDR ISOLATION r,y% - .'

  1. ~

~(XVD08441RRMWECHARGINGiPUMPSUCTION W.l b & Ull50,W. ; S I m.,, f-"~

%

' r.

-O - QM ' Q h k VALVf,$1'sq0 PEN? M;& T ( $j <[ , ..

sjv.%' EFW flow, tg (ea,chl.iS/G is Approxim Mg i [[ $ % F < @s.rf-2 ykf(;M 'JNRJ1gye15inFal'l THREE4 (3)

  • N. ;

% Qk . , 9l &Qj' \\ lbd ' kbf, cs'& " b;. "T - S/G's is % <- r. w'.,. \\, "Pf? $23,^f h $3!._. d2'2'"Cr"^81"9 - .. " ( .. h ' - " t ""n.

Pre, ssu,redih~> iill! THRdE (3) S/G's is ,# . . approximatSIy'1000#andrelativelyh'6able.

- - - n \\/[(, . pp -.. . - Based onk_,ht,ise indications, the loss of suberiticali.ty,1s due to: ? w d'. An unisolable faulted S/G.

C'* v x /s s,, . b.

"Ari" inadvertent dilution.

4.

h.- t + -/l, 2.

' ., - , c.

Blowdosnlof the:MSRs through the L.P. Turbine.

m d.

Overfeeding the S/G's with EFW.

  1. 5328 ANSWER:

.

. - . .... . . _ - . - . . , .

- , . - . $$. b.

(1.00) , ; ;.

  1. 5328 COMMENTS'

, .,ignificantly modified from 285.

Changed initial.

' , conditions.

Changed correct answer and replaced two . distract. ors.

. . . 'a. Although an unisolable faulted S/G is one of the

  • ,

most 11ke,1yqyenMthat yould cause a loss of ' s s.oBeriticality tWe '/ Gip'that NO SI 'has occurred, act - MsIVd *are~open',' dnd . rchsuges are 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 CVCS.

. S/D of MSRs designed to protect turbin frpm ' h,c.

69erspeedirl rgnota;tS~p%K, MreveWfcooldown 16se SDM).

- VQm M!Mu;%';&m - m.

f f - FlowsSo 1.-g 75!gpm are norm.,6c %.7fy g%l*4 v jp f.. f d.' w - a fflows after,a trip, I onde:S/cs?a~rd atg'inimuthueWi# D'* & n j@NT4I S t.

@@ $ff:V2 (,% i ' fsQg$,$.MCF T@% mij M-T.s %/ s .. . -,. h d);I MkI ehh_!N kI , (0$hyA9h@hfa3Isp;7ps$$a$$$m$$ b ,, - WMe -- @'.@s (/+,) Qgh_Si-N 4 4 ApSpf{ a&5;i ' c

a m e~ m . w'p%[%gdf 4em _a . WN %j 9g i Pa

  • N( 3 h, p

i ,, m gsn d.D,s.3 ... (# 'FJtM @ g " h5 3/ gJ% N Q& Q y:syq;<;,w$hg %?:b5Y nwng ., mm -\\'\\h, NNQ ";lll' h ' m h* S f f .h, (Lfjfl;M\\o, 15 h LA . w v

a

~ .. Q g)' > \\'.c"r w.

. . . [/ ' ' ' , . ~ y d.

u N ,,. f., $'% )' 3.a{- V .% ., W,I * ' -4

, r

. t. +g

sq"

- ,.. w~ , ' .

4 s 8g-a

9 .

. . . ,e (- r # w - - - - - , t w - .yv,

e w ';-9 Question Number: 24 s..

  1. 5329 QUESTION:'

POINT VALUE: 1.00 Given the following: ' The plant is operat'ing at 100% power.

e e During a calorimetric, the NROATC is in the process of adjusth gfN44,,y\\ / hen a Turbine Trip - o.cBurs'. Ii'8,' i" 1."- ( ) // . g ,I U Mey[eactor does not trip a[utoinatically, and an ' ~ "* % .

. .

Q ttempt to manue'ly trip the reactorg s i N ' unsuccessful, yjN ~N M.

, e,A), 4*. Txvo is 8 degrees greater than Tur.

( . ( ' The,E,dy.o..f rod.idnssnfon?.fo,r1.th.dse condi CRS directstthe-NROATC To use"the p ferred

e d oAs m'eith - n.,. ,/ J-D a s e,' W *n,e these co6dit. ion % w'tt .. ww n .?:. : ?.. ' ..%.T GW,e NROATC d;hould.Y

ct c s A, <t h . w v, ' r,r r e s~ .g Switsh36?MANUAU"E5'dfinsert 'Tdds all the w(ay 'in.

q. ; r r, > . &*_ a.

,% r;. s, r'& .* G.; r.

G; J m.

% q.,. y a ?. - + [ . % r s .% f* b.

[S t ay (in?HANUALWnl es s; ONE s(f)/ PORV ha s be erig).

. <?:1 N,M}freviiidslp/ isolated [Lin1.which" case)r switch to-AUTO.

." t.)q r @:;gu a C.;w,.:: m. p,to _,,[i" Q 4.. e(.% M ,, c. Q., o.Stayrin AUTO'a euntil Nodispeed,dr,op~s/ below 4 8**spm, e ,.

%dthenM nserti" rods)iri NWUAL.

' T M { UM. ' N p#@/T'! eg h'**,)" / c Y%7'Mbc$ AUTO uhtlR#ciilsp? 4 Witclhtio eed drops below%48,spm, d.

(b thenin' ert.TodsiiiMP.A.'TUAL L(:N& ,;.C}y / s - "sXjy& L.(: y,,e V ' ' . # 53 2 9{/j - , MSWER i C J (f,e ' -

v.

,r y ' hd, (1.00) { ,,

  1. 5329 COMMENTS:

%s Signi[w.-icantly n:odified.

Changed st6mfand distractors a., b.l& c.

'~ , . e4 %

d.

Correct";i RequEres traibee to analy::e symptoms, apply Note 1, EOP-13.0, then determine appropriate response.

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 MAN.

.

. T -

_._ _ _ _._-_ _ _ _. _. _ _. _ _. ~. _ _. _ _ _ _. . . -

. . + , . - .

t . - 3,h ' ' Question Numbers-25 ' i-

  1. 533'O QUESTION:'

POINT' VALUES 1,00 ~ .Given tle following: '

, , , . - - o The. reactor was initially at 100% power with all- , controls in automatic. ^ ,

Ypr' N#118"the.,Centrol Room to report ' e' The-IB .e - aA 4IAdi ib rokeE'36'ths 0 6 IB.

'

^ ( \\s ~ ' ' % q f,*,.,. ' A (DATC reports the foll'ovfihg: . . .. . , _ '

' ' .o

. .. %g g.

, N~ - .~ . , . Q- 'FRV deman'd~ signals are increasing, and ., { feedwater flow is, decreasing. # , IA Pressure 70 psig and decreasing

. - TNf EOP eni ,/ -e I '*di' ate dp ra A

  • -

k[' prl56E.disr,e'hhaYe been -initi*aYe5E "d a "MAI RX TRIP" . .,. . f aniinif6iNf65 flas actuate'di$EIN l- - - r ThefSEZc ecks IpC6andf re%dih?sithe fol % 4W* 14 %W i %

e e i port ' \\condli'EOY15T i ' WW 'W a " , , Nd kYR$ R l$$%yg,, gg g .. ' ll@g I

' wa . , ez"

+

(f) q==u c '~e, - gAn G: ML ../31% arid # decreasing ""# % i? .u 0'>f ' ,K/' ~ f hi f .

  • e "

GrWRalieve.Yh29aseers ' nd decreasingurbpidly z aog s/w$ \\WeVeh /24Nand decreasin - t - d - 4WRT - .The NROATC repprts;/the ? '11owing: h .6 . !! ! I t,p* $ "'v_ g/,w e- . w . ,, . . " - - Rods moving in at 52 steps / min. Q - /% yus - ' e/ The appropriate procedure (s) has(hav Leen

,;Lmplemented-for these conditions ~. \\ ' }:% .Z~1 ... With the prer entiplant. conditions, what is thef asis for tripping b

the Turbine?- Th= _&_ e;T , mg <- p.

To decrease 'T,,[To no-load to maximize auto rod [ . cspeed.

.a.

. b-To shutLdown reactor due to RCS heatup.

c.

To minimize-RCS overpressure, v.

% - - L .

- .

4

'4 .- . . , . .... - - - - - -. . .. -. . . - -

.. -.... -. -.. - - . - ~ _.. - .. -.. .. - . -.... - - -.... -. - -. ~. -,

' . . <

-I.

.

. i

'

e . , X?.'g)-- .d.

lTo prevent an RCS overcooling. event.

, '). . . - '

  1. 53301 ANSWER:

I ' ' .c, (.00) . . , ,

i

  1. 5330 CO@ENTS:

-

. . 'Significantly modified.from 277.

Revised stem and-

~ distractors'a,& d"; R $ordb'd',co'rrect' answer'to require examinf59 td'g " 'b~Ep'erRijtFtas$s r ' - Tncor(rec,t.., ' %f,f f j.

~**

.y . . . . . ' . -

'.Not part of the Wasis.i .a.

. . . ~ %,

. , .' Incorrect.

The steam dumps will d'ecrease RCS . . .

- temperature.

"^

- L)fhdent ' - . . = . . , _, , c.

Correct - per step 2, EOP-13.0 basis.

,S @/*

  • diffst' determinestromplanGNnditidning t a the RX

.'. - /[ s' oOhthav$$"$$iphidsdif56 Tor *S$NEvel ( 7) n "C" ' , m 5E..d.rdent }nust assume 6655E,Thual RX trip was " SG '

f

  • b$p%

3 7 ~ . b$ k qgh j An oVercooliing g/en T1s$$!I$ra!f6oncern whil(e-t' e ' Y d.

, ' reacE884$D till'cri '~c'a M 3 T Di ' % '

S' ?;

$$ h?% ' $$$W ~ termd.neNtlist 4., turbine tr ,. . .,: . R res examrnee . I !) afEEEEfgosdTO$Mee"dE5BdEg~'SjiTire,qUijedtopr"gpp . ,' ' event a wil'hfke}t's$1dQ%5i5.{hedSorrec,tlajkwer}; whi'6)f loEA Vturn,.p^reve RCShoverpressure.

M y . ' %1 y p'y ' Q m - xy i % + , M.

ji ! 9 68 (D ' ' . ). \\y . . . , . .p . . <* 1.

f*%, , -/ % / .~% _ r %. N Ns . L a.- ? F U %.A .

. g ? 7' 7;- 't.c_ J q.

^i

+ ,

- 's ! . ,: _ s '

. . . . - . I - o ..;...., _ . . . ... .-. -.. ......-. ..L .~ ,. ..- .

,. . :! f.)

Question Number: 26 ., ;.

  1. 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['6perating in automatic.

2s 9p Iap; c ; L . x n t ly. a...is t.b : . The..following c,onpiti, s sdrre.

s s , ex 1r / f ons c 1.J.p , ~..~1.s w . - . . . {gvgis575'Fandincreasing.N,J,#fg

  • ,.

% ) Pressurizer pressure and level also*b6 gin.to es , .

,,k increase.

(*~h - ah ptoms IEe%consistentitwith:ShlNf5116w~1ns event $( withf [the first'@Jum,.ag.% y, These "s tho's6TE$at wolfld be eceived

fnI2te onshidh%f .,,j q AS 8 := w + cri i.d e -;; -,fgj F % . PZRicorspiv(alves;.partiallWopeii? then fail closed.

,m 4,-% a.

b:n w:s.2 ry wx t, WM, g - e) t ne u - xv t,, - - ,...3 ( Cont'inU'h;5!frod UI 6draWal W; Rn 77., b.

o K %' ,% n w.;v / c.

u-m.

. a; y sw..,.u. -.

py-i

, O, I'" c.

/t.The c'ontr'olli5gCPZRiPCSetranbrititter f ails l'ow? @ d.;N$[3 M35$9f M 'M NIkNr,$ D [ f1,-} I r[3-) t

cWc ;c ontrolhng. PZR4CSctransmittet f ails l'5~,.; . d The c

ow.

a y n:: La - v%nn c. y: f 0 [%4 -

p <-

w.: 4, W; a., hr fe n s, r:W r H ./96 J.% Md.u'., d a h $ (- pJ d. h. ~ .pg.

e ax jf ?W M m. M/~ %y c .,, 4ff

  1. 53314 5 ANSWER:$ G

""p g* T'15'oo)f af/;aqi Q ;, yg,,, jQQ2

\\ $ g - w, d b.

b. py - p ,.,. r p m, :s s n . . J ~" m 'a v QW t, *

..

  1. 53314 f

.COMMENTSt $Xi-?/" \\."'(/i ' . .x,[s.

. ' Significantly modified from 223.

Changed sSem'and

  1. ,di,stractors a.,

b., & c.

Resequenced distha.ctors.

, / Has no affect on Tavg. %. . a.

sIncorrect.

. % Distractor fased on given information abodt?PZR pressure and level beginning to increase.

7" ss A - -*, b.

Correct) Student'must determine that Tavg for 50% is 572*F.

With"Tavg HI, it should not be increasing.

c.

Incorrect.

Tavg will not increase in first minute, d.

Incorrect.

Tavg will not increase in the first

.

__ _ _. _. _. ..... .. _ -. ._ . _.. ..- _ - - . , . d

-A - M0:}),. ' w'* minute-and PZR pressure decreases.

y . .

9

4 e

9 g

9

e

  • Y /

,{#$ "f z. j"\\ '

' %, Q, /; e,

it L t - , % 1(y g - , , . [% g

.% [

, k. d, g f

9% ~ \\ a4 .

l , W 8.

,

J - - . s . 'Nw1%w w w&Mg?GP s G . &- '

egh e t . u ~wsshaw q1< peedyE6ch7dfgNyU -+ N G# 1 d.[a s%m. ~y' sg s.

f2' / . n w m..oLg;ge geg w ta .ws m p.- o .

Li$$ $ - - ,wa ~ F;gze>s1syssW ememG,y ,c ekJ AJ b, - ' 1; d-) %s e@x w p_ u g g n~ : J 7 p M( W p gyna - hs L3 wh wi, S, ?ga, N s. m w g g u&p;r , m - %Y h!? - A5 'k f,,+ t "% 4 4*c.* y+s??at p% myCP %g - 4 mhWm y 3_ ~ ,,m.$5%Q"elg{fsyn u.- k ~*7;g&g 2 - g sg %.,5 4 $,1 J % g.

  • Y

' ' v n n..~\\ . s, & r,A., '

r '- -

tr//, l \\\\V h.'/ f** j. s e tf-

(fl j

f j %sr,t\\.~L) Mb" > .-

Q @# /."p. 4~ . . , -.. . v . ,;l,{ ^%xn/ $/ r*. % 't .r l

h, N - s ,1..- r s.

Mf % A, b " . j.

. $t

W* ' L.. A s,_ . . e , - m.

~. <.u ?f v2

  1. 4

. I b f

~ .

8 - - - - - -

. m _.'A Question Number

d

  1. 5332 QUESTION:

POINT VALUE: 1.00 Given the following: ' e' At 0400, the Control Room is being evacuated due to toxic gases.

, 'o Two operators,have3 edomersick due to the gases, so the b SS has.: balled finkeli6f 6 ;for/these two operators.

  • v fu

~ ~aw '('? $ f, "- ' , , .e Therp a\\iInimum maintenance'doipiement.

' a, ~ n.

sy Cont *rdl of the plant has been establi yshed.,at the CREPs.

- ' s \\V ,f' xes ,

  1. 6sK. ~ ~% CS pressure is,being increased via PZR heater,s B/U k

,4

n.

- g I+ h* group;1, Prior @to;; t.he e. vacuM.*?"*WMUN,47 ep}" J ' f.

' h.

e ' . ationgther.e~w eiNROATC,zeported the d,o,ere.bproblems n_oted with ,

  • e

- %v,;4 CCW.

Th.

~ llo.< wing RCP parameters : E <M,. k-- :gs t OM

n.

n =T p:fy.: g u+. . -. - t* %,* - ex Maxcmotoribearing temp @eratureiwas 150*F. a n d N, steddy'.3d:l ~~ kdOy 'd' (< T" e% - Max (sesMater.QearinVltsmp, Nis 200*F and stfeady.

y t l'M n. _ f* - m.,,ax m,o. t. ori st.at. ort.t.g,pe, rature*was 2 5 0 * F and 's_teady. em .% c , , .,, f , E.

. ?b. r'Y3 f _ Y-

/ .="f j _j-The/followinggpla{nt condit:1ons exist:m[ ' w r/

  • '

%PZR3piessurdjiih [$ [ E '%.. fj%fj ," % 3. % % %ffSPn 219_0k psig. M 7,#

- TSU6do31,in Fisb26 P M.1.V C$'N' Qo_ % - [# j - "PZR $iU7e h.id",Ii'2 Waiidh EaBl E55 %' \\J - Letdown'gflow'lifl1'@00[Wpar.,G9(adjud3edto85gpm!"A ChA'rgih'g flo@pA ? - y* ,uf - - O,u y-f n s.

. the CREP should p.;v .q u The oper/. x ar erform which one of the e ator at -* , followi Q actions in response to these indications? f%[% ? "* f*) Initiate GOP-8 to cool down the plan}t.. ^ , 'af m:- . t $

    • ,

b.

Secure the running RCP to prevent pump damage.

- p - .,;, s 4.,. v c.

Turn offtB/U group-1 heaters until PZR level is restore'd'. e ,cm . d.

Turn on B/U group-2 heaters until subcooling, sufficient for natural circulation, is restored.

  1. 5332 ANSWER:

c.

(1.00) .

. .

. _ _. _ _ _ _ . . M

  1. 5332 COMMENTS:

~ n ::;., v.. Significa'ntly tnodified.

Cha'nged stem, replaced 2 distractors.

Modified all distractors.

Resequenced choices'c & d.

. . . a.. is incorrect since this cannot be justified from the information given and would not prevent heater * , . damage.

. . vs, y ~....,,+n~m . m b.

In. tor,.rectt 'R P'1 ripf cr. i,teria met. Maximum Wa. tor"b. w:in.Notempefa.

t c ... - . mo e.ar g ture,? l, s,19 5 ' F. Maximum seal - , ,

tep bearing temperature 1se225'F.

Maximum mot 6r.

. Mgyatortemperatureis311*F. %. d T.

Student must analyze given condition [\\..- .

< g F

. s

h s+in light-of PZR level interlock (17%), and CREP kefation . r overrides to. determine that PZR heaterssmust.be

LA shcured.

e -#fMIP

V5

m.

, %rx,d bd.w!;t.x A.%m.,,.c.,,;,2*,.

O d.M. rf

?? d m ig Mp/ y

.1.. s

p / - e d.

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 .m y /\\ t.'k, [ j- ^4

  • - *

m .# tuistidhn65befheaters thht"?chd1'd?be damaged.

E' ?**w y &1:.pr; g s v ; m.

r; + p%.

CI# h h h? NN ,s m .- y%* d;.;-.m a my+,- , mp a ik.

v f: y m Yt O}yfO' + q;mg . {*** Q Ls* .s.; f * 4 %WAy+ -~% L $yG H Qs:-bRvf %;j w'.'.'t % jC'WT) 1' ...YT;W Lp p.3 _ .[ U.* h

lw[' g r.

w,p me, pan a .._r, a Q&s[.f,;Q@ w ei,kk & W+

QQC Ah w%ll$ gn$f t, %.a m., t a e %.s .;m.,e,Q.;Q%...i )a w & s n+,u

yL s QQ;qv.3, ' s ~~g:'.j %W *w%%m:.u%g_/,s n: ,n ,..:,7 e s;%c & ~ w: e t ws .y? &sQ k .:N j-Q3 " m.Q,_[q1m 4

g q,p.. m3 ,. % \\p\\; - a ., J %~ ,,.;;L*y f* . . a m rgafj/ plth. s .~ \\ M ', q g %gg s\\.> s }m% p i 1.,yf r ! ;.s; g i q f.: w.

w. f t.e** ~.,f O.,?

. C

  • wt

,4.- - e v~st- [ n.

y sI e +f. M.

?- +

g [,,d [+\\ - '/ ) 4.

~ / p ,. w,O

4 % i j Zy

, ~ ;

y =..

  • W k

_g ' A *! " .k.W.j.** .K_,. '

.M

, _ . ,

. $ _ _ _ _ _ _ _ _ _ _ _. _. _ _ _ _ _ _ _. _ _ _ _ _ _ _ _. - _ - - - -

. .

e f. d.

Question Number: 28 .

  1. 5032 QUESTION:

POINT VALUE: j 00 ' The. plan't.has experienced a blackout of both ESF Buses and implemented EO.P-6.0.

' 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 loads.

. ~ . . ~m mm

m 12,5 vo[s. f%[, >1 i l[,t.,[i(~-h/}; a.

  1. a12dW

,, . - y r , s . b. W olts

s 9,4

' - . - s . Q.

( /, * oc .111 volts c <% , %Y, f.) - . s . . v - d.

, 4,08,f?v.olts <# . m

05l... NY,~AN& ebb ^ / .,

  1. 5032 f j ANSOERsM!h M N $$ *h "f

W" dsh.ekT ',m ~w, ww.sa.y y e n n:,:.=.z.

w f w..wn (n:.toob. y #J, f M'&;+J' .v a@N5.%M5s ~wce ' % d.

i ? . y.m a > p ~ vu (%} k rg $TEjn;MyMi$f3 % w sw o .- smm fr

  1. 5032='

COMMENTSi?u%m ?n Aw-W /?.m 's ln,,1 a_ w m e. ' u sys ~ L W W &.g & Y[ a r X [EL, w,H:. ( , m e "}f '-

i., {,..,.,A, s

  • 8.
  • 4 V.. : 0 d+.%"J SignifIimcantly modified?iChanged[5tenfandedistractor a.

,.g . AA eme m: RIM.y.y y. " p n Mr#C' N ir*? 4(5 d@2Mb *'t f p;TechiSpec limitforcc:eque s%w :' :ii, *t* sew.ge qr cF , tteryl;lv{A'" t charge,

e '

$ ep 4,fg %,,.

-m a.

olta [9 0'y m.

~~k

Lal.m u &. t ; p.t .as

. m *~* p: 3 g g r wo

--s .gi}. b.

is equal:tF60" cells' times'.tfie1T;Seminimum cell voltageM .-v.

.., 4. n > = ~ :P. up6-s % $m V' is the miriimum v.,Uif.\\\\y (.R. ~L'?ll n(tper STP;501 , i s/r olta,,ge, m .. - ~. . r,,. c.

u,a. city Test . , ,, s "g.

d.

' /,d.

is the value given on the reference page for EOPf0'.03 e m A %a'tz/ J < / / '*.@. e.

%"? %% y & p, r,: Y 5A , ,

  • e t y

% r f, * _... ? " sq g - +, 9.a Q .* . . . l .-

- - - _ _ .____ _ _ _. _. _.. _ _ _ _ _ _...... _ _ _ _ _ _ _-. . . -. _ _. _.. _ _.. _ f .

> . i$) 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 safeties.

. . 6, / A M,% , M b., - - e f16GO.' lass. commenced >a,ra

' Ttle cr.ew f p"id cooldown of the RCS IAW - , V/

' ' - ' ) %d z% .,

' ,. . .\\g Reactor trip was verified.

/ % /r - Y Safety. Infection actuated and 'SI flow verified,

+ y , Q1 k.,feinment pressog;m$j0pyh"? hk?lf

- ,-..W a Con .... 1 gfand slowly; tncreasing. / s-f-1 . Y) ??bWh, S/GilevelsTggroximately 50 Waded $ creasing.

I - D RCS,"pressu&s UV.mm 7 d. y n&uan?)f,)* i M Bh 4B.n.4En " %* i slowl % re;1400v - gd'Ydd$y decreasing.

W,,, DF/N}b ~ psig an -

h p sadtionsjsh6Dld@be'take3 or RCPs 4,90 Given the conditions statehAt%ds" f . A' U) a,fhh,,,holu $hEfhIhQh&W (b?rb gkaMRd5 cooldoWi,[dge"ctediby EOTbg Ingped becaus RpPs s . 7aN. w% . Pf

g- %iM 9MQj; 2%dh %h a ,5w we's op d'NOTj%,7..6eitripg beca

Q,$ b.

prchibit amRCPgrestartind c>)psE'PZR level > RCP s . % Qi;gi,U Q* G W ... -dic.

'The RCPs should be trhped because CCW has begrg61ated to ' - , - . "// the RCP motors.

"1 e A) - ., ,.\\ - df The RCPs should be tripped because #1 seal %P+is in jeopardy of '#g lost.

bein u '

  1. 5d34 ANSWER:$

l.

.[-f

. < y- .c o,

.y

- c.

(1,00) - - '#5334 COMMENTS: , NEW QUESTION l -

, s L

' l l -- - . . . . ?.

' - =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 exist.

" , , - b.

Wrth a PZR steam space break, examinee _ should assume that . PZR level' exceeds 92%, which is an SOP 101 limitation for.- ' ' - -- . '. . starting an RCP.

' .

' 'c.

Requires examinee to determine that with RB pressure > 12.05i a . . IsolatikihasIdcuir {" ' trip crife(ria hidystapply,le'va!edAOAG-103.4 stat

Phgse n ifYOP.0.operat' r. controlled o ... . cooldowrfhas begun.

/ '*

' ' - . V .. f' .

%g ' ' . . . . , . , A.

ncorrect since 1400 psig is more than adequate to maintain: c .

  1. [""J}

. {. minimum #1 seal AP, ' ' . . , , ,z.h- ' Ngg@amBG$gg? ' - . a dr$w wa bjk . 4%

} ..

%g <.

($

';g r y ' .=r - ,/w%,Qy ^~. gf[h,% ' , , UM}'g?hJp],$g:t . ' l . . . eg andr w. nm y .. E

.

s ,, 1. *.; 9 rA

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  • e

. ". Yy ' %.e ~' e . . . ,.. .. . . .# p ' L /e Qw: w% 5.

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._ _ .. _ _ _. _.

. . .__ -. _. _ . , , , . . d m r .;1],) Question Number: 30 ' -, , , '

  1. 5036 QUESTION:

POINT VALUE: 1,00

.. . . Given the following conditions: i ' ' , , , Ths relay room is inaccessible due to a fire.

- . The S/S directs the N ROATC and the CRS to trip the reactor and ~+ ,. prp, geed'io itae@hEPAh'dir.ect's the:, crew to place ' ' C6 - From IN ChER, the s/Si .

- . NJMdgF,'5.# "4d/_ ., ', ' ' % Atx " - , Which ONE (1)wf he following procedures will the crew use to follow.the direction of - , h Y]e

  1. /

the S/S? -

s - - . ._ _ ' , ha.

.F ,027, Safe gg g k'/ b.

GQ 8 hnt St$t[[v[nistbotitIhl5ho Cold Stiff' own , , ' d WithiC6nif6f;ho"mJnaccessiblEffQ@#

f - AD gg.g gN hk(% m J}9Wengs 2# } ' $

.. wg wyn f.

. . %, c.

. AOP1600!ir$$I),474MhDliD:- contropRoom5vacuationy ,,, h= 9M$i pf-4 /g'{nttSfiutdoWrini6m' Hot 3' Standby

, --

Ne, d.

' i h Due To Fi(elr[5Mii3}5'ul$il'n*$Ef# <f.,[6/4M

( ' l YNEhfG I [f F

. %

'

  1. 506]

ANS , ~*%f1@%g$f jy- \\&w.

d.

W[' U r 'v - p2 - O-

  1. 5036

_f1COMstENTS: " '

. .. .< > s** sGIgnificantly modified.' Changed stem and distractors af&sc.

Rssequenced choices c & d.

  • 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 conditions.

. --4" . ( -47 . I e e- , ,y-4,, ,,. me.w.- -.-.---.m . . - - - - -. - -

_. _ . _ _ __ _. _ . _. _ _ . , ,

. > O Question Number: 31

  • ' t

.

  1. 5037 QUESTION:

POINT VALUE:.L,0,1

. 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? . a.

Trip of 1DA normalincoming breaker, and loss of . ' Pa.g,r 115(KV7,fi.ne[U I",p.. u Ag. I L 3 pu ,- . , . .,. . ADB ov,ercurrent lockou. b(51BXf

  • <~

e - . b.

t and.

.tr[pflockoutofOCB-8892.

"(JDB)-not' reset, - - ,,9 .g pu . - M Trip of 1DB normal incoming breake9/g5 d loss of 3* ' Parr 115 KV line

D' %,. I . . . < IMiisqf Parrel4QKVRineM[51BX-1DAL not de,4 . 1DA overcurrent lockout set Q#,,fd.

y.

'

  1. jf3 l

wb.;;h.%%q=~=ce,.png:,w?r , n ,i.

%ggc27.n.%9. y &Gk::. ->;nMiM --c.x n u rs /- y e@w*s.:ks:[+f"k;r,?. > n _a ~,

.y+ s %w e

e. ng'.;y m+p - - ,;% ~~ ' ijjg W (7%,

  1. 503J,,,

ANSWER: ) ,%g .n rew / .a s jp(1500. A. +&e.v-<p.p g.g f %.1 s v t c.

t .. w-mw.w,. Ac,g;m.<

  • r=m v

s <

. - a,c,,ty;i-9%nw. - - .d .m.., y s f ,.u .' *.

  1. 503T)

COMMENTS: > fn b F Reorde?f.*g u.r;vr *y:mwnm.i ).ao .,M p'EW[h% & .s

~ Y n% w.

, i?A.

"; w?9

HMMe$yW1 I / #7 '"*77 $P ?ffh Gb NN$ "' Modffie% red s-b & c %.. R d:c$aq u.7 &p3 E & W k b, p & 6*e

f"3 /f i b OWi hms<M - % w be*8 - normalRsubjilffo"1D'A*&.3kithibBtih5D/Gs outExam.ine'etmustMeter e the and'lo b\\ ~ normalincomingtpp//fhYP3f/ 5SP biides/~th'e ESFLS locks buhYthe Y alt, breaker 6 5' ',f '/W g'".*' ' i,p* - . s" v.. s - \\

W$ e

v-f.

% <f ,

  • f,/m (" 3 w

t s) ,Qw e , v.p hd p,. fh f( y %a , Y E ',' '

  • w,.

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.. .

. _.. _..-._-_. -... ~. _ _ _ _ _ _, _ ~ . - _ _ _ _. _ _. _. _. _. _ . ..- . , , ,

. . ' , . ).3 ' Question Numbers 32 -

-

  1. 5335-QUES' TION:'

-POINT VALUE: 1.00

- +. Given-th.e'following conditions:

, .. , . The p'lant is at 100% power during an A1 e-

. maintenance week.

, - . i ' as-been ' transferred to APN-1FA while - e APN-5901

  • *

woYk. mis hfogrliis hn XfT-5901.

t ' . 'q ( ' *** Q $ f r ' ' ' . ., , '. e g Qu,ej ormal feeder breaker for,, bus-1DA trip.s open' fTh

_,. etoafaultinthetripcoil.g[[ - , .t t

, , , , "A"~D/G is tagged out for cylinder A,,nspection e . . Q' , ' . . . . TheCRSimplementsAOP-304.1"toreenerg).tz e'. bus ' . ] 2PA- ~ cqgggm.rgg Agg , - . i . Whic IfE (1) of lo ng describes 5 owethe "A" Tra ESFLS . . in wilQ.ferateunder[$t ~Y$$odditions?-[MsThi@ is t N5M b f ige 't

Loak ' 'e sliedptndS$h'elESFLS will resume / r - pN'# segun "61hcy,once' iti Miesst$1'dBally.

  • a.

'

  1. %

+5 w 2g.,,e. ie. wRP

" ^" ... -

=

>) - - b Ibad fishe'dgth,e_nnt'h'eFESELS; will rema ne in a ., 4r Mandii9j$i6t$1filietD 38nEbbt bfeaker closes'~'or %.}is IternWtd ~ f'e'edd"r YEdker'1 ~ cl'6 sed.

~h

g %ig ,,p p g$

  • '

- ^ p, ' I %e, a.d s. ' c a.N,O

  • sheww a,nde.th,e ESFLS will I'dsu. me

%.aJ ' c.

- =c ..s~ ~ gsonce 2 sges.et ocally.

% ..k . spqugy!A eM// a ri , . - i i ' d.

Loads will NOTie b' qd 'and the ESFLS will e'

  1. -

. prevented fr'omj6p'eyating'"during the blackpt

, , condition.. 7- +. - - x '/*} ANSWER: s%

  1. 5335

' ,, . vA - d.

(1.00) N y> _ >

  1. 5:}35

'DONMENTS; h'",7i-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 a.

fif bus'iscreenergized.

" Reset-locally" is

4 ' aplaying'offa.a common misconception that ESFLS

.

g r 49- . . O % .. '- ,,-g --,.,w, , -, v-r.~,, .x w.ww-,e'---rwi -- v w r i* ---+e--L-+-----~----%--+--+e


--2--

- - - - - - -

-- ~ . .. _. - . __ __- -. - -. - - _ .. . . , . . . ~. - VD ~j.",ig needs to be areset" (vs..deenergized) in AOP-304.1 ~ %^ to recover bus, b.

Incorrect since outputs from ESFLS,will NOT occ,ur.

. ' ' ' d.

Requires examinee to apply knowledge of sequencer, - apply understanding.of Caution 2.0, pg. 22 of 54, ' ' - i in SOP-310.

' .

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wramb p v v p:LM $ , - aws ge N W:,.md t[ RLgR%.. 41: %Qc: A

m ef ($lh50$ilb$hI?s&YbN.kki$y?s&q%V '

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- - ~ ___. -. _ . _.. _. _. . . - .' . - . . , , ' . . . % .[..,.) I Question Number: 33 ' . '

  1. 5041 QUESTION:

,' POINT VALUE: 1.00 ' Given the.following: ' ' i - . , l . , The plant has been operating at 100% power during a B1 .

. -l maintenance week.

' i ' .

The plant experlepcerstloss of.offsite power with failure of both '

' Didsel:G'enNgt'6fsito $$nq7diz6 tiie;ESF Buses.

. a fiftestfm{ inutes later when 'A' D/G isitahed.to ~

- - - -

'

- s'\\ DA ' * * ~ The NROATC is directed per EOP-6.1 to ensur[ hat the charging

" N ' pump ininiflow isolation valves are open.NROATC reports . - r - ,C ' e mm'A,gGI59 &1 ej , ' ~ Underith"ese conditionsg %ar&=m% h nmupfMVG'-8306 bs'op . m %; q w.. m gryn n.. s k e w; % ! cW N . a.

PlaceiT N RWRICKO 3'" sycUT Snitchiiri!ON, then ope'n MVG 8106.

< ar*

6 wdyMMM (/

. c.thbb $ ki h!I; y / w' nxsh f% + lace TRgPW. fr$me,,5witbb'irbOFF, then open MVGt

  1. M G

. .f-b.

[;$.5N f[y106.

z . R CgOUTi . ig I!h d lj

pggepTRN QPy(yL t(0Ug&g,n ogopen MV - Switch I c.

g j . "ik %g g~pn:MV g 0& 2 ortC.

p - .h p bQ '2%stgGLu b Place TRN A l WR/LCKOUJ;Switish'd d.

or C, therEhpeln$l in ON, open MVG'8109A, b - 1d6' $M j , y.

- , ,

. :.. .. #5041. < p/* ANSWER: . . . i ... , e %a/ .,,,4(..> ' s (1.Oo) N , < '

  1. 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 on.

. . g

-

4 / s % % .s __ _._ -_ _ . .

. . . Incorrect, MVG b106 is not interlocked with MVG-8109A, B & C.

m 1,';$ d.

.

6

e t

4

4

e

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  • g L+ #%k. d 1 ).f.,,3 i(' 7, (/.

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g

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h [ /- , . % ( - % - - . . /s.

- D %>w,%n p,i> / ,). - m.= mre /h.ed g . - milij:jE:.i"m.::;niht%jjia;bij;rh.a* ' eg& pglI.Q- ' Ay xu G. '.,.f' , R'hi:"* P**M.lO % $

s.

,t ~ QA ? -n.~n.M ;%g,.s... ,.,* t

i n ---

M, C L dlG;5 l7, J: l_ glcf;%"lf; y ,"$;4,'~'m %kQv :LGl

r7Q';gs %.l? pn}- Xd i:n tfd%* hr'* % (%%,, r A AV^,W+,y <. L n.

-

n;~;r: 81:

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n ' MW n casa

Oo a

m , vNl. M,5D.3IkN %ya G g %g g'?.T:d'f's .5 p! ev F%d75 cf,3 g h. M>.d 1'

W2:Wy% Rwk"* - w/

.>.~y* " }.s. J] ! Rp %,, .,qQ %. b :c.%)QNgigNz;p(:kUUlc$ i f f h p[$flY:P

3 e

1,h v: - L1

~-

<s-eLa ,s f Y b, a$&ps,,fifai , ~, cm ee s / w/, / m#y?:%w%,,, dyg:%k _ p A ~. ac u .e;fA

. 4Td fdh,, y L ..%g V g* ' to..'.w.:,g a%g' - 52h este? & n rz~ ~9.rw}.m. "Q. m@{.W:v.u,,j x,~..yf y.

~3 - 3a p.

"R Q ~4 j;4 . M: ~ - - v, .s mjM. ~ylw .J L . . s v.vy c&n , s,**. } ~. .

- o n x': %w -< %d k L s s./*N .. \\ * :,

u%- - %5 ,4 e j b a y 4'*%r d '3

': s ** p m,t m--;. 'f. % s Lf g +. + ,.m $ i + m

$ .

.

... -. . . . . - . ..

. --.... - . .. . _ - - _ - -.-.- , ' - , , , - . . . . ' . M Question Numberi34 N , ' n;f.

- . - i . .#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 operator.

, . , -' action, what condition will occur? ' h%

- fry,"h' wilbopenyMF,P., ppeed. will increase, , % a.

- and L S/d! %5 f,ddl twillli'ngr efe using P-14 to,close,. . _ on y FfIV "A".

I f '

/ ' . ' A"willopen,MFPspeedw11INnbiease ' ' ' - FRV and- < . S/G -"A" Level will inc'rea;;e, causi'ng"Q4toclose - ' ' - - all FWIV.'s; g ..j.., - , . _ , -h .c.

FRV "A" will o en MFPpp.eedwillpeereifeL ' ' ' g , ' Ne crelsieddfEsdwatfr flow 26/"B" 'and: "di5'giting-s agwh#171"6dOEeapl}jlfS/r1 eve'lm [*/ ' -

f A$j%rQgid f % Reic Ttif ' ~ FRV Q Y lhA VYTthh?W. M W Aj!!wa11 'd.

pen resulting3 njan increased Main

g*% Feeddum,p'Ta eedNfil 'hYd$11hedUse a hi-hi lelel on ~ > . pall thiisieIS sk$ Lg{.QT% () E l4:.a (f

.

m _- L

  • f f'

- . y.

W ~ }g * $[ r s.

A.

  1. 50-ANSV

~

- g ., g e k'iiij (ed Magg e&, .

. s

  1. 5046

. COMMENTS: .

3 g f, f f

, }NEW-QUESTIbN \\( h),

. , , , ./ j

ka)-Incorrect - With P-14 : locked in, alliFRV's will . / _iclose.

NN / 'Q Gricorrect ~--- S/G's "B" 'and. "C" Control Systems _will .c.

- . /sphbilize--levelsatsetpoint..JQ , _ _- A j a.,. r - Incorrdeg"- FRVfpositio(_doesn' t. impact _ FWP speed.

d.

.V4

> k_ _ r -- b +- T 0 -.. +

'_.

e

- < . y ? _..

$ d' f,

7 tr d e-s 't- -wd

vr ,- - F ir +' +4 - er &-

. .

, P.. ;.3 Question Number: 35

a
  1. 5341 QUESTION:

POINT VALUE: 3 QQ Given the icllowing: ' "A" CCW Pump is running in the' ACTIVE '.ain, "C"

CCW Pump is in Standby.

' "B" CCW Loopis the JNACTIVE Train.

"'h .,f Dlscha'fge}y presbur[e% f~ (Ay JCCNjPump drops to 50 ~} j , 'f'6r f.

o - , gb lg,Jand the "CCW LOOP A PP.*DISCH PRESS L.0" . j \\a nunciator'has' activated.

N,d g . 4((. / /* , , . Annunciator "CCW LOOP A ESSENTIAL LOAD LO LO" is , in alarm with flow of 4400 gpm.

C D w *',ea, , '

  1. ,

E,/"#Ie Thermal barrierxflow totthE$RCPsfi's 80 c),j nd a thcN.j,'R,C,P A/B/C$ THERM 1B'Af. &,.BRG7[FI.;O LO" En,n, unci ator ,/ f

v**/ iscact:1vated M( - g%, 2 sua n ,s c , -M %g%s.:m..

  • i. I N. I. La f '

x e.+ [g CCBP,idi's,.,,. p 'r3Dt,chaigeepressursfisE85fp'sig. Q], C.' t.. s* .#

g% y gag cogm ;g:.c.y.e wa gs ,- ~sq* p;;ger.g p,f t , C,y.7 q c.

ma Jg pp _ x y ..% Whibh*ONE of the'foll'oWinWdescr,i3es, tthe'iist'at'us of the CCW,.Jystem giveng these reonditio'iisMd]GyQiW1M 9M' /y,LC}3

  • - @

WWM@MNf' j4 h Uj R&% ' Q :,5.

y n a.950CbE. K.~floiidldsh,,e,nEf,a$, l valuesfesd6,Etial loa sand *non -- - w. t e v %becestoredFto rnoinina f611owing automatic , hp 9dtiN{g.,j h%sEahdt3yjcCW pum' %'~ M phj _ p

~"*p3 6Q fyg]Q3 CCW flow wil1$$enreddced g p A h)g b.

to' essential and/non- - essenti[1 l'o'dd6]iehiihehCCW or CCBP stan[dby# pumps f{,,r . ill automatica1;1'y) start'.' ' . Q@<r w - /j-[h. , , v.

.c CCW flow will be reduced to essentialeloa'ds, and

q MOST non-es'sential loads will be restiore'd to e nominal values following automaticms.t.da.rh of the

.e 4tjandby CCW pump.

\\n ,d. h .$' 7 d.

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 isblated.

,#5341 ANSWER: b.

(1.00)

  1. 5341 COMMENTS:

I

- . v . . .

- . , . . m m. A,9 NEW QUESTION

, - P . a.

Incorrect'since standby pump automatically starts at 45 psig.

, , ' ' c.

Incorrect since pressure to CCBP's is enough to - prevent CCBPs from tripping on low CCBP pressure - of'30#. ' ' ' d.

Incorrect;,, sfuge RCP therpal barriers have an agBomatidjcl6sur#"bffth6 jhermal barrier return flow h/d^ l.veMn hidh 'fTo~wl(V. s.i Iow flow).

. , y - ~p p.

n,Y .

Q.

py \\ '4 %,4-y

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y'

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  1. 1h e$,'.aw,rg w / %e gw

- Q;hT *I.g;? se 3i',EN*zQ &%~$e'%m3m,47 W$gby;.1 (t?*n%.$ .. g Y y % n.:, ^ C'W :.a ' t I:<'&'N'.?:42% ,*u 4 .. ' gTQ4.- y+a;ea ;A: i <- t &

n.ey.,

% y.,,,ag.2. vy$ ??[t bl$.h 'Th5 l y '% rYI 5^ As A*% ~, e + d: ,4 m w. 91p 49,w y - x }ga gi; % gaJ , m , mwano 39 sd. g 3 jg q.3 s

  1. j

ypQf,fdNgq&(yaAw&k;.:;.;t.:q4;;$g;

Q,, l.7,; t,3 w h %?;l,,hf IU5f?$ $5f?d ' f' . . h? Yk / ' [ cmhMo], ~n%D.u{k k %w$ ~,;)/ %jd

y&?y - + W plF*B;illiOrlSfi .e i sw 2.c

p1GR.

  • Y:.{. }}

(pN %.. " * ' ' hi3

  1. h 2m:p!kk N d ah

- mML,as/j f'jp'~t 4 /n \\ ms8/qe

.~~

u b u c b,n -

T. r Q"T Ihp s f

/ Q,cf $2 y,ig F t r-i LDr ,7( (,n v - g js.. e . v- . , . d f%q r y p W q.

b, i,. ,a s..

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_ _ _ _ _ _ - _ ,

f,' @ Questi'n Number: 36

  1. 5336 QUESTION:

POINT VALUE: 1.00 Given the following plant conditions: The plant was at 50% power will all controls in

AUTO.

. - A loss' of_ ip'sprusidilt'" air forced the crew to

iJtiplem6n t"'ADP(22 0~.'i.k.".- / ta - lu a f / /.

  • -~

3-

. - Af ter initiatinT):a.

s

. rd'a actor trip and completing EOP 1.0, Immediatie - Operator 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). ~~ Locally gag open XVG-9627A(B'). torest(. E af r ja, a.

o5e CCW Surge (#1

  • TSnk leve1 g~~-4.&n,lLi "u2

,,~S M T-f d ~ fycachumulator air pre,.c* W' & & W.

c} & ~hY QR~ &**'~MW

Verr,n @ % ir s ,. 4) b.

ssurethas opened XVG- ,k ' 9627A;(B)Ati61Eestore CCW?SurdeETshk level. % Locallyfg,sg N,.,9 y ,w 7 g

-f4..1 y - ,A m

n s.

o < i g [\\ ..,, clos 6EXVGQ627A'(B) to prevent %

c.

overflosing,s <hq'.3 w,9;%y~ surge liTank! CC

  1. 7 t

4 m w., .1 p, ym a y a m,. . s g w 4 d ; g, 1, AM" *.. /..p.7y u-2 c..,g hf ..s & t ' - _. ~..i? d.NM#erify)ienEgh5EtT' '4slkssic1b~sedstoiprevent AC XVGfS627&(B)QiaveLFAILEDeclosed on losau of U() r * ^ DYdit tl G M ef,flodihgaths EC Bhrgd" Tank.%{/ ~# y ywE g 7.

. %.. A ac fly . &jktI p ar., ir e*? -m %,.;l m pq,ng.g,d Q( W3ewmahy.g%;/g.)

  1. 53bA.

_ 9ANSWEP4gQ ^ - 134 $. F' kg - g \\p\\ > ryWThoo),,n,%p y\\ /my" t fy ~- ~g ,., y.

c.

m{;n; g)7 - ' aw @d ' L - .#5336{ - .COMMENTf: s ",g - f

. .'g g# m- + , Af'ignificantly modified.

Changed stem and,di'stractors ' j ,.b,T c, & d.

Reordered choices a, b & c.

s (,)-

Q s.. 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.

>

- . D _ _ _ _ _ _ - _ _ _ _ - _ _ _ _ _

. . .m .'d Question Number: 37

  1. 5342 QUESTION:

POINT VALUE:,1,.d0 The following condil.tions exist: , A reactor trip without SI has occurred.

e The operators are. implementing EOP-1.0, Immediate e Operator,Act'i~onsPi ;% i ' Ahh$c'd5[Nohpo['$:n.j,msit ibn\\lnd'icat-ions shows that on .g y ys rf-4 i -

' , \\.s. ;.rdf rod has not fully' ins'e' ted, (D'o'n.t I r .

3 *..y g-T %% *.V;The operatora continue with the proce' dure without ,e s. , % taning act. ion concerning the stuck 'rodh t y t .,r . s Given phe conditions above, why is Emergency Beration /OT, ' requirecf'at tl. intime? VAQN W,7"A~%FN'*Q .m e be um up.q ' %; y w A.gr ?) J g jff Emergency 3boration will.soon % N'beMequired, m a.

, , .%*e a.

I followingdhe transitio Mt'6[EOP 1.1, " Reactor Trip

Recovsryff"$t/c[.a! WCw

I ' (T N, , ,. - .n e ,., . m. ~.. g ..o y . m. ~ u , . r% b.

, e shus.d6.w,,n,t,inargin is ONLf"d fpconcernQf611o.de'auat.is Mainthi.n.ing a j

  • s

. s g -,., -

j"" wingf,a :. reactor trip with RCS ( #' t e.mpe ra turet:less Gth(an f557 Fi[ and 6de cre a s i ng. =.s~ d's ^ - ft } c

o

- s - tiW W 1:- 1.-- - . [1:.$. g$$v)?C c. W At? lea.st'thr$Y c -,.. . O M. N N J# s ?eff e~ct sh,utd.o.,wn :,m,nt.ro,hrods m,u_stJb.e stuck to.*"" .ee[,co . xtent that.w - .. - t.

a . o r a t i o n.s i s s.. t o t h e r,e.rede Q p% a.rgi.n y ), SemergencyW.

n n.

-,a . requi a r . c g". t . ]$Qi@S47'downemargin wrl1 be maintainecPeven f b y 42Cpjd A hj ' d.

Adequate shdt , during h^n tinc6 inn 1'ie 1 'RCS cooldown.

,,>dd y
#

t,\\ A, %.; : q .e n .\\ s 4 "r

  1. 5342 "M~lp

' ANSWER: %

~-

/h

N 4.T (1.00)' +7,A, ~/ '; <

  1. 5342

. COMMENTS: \\ , ,,,.. .37 , Modifisd.

C,h,anged order of distractors.

. ,. .... - .> .A - EOP-1.f'only iequires Emerg. Boration if two or a.

more rods are riot' fully inserted.

, b.

Suberiticality/SDM must always be assured.

c.

Boration required from two rods.

d.

Requires analysis of intent of step and effect on .

.

_ _...... _. _. k g i + . l. S '?/j! SDM,

...

  • r

.. _ %

4 b ' s e

e

e a

.

9 ,% - @%

  • & y

- (:ww ,%'*gL. j"*\\si . 1h at 4 . . t,,p . 4f ./

tys . < . u g . -. - - .. , V %,g[ ' '

- i

.< s - - . '

( . . . , , ,% %w-ae'1 ' ww wn %m e -s

- a sw ,/'/ ~ m4 4 tsa. - $sw*gG# n a E

"r w c e

. .[4%Atlyd - [5 L'QD&W" [% %fh%{gIb O(/*'%Q n2@ Chi $%Q& .(D '#wla l%** - Mi .r-= 3;g % s' u#rubec.amc.M,,2DMi.6,, (.) wad,u.: - .mma - - .m3 . )9 ....,,... .. p)J 33h % ma O h k g g {rg@j f f,kYA ( J 7

  • ghtt-:

f ? t ? 'p~ @f )e 4, 68 ~ f ' 6$ }g li F '. 4 > ~% w-gypfr . n @W(u,- he, - 'hh $h;M E A lh! fM# . . mf %& der 3p g1 4%)F.'5$ljiif9f(O ' ' v _ s ,g.

e ~ - . . .. . ~, . ,s.

.

? '[/ nb$." h . } N As, - vp( b'"" J . s.

wg g% . Ig.

Y W ' 4... e: A;}- . . 3, t %.. V% - ,

ev ' l g . ~

. I e

J .. - r ~ ~ ____._._.im .___._,. -. - -.. _ - .. -. -. - -. .-. .. ...-......- - .... - - - - ' , / . . - . ): Question ~Numbe : 38 u.- , ,#5338L __ QUESTION:" POINT VALUE: 1.00 - j _ - . \\ 'G,1veni tlje Jfollowing: - ' .

With the plant-oper'ating at 804 power, a reactor e ' - , ': trip has occurred.

,

. . . . . . . - The Controlv' Room)))etatoks have been directed to e EOP-jfD,,l".Shs' m Geneht6r[' Tube Rupture, " for the - I a

' ptpp*io'5 fan'SGTR.'*Q[[f

r . . ,. - ' . - f.

9e ' % ^ . .. ' e: AQpi part, of. isolating' the rupttYredCS/G,' the .. . ,. , - - \\ g been adjusted from 8.40 to 8.85. associated S/G PWR RELIE ~ . .

  • '

, ., - . Which ONF 1) ofthe'followingdescribeswhy~therupt(rs S/G SG ' ' g-PWR RELIEF Setp(lpt; yis' adjustedg%, pods %p.E.~ !f -

' f [w eIdha the S/G c e[sft valves wilt open n ragays. . . . a.

En ~# " bef6Eehtk$2PfR4ELIEF,551EF6dus to watern nihiiHng the po ii - b

  1. * %J5306Nf ogenF forq PW'RR ff

.$ h h h %, - 4.Q,3 b.

AlloWsh h rh/ f s re prior to ope ing ~ ~ (f) bhe PW LIE ducee r3 mary.;to-seconday " ~i.

... V/ akage,: C

uM+ %., . Dip $h i 1 fromfo,[p[.gning, ^ " . (

.,jektsphkljRjREU ^ c.

as ru red De- .1S/$5Me,ssurefscannot%,n, crea above 1150 psiga \\' dpxtygR:aneSGTK %

Minimiz$ f , f* i

whilepre(enting-f>' ' ' y. d.

,S/GCodDSafe((jajveser.ation,fi'm opening, es PW IRE EF%cp v ' " 3 ja'. o t . . . . .. , f]\\.

  1. 5338 "

>~ ANSWER: , _/}- +& ' .

(1.00) . u

  1. 5338
CQMMENTS

y{ , u- %. Significant1yhmodified.

ReviI6dandreformattedstem.

  • Revised and'resequbncqd all choices.

Changes correct -

1 answer._ Risk-Important Operator Action _#7 (RE: TWR TG10894) .. a.- Incorrect.. S/G'PORV should open before Code ' 1 Safety _ valves.

~ '

. >

. .-

, . i * , ,.- s.sv.

--. -- eN< ,4,y e .e.-.4 w -.. -,wir---,. m E m.w wy,-r-.<<,-v-rw-cy.,.-=---u ei-n s a m es - __ _ _ . _ -.. _ _._ _ _ _._. _ _ _ - _ _ . . .

. . JS-b.

Incorrect.

Although increased ruptured S/G ' .. 'W _ pressure ill result in a reduced primary to w - _- 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 rate.

. c.- Incorrect..WOG ERG concern is to prevent lifting . - ' '. the S/G Code Safety valves, which are set at > 117 6 psig,. **", i a* PSr if0GI ERG Backg["rotf6d7""% h t..t - / ' o, y yg LA , , o'cuinedt,- for E-3 page 59_

d.

- '. "TstepDT. ' b//, i

i ' . +v ,,s.

,

,

.A . t [/ 5 . - , (v%)

D ' s . . . , n#9M/@ % ttMQif mf . < f kVN"vgY - _-.SDg-w y%3%,u$l,1f$w&rk - Gi:#:M e ebs aw MT

  1. .w.a##gT.3

- e

y \\.&t.e;w,. ve.. Ar_ < _5;:,r,,,.,sr

&gy 4[a. = 3 - w.

, 0"Y ffN$$SbhlfS$ . $[$'mm fe$^msww%? n y r yDw mW& n a w b we s f / s a g~ w :e g r%y egggy e-w,aga - w .on, <% h b kA

' g hn &ema w %an e n % g n %, qe ssa w w () - ? va un kkM$$h gg.N @$ [i $ INN '%@ ~f M

%"%p%JDgw%ar)fg., w m3 - I - ()Q

, W. va%n ed.- %~, Q9&r.IEmef&sgw n$' fn EM > % i

a wb.1n.

'cv - s - s / a.

ww (e/. ~ . . .

J

.s

  1. %

% y / - z.

NE 6,. d< * u ,a '; ?} - t ,

r Dr,(?

, T',,,,c - e"m , k..- <&_ j ' , - c ~ [P%{ ' ,

. e d

i . .

9 m -_

l ,

%'. 3 Question Number: 39 . -

. .o ~

  1. 5337 QUESTION:

POINT VALUE: 1,00 G,iven the following: ' , e A reactor trip with SI has occurred due to a SGTR onB' SG.

Thecontrplyrgom(dperatoyshavejustenteredEOP-e 41), Steam Generalo27 Tube ' Rupture, from EOP-1,0, React'of*. Trip /Safet "Ihjhc51'on/ Actuation.

^ ~ - . ,\\}* . ~ %El condition [sjareasfollows:

Plant ,%,*-)SIflowonFI-943, %,3ll /g i

. , CHG LOOP B CLD/ HOT /L.G FLOW GPM, e s .<\\ is 400 gpm,

g

r d , - t/) e PER. pressure-1350-psig4and$ decreasing ebj - / ',. DDh NuMAO65DMi[57

y%j > PZRA:evel,&30% and decreasingusiowly e + n.x wq g. p4.u.r,,[ n,..

wy. m y'

s~f.. Rupt;+bre..d!:pG;, press s.ure lpBO;, psig;.

4 ....r _ g. g , j,i e ,., .. c,,.-.,,,, ,..~ w a ,- w r w_ m.

. u.a ; p % RCS jub'cooliingion TI4.n n,e~;.99A(B)i,9A (B) TEMP 'F.i'sM35*F .% e y g h(40 i[ jpi.M.][1-E M - (/ YNY<Ql.fyl&Q.hQQ:Q.0ll$;[,-}g O l* ~Y Eei ~p f\\ Wha lt~must beklone$at thisZpointAand2Why:? M . ' M % +:-- ; ng M ze g r. b n gi fs Jh char.sgm,:n.lgrp.[i [ p; t y; d ope.r. ate > val,ves a W. ty f.t Lc { g,,1 w NSta.rt!7 (.+1 a.

i umps;:an s .m ~ y$necessaryi.andigo; toFEOP}4.2ZiSGTR with Loss %gf .- - -- . . s gra e a~ <.. . t g Subc.. led; Recovery Desired,. Reac~ti" err > Cool _an.

,c., . ,. .~ i ,. ~oo hJ Q 4 p//,n QN \\, ~ '* Stop thEtRCPssiWo@rddi ito(f' /"fy - , ,,, - b.

fprotect agains,t>*d {g .subsequ'ent core (ya' mage'if forced RCS floh/was lost

  1. ry later during a concurrent small break LOCA(

e-Ils jm Q [c^.'N Stop the RCPs in order to minimize th'e.5"RCS h" eat input '/ into the RCS, thereby helping to reddc ' ~ pressure to equilibrium with seconda[' pi essure., 7 :.. M d.

'Ds'e~ normal PZR Spray flow to rSdbce RCS pressure to s tE! ruptured S/G pressure 'to minimize . primary'to-setondary leikage.

a m

  1. 5337 ANSWER:

b.

(1.00) ,

  1. 5337 COMMENTS:

. g-- .. .

_ _ . ...._ ... _ _ __ , , . . . M Significantly modified.

Changed and reformatted stem '< ' and changed all-choices, Subcooling and PZR level air > Reference Page a.. ' minimum values so transition to EOP-4.2 is not' - ' required.

' ' . c.

RCPs are tripped to minimize heat inp,ut in other ' EOPs (ex, EOP-15.,0 ), but not in EOP-4.0.

-

  • *t o n

- . m, pc % . , d.

R.CB pr6ss,ure,. . . . . " ot rediTced until later in. procedure t afteE"'liCf h5s een ' cob 1'bd[d'own,r ~ , , . Pi W '%.) l - ' I N . y .w - , N.

- . b$k A.w. y;$$$$$$$$h; s&p&y$h $ $N .~/ 4// . g

vzwno as f ~, s y WMiWOR BWBRM m

r. m w w% w. s,.,Q:= r u. woa mo , %;% khh 13M mpa"$n 0.h. x l w w?. jfh f?

  1. %

g ssva' t.t t ,

_y ) L- . . L, h-9fiW j .... w. 4,qt s tut N 1 L W.J %y h:am+/WEq$Q2% j4,)-4

' Y.

i

thg pKP i

== . t" ) y mpa e m.

M e j + q,h e e e~n es.gqgg&Wpinga

a eg% nh y AA q % , %y % & & EV ~ F.

'$ h " r, N bh L.kbhf $,h[S'?l s,$s e q u '} } W}

  • s*

't g' ove

e

% , . vlff.\\ 0I j ' - . v\\,], . w c = " A).;~, r w . v- . - d.

. ' ' " / _f , ' , /. sv /** 'D*)? u \\ 4. ?r ,)h,4 h ( 'i f** j . , 3 g,3ns - , %,, & y .x .=' s ,

%g K
  • ,,P Q Q.
  • Q.

' .

4

. .

+

. . .m "N,4} Question Number: 40 .

  1. 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 to trip" yon niider. frequency.

' 19 pu g i ,q jp - f . .. r s ng on T&499AjB),/A(B) TEMP FF,'is >'

RCS s~ul5 coo. - . 60 h,7 %f F ' , .V ( h..tSafety Injection has been reset, butenot

, terminated.

  1. #$

W C) , A' All P'ZR heaters are off.

D ' a.

\\% ,,~=mw~~MRT? f

  1. %i t

< . ! 7* Tie 3dispat6heNrs38FEElliSt$.th'h$g$1d wi1Ig"robably Af+I reliaish.udh. table for anothirfhbur

p 9.:, w" Jr.5b g f;C""% ~3 A ?5 M N'k" ~vzy v, www s N Givsn phese conditi$r:isl;;lJ,'wh;ich@NE 5(1) fdfhth$$following is([Ne pu i prefpired method of:7refilTing tibe7PZR4whife?6cnserving reactbr cooldnt inventory aiid@s+oiiidings. t;h.e[bistSR'CS$ressure cont:fbl.: 4, 4 4 +;;;:~., L!gan, B, A x. + o qw.t

n s

.- Q), % & y y. mci. 4 ~:).

a.t-4sStop a'11EbutAONEd+(1-)ichargin;g pump / bp) Wj3d6imal Miialynip?I;EdF1htidown7 bDy 'C

and establi:sh CyclWone PZPJ PORV sashnecessa%gylgA
  1. y,_

c. ;;.y :. y "in e t L u c y'"N .ip was b. y,r Z .7;',v ~ Y y h V f! y y urs d %: .A 'ry. ! k,M h['^d.i,ately "[r.es tart.If,derik 'NfdhbdmMkdat imme- . ~ g5 g + .. CRE" A. ".w?o.r " C " and e s t,'abli sh c.

kt \\f)# normal 'PZR fiprag.\\, s s /~p $( A . - (, Lilll1 (,,,s- .Establi'sh noimjii[H WLI >l1c'hargi'ng' and auxiliary ig2R- ~. . <[# d. ..y f%(a ~'

  • <
  1. 5346 ' y//

ANSWER: n c ./ %r b./ (1.00) 7.Q t. e \\

  1. 5346

_ COMMENTS: >? , , ~$,+ , Significantlyfmodified.

Change'd stein and distractor a.

Reworded original corre'ct answer (c.) and changed answer to b.

(open DNE (1) PZR PORV).

a.

Used in EOP-4.4 for loss of PZR control but not . EOP-4.2.

b.

Requires analysis of advantages of various options to determine basis for action.

.

. . _ _ _ . . _. _ . . - . . . . ' , . .m.

r isq) c.

-RCPs not available for normal PZR spray.

RCPs . . ' would not be restarted until an engineering - evaluatioh is done and the grid stabilized.

- > -.

d.

GI'still in service.

' , . . . .

e , ., . N*z f** w ,

3 cut,-

  • d. #g vlr a*,[ t,

v (- y J' ' . . . . . .. v f,A . . n.s ' i .. )* A . ~

  1. %f %

kg) ! , ~ ' % . . . b .,),es.

- i) 'IE Ao, Ediff5E$m <sMcNg ' nk . n w- "*! tAWdTj;i f $lk".lDIAW2

n na E,! T:ditsis.v . fn mGMT u~n wse, e } [S u - j *%. y#A%ME? (e Y[50i'7 dis 2 *,s.l% eq"# @e)ffSMg i w* ~gs ~4_.w,-Ac.g ~hM7ight (f%g , .s 4w.as '. f,~.

s

- . up.hkEs-e%_w~ ppg.s- , 4@.)' m ~g ya$ws$rs.q$p$,y$OV@& (' * e& %w#JJ WKlal% $ i d- .. a :.. hh??}L@4R!!)kKE hdi?$q{va$lhh"d - %n w $y Y%ge C isie %- n

%9J$ S$43 34' N-V w% w:bnw~.o v v,<. 4y fv) .. s,. - r.

. . . N g ,, W -- ~'. %4 M & . tb

+.4 . ,, [ %

, ,i-7,w _1.

d 1 - p.

-

,,. g

.

'4..

. . , a e .. , ,. -,,- - ., ~,.

. . . 4. 9.4., Question Number: 41

  1. 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 trip.

> e*s V".: m Af ter-trd+nsitioniw,tng ttr EOP-1J.1, S/G' levels - g g %

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 '

  • '

. , . Secondary Heat Sink, the crew notesf hewfollowing: , t W (-}. x p,

'RB pressure is normal.

p.,g . ) '&% reMU"BMTOS g65

  1. 4

/

.r - n;p RCs, pre,ssureAisE2280 psig M r f Nl[ m.m(bN2'I:, h; ~~.+s en,:- m/ s

[N..J % N:S/G.!G-. ".[...EB 8.. a.n. d".<~C" ? WRiil]$evels are,21%23% - N.

p%x ~dw : 'Trespe c t ively. w;,.m (A - . no an'df221.' %,m.

- a '. p ,.. &y tyM 1'Q q.7 j* M Q,f, W CQ z% j Rv JPREccnditions 'ar.d ':*. ' % - 'W 7:gg;jj+%.;V:x;j.;,;rmaf.

efno 3"*: . taa,a t . , .c

np n

k.1 ;+A e t@;R.I. y# " ;> h EFW cannotyi n, Sw4.'f.RF,dyatSlth' f's time. qnW oCf 4.. ' '. ~.w w e N

W restore ~n

% ' QW Q- :j Why,Mb:R.M.f * $,.%i.a Given these p_l,D.lm"?;c,ondi,ti.Dd

C a .y.

u. wa rn/ w raretth~e RCPc5st opped " ~"" ant ons immediately d$d[dit> is det'e'rsined! that EFW fcSIIri'o~t be restoY5d to aerKi.de? 'g, N[' d ",jQQ(J%;pCM9~ M n \\ t %,Q a w-m... a % s -,s %, p% , k h a.

4 7:g; z ig To*' reduce RCSr.p}ressure topmprove marg.in to#DNB , , when SInflo'wfis b'atheli'shed.

f! ,,, y/, b. 'To minimize core uncovery and prevent Inade'quate %j,gb1 'v ' % @ ~~ A . 'f/ Core Cooling conditions, f* Q /f% /) t i N b'/ c/ To remove,an RCS heat input so thatsaw

. determination can be made as to whetfei or not RCS B.l.eed-and-feed will be requiredr7 _ M.

abes.

To del *'pithe need_for bl"eed-andi eed by reducing d.

a f RCS hestiinput thereby gaining time to establish a means of supplying FW to an S/G from the condensate system.

  1. 5347 ANSWER:

d.

(1.00)

.

.. _ _. _. _.. _. _ _ . - _. _. _ _. _. _ _ _ - - - - _ _ _ _. _.. _ _ _ _ _ _ _ _. . . . . . . ! I . 43)

  1. 5347:

COMMENTS: ' u

i Significa'ntly modified.

Rev' sed and reformatted stem.

! i Changed distractor b.. Resequenced choices c & d.

. . . " ' Risk-Important' Operator Action #6 (RB TWR TGiOB94) ' ' - . . , ~ . , a.

No' direct effect on RCS pressure (reducing RCS -

heatup does indirectly reduce pressure).

Reducing

' pressure,wili] redticermar, gin to DNB., '

, Bleed (dr *g p;' p p- ( "f i ,% / ) 't.

, , f i /5tt fCS'yd eed determinat o s p gde by S/G WR-leve'.. ,- c.

, , , . ' d pressure After RCP q ip, RCS pressure

. i ,, \\\\apd temperaturs are expected to. 4n, crease; crew ! . - - Q. I6ust determine if this is due to' K6ss%f hea %QorsecuringRCPs , - (ERG FR-H.1, StSp-35 pg 69).

. g Presence of RCP hcat doesn't, prevent .

  • (d %.tg Trainee 2uathyesearch &

etertaination, je C0 w & GW'nn M W 's ' dede(Si'neWha't is occurfifig%'aEE;the EUP Tor A,f*/ d. f Cqrgec - f and redlTie that . i4Wefated, / achi'oi@Qyp fg y 't IM@&MgwR,'; M# - .- N q*;M (/%) - +&%3 .4 W ,e, aqppe%m %.+r.a . $p%y$j-4ff' $4;g % - w e g:q , % W sm.

y, e$.g kne %.g $dH,g4e ~;;jgd7~ en , 7fyy h ,1 "~ . - ,,, .4% Lpa q.;W9M!p,:,pg;.ng pv 3 ,y.. q ar m ywMi n g5q Q_).

v.u a --, Y,q,9 ep y ung qvupwn.2 .r ~ - fy h $ k Y $ ' y 4 A s h M N.

(,,a %ypkg "amym 4-Mp', f,$. ~ ViG q g '

'gWy %.A %e.

, a ' ,, . ch s(k O7 [h W' ' 't i - f w-n ren c. - . a - , ,/,. . . . J d.

?' ' , 'A n . / g%y /

NT-y u . .A i., v - , ' [.. p '" , J'be, 4'I,,,( Q f L*m )pq -~

4

1

66 .

. n . , er , , ,- ~, -, - ,,,, _ - .,w.-er---- -ew--.m +,, -- -

. ' . .m $} Question Number: 42

  1. 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 levels.

EFW has been+fsol'sted-from the ruptured S/G.

~ e An,RCS'~coolBohnha)s % f '\\ G 'y.% . 9, ss s.

eendinitiated by dumping

- ,

  • isteam*f~ rom TWO (2) intact S/Go'.

. _ y~ - w A . '.

  • AM" p\\r12 permissive 4.,s o

e.

Ar buring the rapid RCS cooldown, the sm\\ Y light goes bright.

, I % . N.> .

' . The "A" RO places both STM DUtiP INTLK Swi\\ches to g'") * liYP,2NTLK ' and-cont:inues" t& dump,. steam in}tilje STM

V PR $5,i!!?um.e i(t o. M:hE " rsqtti o is c'.RCS u tie mpe r a t u,re. mod f

,f Ir u ~ - - 1 o h. A,m. -- ?, '!- % Nl,, '1 N) M ThelNROATC?neg;lects to, block 'the[steamline SI.

/

['% Prior,.' u

.. t u s
r <

u , . - (es ,.g u - p t r; p > ~

"',
to /completitig? the,ncooldlow,, n, the SE reports q%

/'sPORV(injcyclin5p.that7thelplant/is Q gcup and the ruptured;SG heatin ~ yj ""' () ' " ' ' .m'3 s.JA (m 9. 3, J/M.,, " J h-%) eYITliefc11ow'i'ngTcoNdEl'nEexi"stI.'k.j C[ s - .~-, ' E t s ;o ~ c%. #j 'g :w'.'7 w .n n p .. +'., if n p p,c.1+ ',n pyy .,;2 \\.jy-'/t-RCS cubc[ooli;g.is 40*F. [I [, @/ q .%_

e f,,"

r-v ~ ( )g 'AyAijavg'fis7522F Mi ;x /"$ M \\ ~3;>;i$Rdptsfed?fS/Gj pge'soufeTir 1130 psig. % ' hv S I s f 3 cw pi s'(4,000gpm., -4.; / py

- g ',,, - Con'deriser'/vacuumi ont PI-3 006 (3 016 ), NAIN A (B) PR'ESS INCHES 2HG', \\.,",,,,a.

~ 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? " I ' ..y. w < /

,,s a.

, Loss of condenser vacuum.

N , t- ,x b.

^TE5 MS.IVs are closed.

.%, Y.

. 3,

, .. , - c.

The RCPs'were'[ rip' ped as required at 1400 psig RCS '~ pressure.

d.

SI has automatically reinitiated on low steamline pressure on the TWO (2) intact S/Gs.

_

  1. 534B ANSWER:

'

. .. n --

._ _ . - . . _... _ _ _ -. . . . . . , i ' I e ' Aj) b.

(1.00) . .-

  1. 5348 COMNENTS:'

i . Significantly modified.

The stem has

choices a, b t. c.have been revised an,been revised And ' ' d reordered.- . - i ' Risk.-Im,6ortant Operator Action #7 (RE: TWR TG10894) '

a.

Incorrect yG4verd' valve of' main condenser pressure ' ' ' ishless tbaffC-9[periniseTve,(5" Hg abs). , (Co(rr,e(cti ' fit %* Cf / / f

, - . - ,, , , , .. , b.

MSIV Isol. on Lo' steam pressure without - . I . \\pfo'ckingit'at552*F.

' \\gdg% ' ' ,\\ Incorrect.

. i f . , . o RCPu are not tripped on rapid . cooldown, and condenser cool _down can (still be '

. ' ytili' zed without RCPs.-

  • h#

' N;A f5E'IEITGepO N 7 ~ ' Iqcorrect. p-49preventstAuttsydIgifnreinit at[on, and /[ d.

OP - SI!?slibbfd3h.6f,p cool the7RCSiNBF " i ~ - nue inwm ,, f.... h h j,, 7=s.a[$. i r%% W ','*.dh'.. [ Ajf fl%

?

.dl{f@s'A t%@;.af " Q.y .n.

<,

.. .

  • "*'f QTT

.a % ~ a-e % %..jf, '*"* % ;.. ' " VW ",b / i % (;,:: M W ; # n.4g m;.,. b *.$'y h T W {g\\

& gum s 5.p %. $ o% " M* M a * f j $ g[ y.:.1tu r.s*chy a& a.a.

W a# ~ h.n.' a ,v..M i y43.y

I $ $ i j;d A M Ay .M i $! L (f) M d F %n?,4%. +w j

  1. '

t a, , . .

s,a f 'kh.g -

'? 5) f,, o g'i., f. m.w m,h, & .g a&&g p c

c r %.6 f

  1. ..N N*: 't

s

k%.es94 ##f4 :}Of'%N.., &lgNj Q\\

Ap

b,p.

- j t- .If!.@;.y/[Ihqw\\\\;JIiO cn # . // t-s ', ~ . . . . .t,n.

~- . s d.

, . l fi /. w .

Q s + . sA s s [ p> . F,i

%A .

  • ,;*

f f ,a .a' .

    • _<

ge 5 ~ 'r=.)

.

.'m.-*' ..

'

.

I . _= '.. m 8, - w y .- ., - -, -

_ - - _ _ _ _ _ _ _ - _ _ . _..- . __ , . . .m . , *i..Q Question Number: 43

.C '

  1. 5350 QUESTION:'

POINT VALUE: 1.00 The Control Room operators are responding to a small break LObA whe'n they identify a red path on the' integrity status tree for - Response to Imminent Pressurized Thermal Shock."

EOP-16.0, a After verifying adequate subcooling and RVLIS level, the crew ' establishes normal charging.

' O ' UYJ f.T . ' TheseactionsindOgdi6fl>g5wereperform6htoachieve'whichONE (1) . e,,J ' ' ~~' b d / / / ', * " ,ofthefollowing:(y,(lowuseofauxiliaryspr$yitdtheeventtha - ~s / . a.3 Jh al I ' .. RCPs cannot be used during RCS deprps'surization.

d Reduce unnecessary injection flow bec/ % .

D.

aud aubsequent minimum values for subcooll'5 [e . . ' ' Will be r,) . %/' 1%er thari ormairSI*teh ina'tio driter as.d - , "3 d p:ufetWM21%p--- "/ h,. c.. R uc.of s%u. sequent RVLIS,mi.,'rhro.5 Or

, .y/ f . y, i , ~~ a w m nimum;. level requirements and@herebf4 allopRCP rlj.stytij'6 equalize s _3tem temperaturec,b'( E $%$mMNw i i e" y [* DN$ f~

< EliminathtSIflow.

. felim'iYnatibTthe*pEis_as_ so'urceFof' RCS cooldowrfAhd to d.

ibi10'yfofeSI causing subsecluent .q I""' ' Tih$$" Y$y$ h h[fA/dfd "(~ CO t D/ ANSWER: %j y

  1. 5350 g W

c

!\\ rd d.

J '..L {h N@N" sy #Udhyl % ""%,y Modified by'N %ling'distractors.

,f k s 2) 00' ' ***"' - ~ \\. resequene.

. .

g,. y.. . ..,/ a. . Auxiliary spray would be available eyeliNif SI flow ' g/ } still existed.

/ / w. b.

. 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 " ,.., ~ c.

This tests examinde knowl'ddge on the basis of RVLIS requirementfs of step 3 3, immediately after normal charging is established.

RVLIS level requirements are based solely on RCP status to ' equate to 50% void. content, d.

Correct - The examinee must first establish the fact that normal charging means SI is terminated , ~ ,

. % . . -

_ . - - - - - -

_ _. _. .. _.. _ _. __._.___ _ _ _..__._.

__ _ l . . . . . > , . - , , .

.

l M and then evaluate the conditions that EOP-16.0 is Y trying to establish by stopping cooldown and ! preventing repressurization.

. . .

t

  • 9 e

f

. . , '

. . , , ' , t $ $ gg

  • '

( [ . ' '4

, v CJr \\,v ,

. - - - ~ . .. . .

.

. l y ^o.

. . . . ([%

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. e , ()h ' ' R* ^ ' ' . , . .. , N '

  • %w%g;WGwatuaEMB%nd

,

' - d~i uo.n-a-eam, w . ., A b p* . a

wan no 4-ak s,,v %f gk* n&-

v:n < w%$ y-) 1FGQE-g -" #v$19?'*'PdyN5$#N9E

S 20 qY

  1. M.1-:

EN C:q% W MQ %W:@pq+ Q

1 yi / n,, > c%m.rai..ymw.- y s =r a n& pn Q,w 4 'Ylf [[A h+q,pu n.2 7 0?h., f &r, / g > y,,,f gsw yw).

. - , m

w,)

o e m.apy $w e[h&,hh?h,

l *.

, ) - 1, a 4..c.

, /p en # u.

_s g,g,,, + 7 h[yhfS AhigI hh4 g e y% (f, A,' M %g e; s i k - s h '

su s &< kos(>1i (JT ' ' v, .. r/, v. w - . J.

. . . v.

, f - < . - , ' A Y r s , ,% . ,% p..* . d s ',r* sL . . %*. .# 'w. A y . [ ' f , o. s ? s

  • $-{.

., y . -s , [*$ ' . .

44, " 4.

9 s .1

- i

. p : b l' E - , .. . -. -.. - - - - - -.. -, - -,. - .. - . . ~,. -. - . .~.- ..,,-,......... -~I -

._ - - - . -

. - -_

-. _ _ - - _ - _ _. _. - _. _ -. _.

. - . t . , m X.)

Question Number: 44

. '

  1. 5092 QUESTION:

POINT VALUE: 1.00 ' . . The control room operators -are responding to a. reactor trip.

.

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 power.

~ 'Cohsideringthe'conditionsfjustfdhscrikd,whichofthe-following ' . explains why the.fpredhutA mo' e Ts)pi'irfsrfec1' over the T., mode for d .condensersteam,dumpi$obtr61."

"' b/ f '

- - .. tsv , - .. t s . . a.. AS.Jeam pressure mode does not requir gseparate.

- - ,, \\. arming signal to operate the steam' dumps.

' . , eq . . , N.

The pressure control mode gives moreIp,rgelse - , . . control of S/G pressure and therefore dg W e m'KE E R M - A ' . g ,. pd Thkiteam pressure +modh@p@rovidesjextra pr,q[ec '

' c.

adagnsjQxE6ssivecoolpf,n% ' f , d.

Theh p'1km 'ew$iihhbiuallybe'disMiled b whenMWt'emperat(Ebi.y e +F~i[n:, e Y gbe bs160 552*F.

%f % w m. w.: / g pu h, MEhinJWds%mp.dhli 87 Q.

id}y&Mhr4 W D(y M % vg d.h W G

. m c.... (I.

qm,w g,yyy m.% s ' ' 'e : r.. 2g (hiNgF(Y ? ' .-(77 ,f S Ni ANSWERh%$3da @4G '

  1. 5D 2

- . iil ' - .

h

  1. 5 c

. Modified by yesequenca.n W stractors and replaced kg.j distractor d9 '-@j)tM 7' _ " (Q . . v.

,. ye . d,"//f ' a.

No advantage seen here.

~/N ' br# Correct - Under the range of normal,ySfG pressure, .

.a large pressure change effects'a relatively a jothaller temperature change (Taig7.- T SAT for S/G) therefpre finer control pf TaVgf s available by i pressurM controR and also7 control rods are not in controf%fTavg.[ W c.

Provides no more protection than Tavg mode.

+ d.

Steam dumps will be temporarily closed as temperature drops below 552*F, but they will reopen as soon as BYP INTLK is selected.

. s.

J' . .

.. *

--_ .,, ~., , .- ..y -*

. . . . . . s%;U Requires comprehension of the basis for selection'of

, . steam pressure mode and the characteristics and uses of ' that mode.

' ' - . . .

, a . . , " ' . , f

. . , ,

,

e '

g Tfh>.k<v l 7.i. h"'"'t -

s

  • d 9

..r.i, - s sf t , / .

  • s

' ' f jf . ., . . /y ....

., . g . . ~1*. '

'

' %.gf y . ,). _ ' . , n , . . . . '

y' , , h O ' igx 'gssssag84; h-4/ .. w a o --,h,em . w' f'e@hf,5I ' m ..mwa w . IS%kbj[" [ i 9, lk Mfff

  1. h0kI h

kh 4 s % rum a m$g;ue[> 7 >,

s t~ . --.

,e.,

- b hq.jhk $!hyfkk hh3 rh u yy wn l' % I ,. 4

e% #g@)g %$lbf ~;allj.t4l14,y ' %. g- ' k

  1. s

$y t t r .%

j 4*

v- + . vbAr

g j- . . g,/. . m.

. ,,< . .. - v/.) %v( - . , '$ ) y>1 - % . , .

T% '~4 e'yi n . r~Q ~ h (

4 t' y 4 6

72

0

6

  • Y)

) _

. _ _ - - . .. _ _ , , ' ! l

] Question Number: 45 l ' . !

  1. 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:

' - , - , ' q py f: * % !

To is 430'F RdS su6cooligls 508} "' h / . .' '

. S6 acto [cotilant pump A is friserdieg/fl ' '. '

  • '

- . . (Tfie PZR heater control switches are in ths*,DFPpo , , PZR 16 vel is below the indicating range:. 4, l

y . !

' Charging pumps A and B are running in the Inje,c', Ion mode.

!

    • -

p y . . . eIts th perator to.r'efill the pressurizer byJ epressurizing)h@pCS , '

' The CRppl(l spra'y i ~ f k.. %ghiEgfg Qwill thisiction reqditJn the ..L ance<w ' using gorrna

) - $![fy pressilrizer being refi e i ,, I N .M f ( R S)will expand [$t @wer pressure ~ . . D. % N a.

The water; intolh'e PENE " / lowereRCS pressure:n&g:?.p.X{nw hE \\ ~ 77" . % M tg y .ru f , PZRf'fdiHISijydEDK{ d; incre e S efill,n)g i_ b.

. , will

M.g i

i , y:gyf {j h.' ' . (}) " '""" hyg g gr j ow will force" 7ater into theTZR

, c.

. cou lator etiortADd

ML ? dsf' % M h%_ howet ' RCS pressur.wilCi'% gHR/SI flow, refilling the Yh d.

ni i i PZR fro H SJ , , i . , . , #5356 \\ ANSWER: % "

' \\ ' f} (1.00) - , n\\v / .

  1. 5356 COMMENTS:

,, kE' di r , Significantly modifipd from (093 & 439s, Change'd stem and original'

... distractor b. Also exchanged' choices b & d.

- .m . a.

_ Negligible magnitude. RCS fluid is subcooled and is relatively j Incompressible.

! . b.

. Incorrect - RCS pressure drop will reduce break flow as well as increase injection flow to create conditions for refill; however l ,

  • w.

,

. . . - _ ) , .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 max.

.' - , e mp, Wit T' Is t.-d Pr> . Q **.,$s 430*E, pressu e.can/> .i - ' gs d.

"t. b enough.to inject ' ' no RAB (// '

- '

  • .

%

. \\s.. ,, . / 'N , % ' . ' gf., g w w. ~ s ~n y,N &a g,, e <,4 %e ' ' C . %n . e-w i ,4 %/ ,,% ... u A c A.

O m\\p:,13,gg:;% :[ fMWy:'n % gu f %, c, n 3 n. W p&'L' t Oo 4 9 c-rc ~ ype c.,a(e Ql%* u<';*a %jiyl

x 7%.

s-n: - >- Y f M f)** N W r;'r'W'i:r A & A, " g ,,pd [9 7) j&'$g/bydT@fpgjid[;)/ ~~~'"Q.)jE -:l,j?,!;f{Q Ur g% , h {=, %Ih.r/f.n,jl . fl _ pu,

f a} ,te , wa,l y es pw Ok.Qy;p$e$;wwn-Q Q htQgQ 7., 3p f.

<, gg{gf A > wie pp v., y y it .%

  • f

!

  1. !

mygh;i n g, ) p

g$yn&s, s m&.a Gm e,. m.yij

+e " av w.

, &W Qt*%2 ezy % \\ \\b %w ~ m, n s.~i - sm - n. t $1 u .s s

t .:n s g

'** I p.

\\

' @* y/ t /

( /,o

d' ' y#if / i . . >. r.

. . g% //p . ~te\\ v,).

  • % pr

- s f

N4 \\ ,,, J. %,

,.~t y

.t ., 5,( * ,%.4 + ..k, C..; >.y' r t..- i.. p'dx

,, l -

. . .

w __

- .. . - . . . . .() ' - Question Number: 46 , - . .

  1. 5097 QUESTION:

POINT VALUE:100 } The following conditions existed::

, ..

. . . ' The plant was in MODE 3.

-

+ VCT level was stable p1.30%. ' ' . ,. ' ' level gasIt'Able at $5'9."'hs[. P - >*- . " - Leto$e.flpas110s gpm.

'.

-+ . . ., , , f % , , , ,.

- v a . as begurilAW AOP-106.1, Emerg'innpy$jN ' " '

5 An ernergency bo oration

" , h. Fl;110, EMERG BORATE,' reads 75'gpm - '

' . . . A Assume PZR level remains constant.-

. Predi ehavior Jevel, 16jii(Tu ct s$ ken.

' ' a.

Increa T.

f valve-d? I - m.,$? % '

gg g <\\ u.

t WullTdhe . ( b.

Increi$rs. 11.TCVf yu I el&twe-20 and 40 libI ' wdnLe c. e co ~. . c wm e ncreases, t on:. ola,s atesorpe'sYel be - 0 70 and 80 d.

, '

  1. 509

,, ,,,, , . (1.00) 7* - - .- .

  1. 5097 COMMENTS:

s Modifiddty resequencing distractors.

g, c.f.y %f~ .x . Requires apply,T6d:CVCS system know} edge to unusual situation ' ' y g.g . t,..~ . a.

VCT level will not increase high enough to lift the relief due to -.

LCV-115A modulation and check valve keeping emergency

. boration out of VCT.

- . b.

TCV-143 will NOT divert under'these conditions.

.@. - , . ..y . _ esos * .

h g ' ~ ' .. , _

.- . , , { .- - . , , ,

- , .,

! M" c.

20-40% is normal makeup _ band; additional flow from letdown will . - cause level to continue increasing.

,.

d.

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 leakoff.

' ' - ' . ', 90 + 24 = total, charging, pump flow of 114 gpm, which balances, ! . , ,. , with,tio,n of{75. gpts Is es ablishVCT leidog3+ sea 'i - l skgprqylli tome from the VCT #,ed;on bo{a ! . - thh.144oing into the VCT and'- . .' " ' - , 9'gpm coming out of VCT, VCT level { vill.jncJesse until 70% at

I' . !. Q which time LCV 115A will begin to direct, it wi l ' h until flow into VCT = 30 gpm. There, it will turn,ljanod ..i , ' l - i % seal returh + 30 gpm into VCT = 39 coming fromNGT s~ its

.i '. . g@iribution to tot $chqgigg)gtCV 115 wijlpodulate ": '

CT level - .' at olgt whTrIs theleJsla tiilihd5 bet 4een letdoW nio VCT

/ (+Is$$p]5PM[6sv) and the fIo%gbliigiihtyhe c . . / 1 etiirn - (' suc't16h' - f. -c~,} ' I.YND-

- t & l%%UlW k.} Q '

g o. /, ? * b $ $ %g $ l -- . .f.4 --- ~ . > .hh< ykpiz;. ' ns W"45*hvu li,h> 3(;; @ Vgr [SpN A ' !. 9% < . ca sugkllfff;I2h s \\f ' gr - . .. // v.. . . <. .. , + }} hf ' v z._m.

, .

W

Y,=- ,. 7g,b ..,...L, ./,4 , - . , JN - , l % < ! ' ' , ! ^^ (.. . u,t - "

' . ,

. '. l

n

,.,,.i + s. n~

,--u.. ,,~ .N -.. - -.. -, '

__ __ - _. _ _ _ _ _ _ _ _ _ _. _. _ - -' . . , ,

. , %) Question Number: 47 ' ~ j . ,

  1. 5354 GUESTION:

POINT VALUE: 1 OQ ' Given the following: ' . . The crew has completed actions in EOP-4.0 for a SGTR on "A" ' - . ', SG.

. . mn . . ThN'C[S tfahsbons t h0PMh ' RCS c'ooldown to Cold Shutdown!afdp/ as the ARO establish an'. ' . ' %c

-

- v" "

Qg

- . . , .Q ' note in EOP-4.1A states that a ruptured S/G,skould be refilled ' , . to 74% apd allowed to decrease to v0% before r ng.

, . , , Which 09E (1) of. thetfollowing desgh@s thged@N;for<allow p ribe ases . betweerithese valueY$ 4 Qp% Af%274? fi ddh*

  1. [

MS ti CAS% subs %g%e11evel to_ drop to 3088belore'rsfilling e C* Allo a.

-

setp61ntQ(MdO filf%ill'n'dt'ptessu[W:lis"de'6d W MQ@ Q)K % llow$ h? Y B fi$ N N,hk? N E(bCh - -.o - J b., toycrgs,e to)Y! rapid' pressure decrease!8 74% tiefo[e draining assdres id$dwate;thei " ing h-a rydh,e n f6mrevent

oddensation$y(! ' I $ II[f!F p'Q[ (3 ei ktc k$h ru'p'[d ed

/G aids in co~o of c, \\ tlEiystal 5'tM4~5r ~'l[75fS/GV (NO, %(~ ! Qj Allowing i e leve ol(lc - the ruptured S/G prevenStpe [/.fpl .d.. - ' 0- . formation of a therina tiarrier between water and stelim. -

. '. ,,m j/ ' .

  1. 5354

) ANSWER: , N,x.w - .e . tj4 (1.00) v c.

~\\f . 4.( . ,,

  1. 5354 COMME'NTS:

h.:

.m x7 n . pq - Modified by resequencing choices, a.

Incorrect because part of the basis for the hiah limit is to ensure that the fill is stopped prior to lifting the PWR RELIEF.

,

b.

Incorrect because the purpose of stopping at 74% is to prevent , .. 'f

,

4

.---m w,, ,,~,----.-.r --+-.,,,r ~,v- -e -.,.-rw.r,m, ,m-,------.- -,r.-,.,.w,, ,-.,,,,w--,,..m.,---y---w,,w.w .,, - m-, - -, .-- -

. _.

- - . - _ - _ _ ~. -. _. - - . - - - - -.. - - 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 condensation.

. . . . c.

Correct. ERG background cortains actions to cycle level to cool - + - . metalin upper'SG.

' . . . , s a 4/ s

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. ,~ ' M.., Question N;mber: 48

  1. 5137 QUESTION:

POINT VALUE: 1.00 The,following plant conditions exist:

A waste gas decay tank release was in progress.

  • RM-A10 Waste Gas Rischarge Radiation Monitor, is

in.,. service. Q b,,) ' - -u . g . IS\\i t 1 3 1 %.i

s, % ", WASTE, GAS DISCHARGE 1[I'RADIA'rJON" annunciator ."

- . received.

'"' ' # %,. ,4, . . ,\\ v; .m \\ . *\\ JHCV-014, Vent Stack Hand Control Va19'& h " /"\\ as > Q tripped closed.

{ \\;, bb . . TheCountRoomhasperformedabackupsamp}le (,%* aniilysis opthirsEstbggssidecayetgnk.

/ ' ) i[t % y > %, 63 W"~~~WP % m A Me%3sljasy" permit has$,.. ~"U.een M 5ued, and approval

  • ff%,

hasi@een;grantedrto,res'ume2th':delease.

e /,,.g i j .J,u. Q W -.t V '; ',- %

ey; n

f 4 -,.... _ - +

,. g Whi"cli..e of thif followingris4(arejf thelMINIMUM actiod'(s')k , ,,, (1) to

takeJ,ONE (VentiStackeHandsControl; Valve) in ordereto or HCV-014 contiinue the wkste g' asireie'a'sh'?D 9 O[R ]dVit Ii[ /M V

Ql:

% 3:7 t.q"'?; ; yX,Qi, ~33 all. Cit to % , a..t TReset thsivalvepocallyaan' o t.3f-/ CC" pnut.ioniatic'All[g y e.-hp[eh'e # Q re p ,.~ s,, e }t p u., ,,#yf,;,,.! y;, e. y ,p .n .. y be b.

LTalic;etheivblVe,? cont' roll, r to;ZERO (0), ther'% .c..z .... - e i'e - . NJ1P,8 /g\\ cip,esth'# valvc^.' y'{l'iPurge tfie reiea'ls}h; .fT (/y ' f f,Q'j y '\\ ' ne with nitrogen until'RM-A10 t.# c.

\\,/ returns 'to uh'ckg'ro'und, reset the valve'locilly, . - f'[, then re-open the valve, p[ a .- "./ x -

-3 ., tI T Place the RMA10-INTERLOCK Switch in ON,vand then . / take the controller to ZERO (0),. thendr> open the svalve.

\\ ,,,,

  1. , a

.P ~

  1. 5137 ANSWER':

y. /,

)'

-% ~., , b.

(1.00) ,4

  1. 5137 COMMENTS:

Modified from Question #1815.

b.

Correct.

Per SOP-119, the controller must be adjusted to zero.

The selector switch does not

.

. - _. _ - - _ _ _. _ _... . _ _. _ _. _.. _. , ! ' . '

- , i . M have to be changed.

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- . _. - - m %) Question Number: 49

  1. 5138 QUESTION:

POINT VALUE: 1,00 , The following plant conditions exist .

  • Waste Monitor Tank (WMT) #1 is sampled and ready

. for discharge to Penstocks.

  • RM-L5 'and Rpo'E. 9 I'c but of service.
  • ~

.g ei is. ~, p g s Fa,irfdT*1 bhdro s'bi*ing Us (to increase level in* e . , .s( "*"" """""" '"' ' '.. ~ ,o' g

g

-

. . .%$ s*G.yTwo qualified st.af f members have rey 1'ewed the

, Q release rate calculations and disch'argh)-line A valving.

(., . , , Based'o1 thesNLeonditionsr M M S 2p2 d p @ J theMA9WMTTif3y bedeleas d j ' prov{ Bed'T '@,?h,, Q7 (4, ,,Q *) .;;;m +. +:

-

.e ElihEd[m$5f.qt;RM-L9 iIi'ebY;oF[d to operability - a.

,

"" pridrft'o'iYeleaseT ! fd Wf /T" u. ;.. - ,QGM. u, ' ' ' ... * >/ (^<; L'. 's ! y% b.

Both!RMfL5i;andQUhL9, are rentored to operability

,]N l'"'

/,'priof.ibfiele'aseliC12,6_:^ ' f* b" , . b 'd bk *.i e 'b ^%;hu[ ds c.% The,Fadrfieid"IIfdroWg.\\ Sj' 'ing,;]yith two C,,i,p ( "'* '>v enerat .s Mindb'p;ende'nt dastld[ro? W. pied (plog/ to re1 i il'ed 'a'nal \\lW.W .02 k & P f\\ modeiwith M 05 aJd J PM9;i}nl ids current e, 'The:qFilrficid!Hy a d.

stays ope' rating bw}

i ' k,\\ prior to relea'seTgW $>g w "restoredtoop{e M ,r i

,,, y w l;iu {. s v.

i e,~ ,. ~ \\ .s - u,/n , . <

  1. 5138 #.,.fyANSWER:

i'

  • '

[(o(%

  • j,p g
  • A f.S (1. 0 0)'

} s -, ,e ~q

  1. 5138 COMMENTS:

\\

~.

' 4, >, g,. a Significantly., modified from Questionft962.

Changed . stem, correctranswerJand choice d.

Resequenced choices b & c.

i '

,0,: a.

Incorrect.

Release discharge valve interlocked with Fairfield Hydro in " Generating" mode, b.

Incorrect.

Don't need both RML 5 & 9.

c.

Correct.

Fairfield Rydro " Generating" mode and -

9 .

  • -

-.,

_ . . . _.. ______.__.__.___.__________________m._ . ., . - , ,

t , ! -m R,.j) per ODCM*1.1.1.1 requiren.ents and IAW sop-108, ATT l , VA, page 2 of 3.

~ d.

Incorrect.

Don't need both RML 5 & 9.

.

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. ,

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T . $ Question Number: 50 ~

  1. 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 assumption.

' , , DNbR c~oulhgo low e achde[Et.be*cause Tavg is oUtside):thpjecid ign imit during $ subsequent a, . '

- > >- - e ' ! ' 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 ' irGTsased due%y tdTNiTal'Hiiitt]eW~ f6deEreagey.7/ , . ' ' / /- O nd h a9 mW ' p %.g dm

s

,,,, I d.

The'DNBRehas increased, becabse Cr ical Heat Flux has , r . ' N increissd%%to' aitiTal. Teat fl0Elli$5aie.

' b?~- -

en'N y W Pfi! g . Waggjv&g&##l (%y. bJghRS{a-A- . hg g e % c} vpf , p Q }g .. - ~, fe - ,

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  1. 5%

h {if] { AN , O-a. jfggkg, e)g g % w[p - %

  1. 5104g up SJe- -

' l } ? ,- p .

.00 Lu m g - ~s

COMMENTS: '$r, h l 4i h' . V 9t g-g,' t~ . 4..* / $ Modified by resec[uencin. h ces.

d . j , & . \\ i . /) hs ' Correct - Requires trainee to recall Tm Lirnitf at then calculate actual T,vo based on programme (onhTech Spe 'd 100% power, c

  1. ~y" '

4i b.- Non-conse,rvative assumption v(hen violati,ng T/S ' Aj~ .pp % . c,d.

Temp t decreases m. Margin to DNB (i.e., CHF 4)

a .- h . .' g

. $. +. , -, - ,1 s.

l r.

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.- __ _ - - - -._ .- . - - - . -Q Question Number: 51 . . ,

  1. 5110 QUESTION:

POINT VALUE: 1AQ , ' Given the'following conditions: ' The plant is at 50% power, MOL, holding at 50% due to chemistry ' + concerns.

. arg in AU f76.f," r g A Coptrol, rods'fbine'is dn thellrhiter. I + - . Ttie Main + PTVjprT rbine impulse PressITIE,ffall cf'ow.

' ' ' + - k /the time the instrument failure is lderitifie(a'n(rods '

i N MANUAL, the resultant Tave - Tref mismathhos.3'F.

. . The CRS directs the NROATC to match Tave witti' Tref.

A V , The PT(f46 failure,(Q)S%g . ' ar d the resultant,.gonttoj,,@r,od motion, has. had /

effect on e FDM M ,ig:w!? y %n 'did @ aD e### Shutdown * Margin? . L, !; ,,f pp J' & e initially.increa,w y u + decreases.

w.

. t. ses then' s a.

Sh tdow,imar - i% Shutdown:m:sd ~w%,.e.}argin has' decrease % :ad. a

,? +m w; _ ? W.a v.~ w ';:i (*~ y s'a N,h b.

c5 %* r w,qq.

J.a y~ e,Shutdo(K b ny.n n?Yy:grem-:. q ,

j~ ..m w $ c.

wn margin h"as re d thrysam,e,.-7 j.,t> "- d. *% A MJShutdown m.Nh.37,qm@.m.aine (d t . y3 .n p

y 3,.gm

, ,yyd'. M..?-W /? k %,. argin has creasedP' s'IW~7 ~s p-

Qr q x fr itln

" g % e,ijfb? &

wmm:0 usau Qw%c.

w+ < s 2:a.

N') ' '&,. x,e.,-. ,i's A . .n @ h%1Q.y % KpGh M e -v! k.[ O '

  1. 511 ANSWER:

s,,.,r . c.s %.g y - - .' (j-g ,,.. % *y.

, ., c.

(1.00) v- - ,AfdMMENTS: em q~hs '

  1. 5110

/ ~e Significantly modified Changed stem and distractor d'.' Also changed order of.bhoices., y ., , . R T.% ... s.... ' ' Answers a,b, a,nd d can be shown to be' incorrect as the reactivity from rod withdrawalis balanced by change in Tavg.

. . I B4 .. e

_.-.-,i,---

- - - --. - - - - - - _ - -. - .- . .m NJ) Question Number: 52

  1. 5111 QUESTIONI POINT VALUE:,100

. Given the following: The reactor trips from 100% power without Si at 1315.

. - - The control room operators take actions IAW the appropriate '. . pr.o. pedures a,n(6_btalElfieI,6 quired plant / system / component ' - .. . ., resportses.

Ot yj . .., ' At'1,350ra control room operat f bheck's'the NIS instrumentation.

, , ' . - . ),- s.&. . . M> The SR high flux trips are still blocked.

(['g

e R power is 10 % on both channels.

,

. ,p\\

wg . Which 08Eg(1) of the following describes the status,of. nuclear flux for th'eso @h

  • "

a.

IR heutron flutis as expected /but Oie:SR trip should huve !(*

yY reinstat6d 69EoW(1350);.5 KW A ('# i on flux decreasejis a\\*M, g.. -'3;vd

.:ui*~

L v* s.

f~,W b.

,1 Neutr,%.

h . L ,s ~, - ~ p., g s expecte'd for SR trip reinstatement at O.)

Tapprokfrh6tel.33'555dM ~ :v %'# ' v (. . ? O r k.M W W % " 1 c. Nlh p " low . h,.' c~}i Y 'Q::M ::~ a . eutron fldfislatinor;f QM R ip'sM,for thispgint In' time. At tl A Dpfeseni.startup16td, plall j% p*B

t e 'h1405%u7g?g, ym% probabl/$t reinitia vill h*,) 9A N GW

z.q;,.

.g;p y.

% ,,f b d.

Neutron flux is'abn,or,r.c.ariall shigh.forithis point in time. sR trips ,, . . [\\,e. .should ha'v'o re' ins' tite'di.t:al5proilrhately 1335.

V,[ " , - .. - ,,l,. . . ,

fe. % V,,e w Qs v$ sy .- j e 3,,A M i z. a. >

y ' *

_.

  1. 5111 ANSWE,RS

' .. ~ z ~

- ' d.

(1.00) '#5111 COMMENTS: Significantly modified. Reworded and reformatted stem. Changed all 4 times in distractors. Original time of 1405 is NOW a distractor.

. . . e: - g ._ , . -.. -.. _,, -

._ _ _ . . , . .

' .

x..j*) Changed answer. Removed YES/NO from choices. Changed order of l . r.hoices.

' . a. & b. Not nor' mal.

. . . . . . . Ind,icated flux is biqh, not' low.

. c.

. , Correct - 10' to - 104 'd.

  • )B.to g'et t, ~Kl7.5IS,J-5 decades x 3 min /deeade

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_ .. . , ,

I . . . r ' m t Mj) Question Number: 53.

. r .- '

  1. 5113 QUESTION:

POINT VALUE: LQ.Q , , - t . The following have occurred or currently exist: l ' . . ' Thd plant has experienced a LOCA from 100% power.

'

' The ECCS is now opgating in the cold leg recirculation mode.

, ! ' xit Tp.,QtableIst afproxirp/ y 35 psig.,

atel , RCy p ' Core e,ressutaret260'Fl L.m Q(./ +

. ' ' ' Sd:.gre'ssure is 200 psig.

. + - . . ' ' . \\j' %d , ' Given those c6n.ditions, what is the core heat removal mechan'sm?)* , W .

< . ' %a.

Injection water being bolled off in the core and sfe% l - .

ain, ndensing i .

  • Y'

" ** y rg g g![ 8 g ji g

  • k*/. b.

. , H ransfer-een the RdS'and'$e;REfcooling sys eihs t % (spia"!S,h'dM.s, C'. r-.. w,en hp A M U52T8 I - ca , W. $$lQ oi water fr6ip,~the'.r$I0$[bh kwt The liijectl6n& & \\ , m.,m c.

ec rculation sump and th'eh, k . removalMfisiearp/watercout.6,f[tiVe;bie'sk.

~ )

u.,

I v mm - ww w gy ^m i,~ m q., yJ l upp n A.4 my ' ' < d. * - t trarisfehb eett SCS IbbfationtoM ' i ! ; -lI F;an the$/Gs due to naturs1 @' , " %vw9 < N; g/j ), fj i N M.

, ' '

f .! kY .. (f \\ \\^sv

  1. 5113 /. NSWER:

' - g)- . . t '- .

A) (1.00) %,,. % " . #5113 - COMME @TS: % mf' %.A.

. . ' Significantly modiIied - Changed wordiIig#and viives in stem and original distractois b. & c. jAlso changed order of distractors.

' .a.

Sufficient subcooling exists to prevent core boiling.

, - , b. - RBCUs and spray cool RB but have little direct impact on core decay heat removal.

,

87 ' i ! . . ! ' -. . - - - - - 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' +- T- +=17au's%ye4 --gr.

-ywe'*;le-p.1-cyup-gy--r--

..___..-_-- _ _ _. _ .. _ _.... - - _ -. _ _ . _ _... _, _ _, _. _ _.. .- - . . - . . ! - i '

,, sg') c.

Per ERG Background - Requires trainee to evaluate core ' ' conditions to determine correct answer.

d.

S/G heat' removal not' indicated because TSAT RCS < TSAT S/G . . . ,

e ,

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.-..-_____._____________; . ___. __ _._ - [ , . I ' . t ' ! m i ,a A Question Number: 54

w t . t . l

  1. 5114 QUESTION:

POINT VALUE: jaQ , . . . , j Given the following:

, ., , ' I The plant is operating at 100% steady state power during B1 - .

Maintenance Week.

- The(Plap of-thei@ay INIgdis.'a maintenance activity o , . ' ' ~ ' . ' L Qi/ f ~ Charger,XE:C4 B. L 1 ! . (/Thh eslimbled time to complete this.

.. ' ' ' ' . t ' \\J@remov,ed from service.

'

l - , ! / % i ' . . , ' ' L The reavire ions to be taRen for tagging out XBC 1B are: dsIy3REN e4STFt$ hen r 4 XBC 1B ' 4W<{;f3E?S-) dolm Quart @3i a.

k/ . froyk@c%wJn NT, Remove XBC?jBifrom s,epice;,Vdb:p;yM~ l $hg ^ ' g&+ b.

g:p y ' AQ f s t 5 hen Surviiliaide(%Ay2yQu{P/@55$@ pe ' - . %s STP. M % % .; % 'm A j$$$ O Q ' 1 Repove;XBC?1 B'froiii servW <

,.

m Ad c.

' lac

d. M};@ElecerXBC-1A B h se' A $ M M ] {ithe$ 8 yu M %i., n . [i b $/' (O , M (7

i'P'

  1. 5114[. ANSWER:

' Q ft - . , , /j d.

(1.00) y- e - . ' -

  1. 5114 MMENTS:

' ./ -" - . order 6ff(hoices.Significar,ly modified - Revised stem and distract . '%i R.

...s J* .. ~. a.

Incorrect...'Not per SOP 311.

P , b.

Battery becomes inoperable without a full capacity charger in service per T.S. 3.8.2.1.

  • c.

Incorrect. Swing charger must be placed in service first.

'. . - f 4.-a 89- ' _ . ,

_ -

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- - , - - ... _. _ . _ - - _ - -. _ - , r

, .

$.) d.

Correct - Need to maintain battery charger on Bus 1HB & Battery - 18.. , . t h

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yp o yg

- f Mr g ihg4 .p21hipi.9,Ihip kghW}llffi

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. , , . . . ' ] Questlon Number: 55 ' '

  1. 5220 QUESTION:

The follohng have occurred or currently exist: ' -

- - , ' A steam line break outside containment has occurred.

- + ' Several equipment failures and misoperations have led to all 3 - '+ , ' /TpveQt V4d Allh,e Rangqqant pumps'RQ%,with no EFW purnps available , .bpve b'een tripped.

enctor ,

' jSa# QpS'glnje' tion has been activ$tb^d a,n(SI flow ver . fgt f ' ' ' , + . . '

'

lemperature and pressure are incr^eayjq(! ' + . - With these.coIo tions present, all available PZR PORVs sh l ' a continuou2PCS " bleed" path for heat removal when: - - . , , 'ggbig ?Ran%LS~ 'adEr$Ns todd$. " ~ S/G Wide / -- a.

  • k'f

. jharroN j ' nge Level decrease;} };ijpgg;is40%. .% b.

RVL(S;pfM P ggym@ip ^) - s N PZRfressu% ged? 'lcre,asesito?2335lpsig.m %jd % - s ,v c.

re a Coje$$dk;.f$$MDDM9[p hw A -

d.

Eg'%qCc;inctesselto-1200Tp D it & GWA?QWdf@NNlk'NA h&

lh

f ,

  1. 5226

%: IsWER:%Yhit }h# II[7 A "d / - " ., d-(M (d

  1. 522B COMMENTS: '

' y.

Q\\ V'# . - c,,,, NEW ' UESTION pM _ , , Q y- - . N

/ MiEk-!mportant Operator Action #6 (RE: TWR TG10894huf / y..L - in(orrect - WR level < 15% in any two SGs.ls an initiating criteria a.

"for feed-and bleed in EOP-15.0.

., -yh j'f ' ' b., d. Incorrect %These ' ate (:both inadeq0 ate Core C

Establishing feed-arid bleed is designed to prevent inadequate Core Cooling.

. . , c.

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 ..

. .

, ,. ' * *,. ,..,_,,nm.- n.e,--s e, ev.--~--

. _ _ _. _ _ _ _.. _ _. -. . - . - _ _- _._ . _ _ _.. _ _ _ _ _._ _. . . . . . . . , , , 9) pressure is due to loss of heat sink, and not just from Sl flow.

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,ny.. re a, !,,- s get<*"*- h % w ' - Q%f W MA t" m n-t . b $ $e.? h s,~ k, r.., y mo ~p ,, - s . h?) 4* op y. [h e fp'wapa g e %pnag'f

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o I h Q :i m Q f . 'h+fNN36) ' I>*,. s;;,s&w%2Te% >3,/# g P9 %p,q p" M MlldlR 9 Y g,o^ ' me n E2Ms td % .rp ih Cf% C - * Y m

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- - -. - - __ _- -_ - - - - . - . . ,, e:f) Question Number: 56 , '

  1. 5117 QUESTION:

POINT VALUE:.LQQ . . The following plant conditions exist: ' . - . Refueling operations are in progress.

' ' - , The "FU.EL XFER CANA.L L,V,,L Hl/LO" annunciator is actucted.

. . . -- ~ Thg, level is 460 f@Let and'decreating., . - G ft.f ^ 1 iC ( r.'4 - .

. . f

  • The Fpel HandlingpRO,fs no longer sufficient to:sdspends refueling

,

because the wate(lejbl % Af g i . k. Limit the maximum velocity of.the spent fuel sh*,1ppliig_ cask to an g s , - . \\ impact velocity of 22 ft/sec.

%# ' ' . Q % f b.

demdveJ9% 7the@m n.,.n.mWactivityeth5t<iAlgrates4 obgh the -

-.- M.,/ fuefE6d.sEf3.A9 enortgag'#m,m W W8 "" w.y.-

m w f C CdRh LOT, l DW Limit;thl& maximum Ve scity of al dropped. fuel assembly to an r% su , c.

[,J,, impa$j$lkcif/of 443 'ac.y[f M.

II_i.m. it thpquCAtspng'e.fy % 75 w

. d.;y ( 't % ",~ 9

mr/hr dun...akimuni'ddiciist at'the' spen,t fue,l pool surfacdTo '. hO/ d. s in w m - v~n.~. w.s . y .- ng;transfeJoperationsa n ...& &< s QW%*7 ',i - U;;jr3 l E y; ; p+ n itij;"7 n $ / ,. l.2 f,.,t,;.,, pa s%,

p;,,$$v..~ A~.,t5 $,s? + h., r 29.ry, p\\ , g ;. . ANSWEN.M 'c ~h0h $..dk.W,C f/ % - w" . i }

  1. 511

. , yju d.

(1.00) %,jg, ;)J T' ' ( ' % g- . . .

  1. 5117

' e' COMMENTS: /Y /*q s

j 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 4..-. * .s ~.-

s . f,., , +- , =l.

? a.

Incorrect since the Cask Loading ~ Area minimum level is based on _ limiting the speed of a dropped cask to 44 ft/sec.

. b.

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 started.

93 . . . _ _- w

_.

. . _ . _ _ -. - .. .

. ~ ~. - s . . , , , ' - .; . N.7"') . c.

Incorrect because bases of 44 feet is for a dropped c' >K, riot a * _ dropped fuel, assembly.

, d.

.This will require. exarninee to apply knowledge that_ for refueling

. ,

operations, the gate between the'SFP and'the Fuel Transfer '

- . , , ' . : Canal will be open and a' decreasing level in the canal will be -

r . ,

seein in the SFP. The SFC DBD, page 2-3-1 (Function 1.). states - ' ' - ,... . ~ !. that the SFCS Maintain' a water shield above the spent fuel ' s ,

. ' ,' as.Spmbjiesjto @t radiatjofSpls in,the area of the pool to less c 5thrhpft55(-3.,than 2i5 m /tirn Thisis amplified ' , M . l,', ' ' %,.- - - . > . . > ,q . .. . . .

& '(~ ' - '

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, . , ., e b ' y .w w /.+A.a - . 45QQq,Amy# t,r R bung , t e heB (-)n, p %MNWMByddG!s f@ff)$allllll[#jw&p[f e -- - l % g h t g g c~ 3 *3 = Qqhn '.Y Tdhi 4ik ) 5a(9 s@f fM

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. . , ' l . ..s am M,0 Question Number: 57 ] ' . y .

  1. 5118-QUESTION:-

POINT VALUE 1.00 , .Given the fo'llowing: - . . . - , . . ... 'Ths plant is operating at 100% power with all r.ontrol systems in

- - .- aut'omatic.

+ - ' ' ..t leliilQdev Mthe.

E JTh'e co'ndsnsing pot is unable 15'1/ f * % (, controlling SG L'!-4g3 reference' leg. D . . ' - . .. ' '

keep;up with the leak.

- - - q)Y %Q ' ':

. . Which ONE,(1)J ihe following describes the response of the plant assuming no , operator actio,g . $N .., . . g . s , , . -G a.

. The 'C' S/G level wil! increase,but MFP speed will decrease to - . ~ . pident,sexce rig,dhg(f~R$~ llfifseigdiNf.

[/ ' g The(distlE6endi$g'thTS/G Ld-lENi;Edipoint.Ci>S/Gjle b.

- prev ("3 ' y pr5R,x*v r&7&yr eWkd Q Gbgg# w F

  1. w p %

gThe reactor!will./ -og.S/G,Lo-Lo levelt (d't zww i % c.

..& L Ml% 'MMCMgd % wm%

d m 2v h* d. 'y ;The turb@in&=i i =~ ~ - g y[leve't.,? , eM 'on:S/G-H ( ' ,

~5 g%~ g!!$. qq w

y ' l? y kh L' n W ' r% .{,5 % 1?%u y % Q

  1. 511 ANS Jj h

' ^ , (1;00)-lff.L P {/. i .c.

-

, , - ,0.

m . :-. .. ~A31id < COMMENTS: ("D O g% Modified by resequencing choices.

"ge- . 'Wf s~ +. sy u c.

'# 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 reached.

- . c.

,.. Pt t 95'

_ . t .t , .. a -- - ua - , ,, ,, .<r , e - -

. . .-. w: 4 Question Number: 58 p .

  1. 5131 QUESTION:

POINT VALUE: 1.00 . % The following plant conditions exist: . I A reactor startup is in progress per GOP-3, . ! ~

_ Desired Estimated Critical Position (ECP' b Bank 'D' at 145

, steps.

g bz Qn~g py m . A' max,itpum> rod withdrawalJiplit of 190 steps has been

" .

  • (,,,//

establijhecf: ~ ' ,- .Cdntrol rods are being withdrawn with Ban.k./D,'. resentIy at 180 . - . %.sfeps.

l; _ , ' The NROATC pulls rods 10 more steps, and the Up decays to , - ( zero.

  1. '

W(1) of the(following actl~o'n's+sWQdTe$n-C % -- -e E' ksiFbpderithese conditions? Which l paw % % -

  • eWW A

/c We!Zbh V AW.JP A . / a.

Boratelasmecessary,to-ach.ieve..requiredfshutdown margi.n shut

  • D dowri'thSIN5istoh;ieF50P-5'5iid:ibchb0 late ECP.

~ 'h Y

  • $$h3

[EhMMSMIE5 [,2 b.

fpontingliwithfstartuplopef:atio@andlrehalculate ECP.

(w) , ~ m. a L L %(Qn,Q Q % w.M ~ n nyw*h: - lculate ECP. N c. hShutdo'w,.&C'j'%hQ:UO;Q??"dW---u.tn.thfreactorspef.; GOR;5fan g h (*% (+.J 5 vi m wn c N$j8p3 ON $ [jhNd3 F c' $7 kll Continue witlysiartup[ operation until c d.

j (% ifQG{;@f ;C%l%x;w;.5%Q%g 5k? " +A o Qe w $l. wy g %w % - m 'ijik '

  1. 5131 ANSWER:

r l)a %s &. v p < , - v

p.

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g' ' -

  1. 5131
  2. 60MMENTS:

x%lT i / ) NbW QUESTION Y n~ .7.

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'. d.

Incorrect. The Rx is critical before reaching 10 power and is

stabilized at 10 power to take critical data.

. .

- ._.

. _..~. .,_ _ __... __- , . .- . . }. Question Number: 59 ' '

  1. 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 hLa.

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 g, }

. , (. (/s - , . . ' A The pressure drop rate will be larger for the PTj4~4jailure, and . . ' '% the final pressure will be lower for the PT-444 failuIe.

- - . T pressure 6roptra]bjili~t5id$' ,foritfie PT-444 (aifure f b.

the%j;d4%failu7siill res'uTIFF5 lowegli$fpressure.# m .. / A/ 1P

- %

qygn. v" gwyg!the PT-445'failtTIe7and a c.

The Nii will bd5I fy: ' rp I the fii@l)[dresstEe5 ITelower:forgIhe PT-445 failure,[ $ d.

he pr fb$ s f r' hpjPT-445 fall but-(.[) F ' PT'fiffsi0re;willidi61tiiriniM7e"r fi6 L ssure.

"" "F " g( i Kygg MT {"]~

, '

  1. 53f*3%*d Mkik;hT.

VANSWEf: g - ,, h* , 75

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% (1g% b.

w f(), f-7, r d, - -

  1. 5323'\\ /..

,, COMMENTS:

-

J % y) . . < ~. - - 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 setpoints so final pressure will

. c . be loweO,f6rxPT-444 failure. 29

.f .;7

,_

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- . . . .

' I . . .. 3, y yr 'y19

- -- . - - -. . . . . p Question Number: 60 ' '

  1. 5352 QUESTION:

POINT VALUE:.t0Q ' , ' ..Given the following: ' - . . - . - y . . . ' ' _ '.- A reactor trip has'occurr.'2ed due to loss of offsite power.

- - , ~ . ,n e-S1[hidWIOT a'qi 5 L., e.

- ' , , 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 - - . hY

  • Wi-k f

lineu *l*![MN srtt, the;PZR PC$Is n $ormal

' Pr - - I I pfMN$$ ] / Yhi h The f31iowmghlg ' arame ers% existPp (n), - % . kb Y&h d PZRd 8Wanda&h,y m

  1. h e "% t u hW ;g[;prysslowly.

A [,

ncreasin4 g7

  1. 4

-== . sig and%e M ZR Gressute isE }980gp$f;.5$( greasing.

- Y; p & !kbW htkh'm m-M55 h gi .[ EEW Flo,w,1.s 7 'Q / - ad k.

h6/ bb~. . b,

The crew' Ensure /L' f

FREE ~1 (3) PZR PORVs ar$ closed and' s; t! - - Od Y.! 'the spray valves aIe cloTed.

. A - A R Which ON difof the following describes the MINIMUM actions that.MUST be _ performed to re' store control of PZR pressure: '*@\\ . N M a.

  • 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 , b.

Manually actuate Si and return to EOP-1.0, " Reactor Trip / Safety , _ Injection Actuation.

' . Increase PZR level, then place the PZR backup heaters control c.

switch to CLOSE.

p.

. ,3 . ~

' .

- O.

- . - - _,- .. -. - -... . . . . . . . , ? a

Question Number: 60 ' '#5352 QUESTION: POINT VALUE:.10Q ' Given the following:- - . . , - . . . 'A reactor trip has' occurred due to loss of offsite power.

- - . ~ ' Slhid.N,OTlg Q O [," $ . - - . - , a'ctuate. a 1 .s y' .(/)/ - % , - - . kBtisMDA is energized by the "A" D/G. y,. '

'

-

,

,

  • /

. s The "B" D/G falls to start and,reenergize bus 1DBIN ' . g Q- . ' . . . . - Q . The crew has just tripp{ed the MEPs$nd hagen . , d 0 0 ( 1 1 o 1 ods srfnilpldsIwTe~d3!EP$egd [ a3N-k., w~m-8s,WF3dk m es . w / '/ 'S eieVent, the-PZR PCS(was:in'.a~ normal, at-power vs Prios - - - . {$

',w

a. The f611owing,$nt;pararpete s,egQp g.

, . . ~ _ ffpp.

p~

a

- c h h PZR evhiki18S,I$$hiribg$g!n^ g Mslowly.

"( a $TbM$9 $N$}hhN M h '" ' ]k!khI ,

' L , T(*, - ,The crew dnsur ti REE'(3) PZR PORVs.ar]e closed and > ,, , , .*'f.

, the spray valves are closed.

. J.

v-

- Which ON}/ %)Ttore control of PZR pressu ' R ' - ,(1 of the following describes the MINIMUM actions that..MUST be performed to re 'p* .

  • d t,.e

.. a.

Plsce both_,ESF LOADING SEQ A(B) RESETS to AUTO-START . ' BLOCKS!ahd allow the PZR PCS:to auto'matically stabilize conditiods'.E ' 'jd 'lA ' -b.

- Manually actuate Si and return to EOP-1.0, " Reactor Trip / Safety ' , Injection Actuation.

e Increase PZR level, then place the PZR backup heaters contro! c.

.c switch to CLOSE.

. !. . ,

. .-g.. w vens

.. .- . .- .-, . . . . . .. . , ' - i-Q.) _ Question Number: 60 ' .. '

  1. 5352_.

QUESTION: POINT VALUE: 1.00 -

.- , .. . Given the following: - . . , , . . , , . . ~ ' A reactor trip has'occurr' d due to loss of offsite power.

' ' e l - - . .. - Pa n.

' %.mL4 . Sl[ddidIOTkaqtuate. '9. _, h^g . - ' I -

,., 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 '

  1. "

' C"5dliol ds sr67uilpTN'iEii621f5Mgy // -f . Q j-9m " #,4 g & ' eveqt, the;PZR PCS wasan%vfp x GI wmd % f Priort .a:norrnal, at power -- - $ ?!?

. AThe fBNhiijj[ plant' gba$. %u_$Rm$ff,; rarn'etE CeEU$(&h(A\\ ' - . lS,.b P t%ub gi p-aw s,.i y e - PZRieveh_sii . :<increasin ~ slowly.

< "' . W "$$%861ZR..h h Y WW <l ' "" . sgei g80 p.sig agWd' ecreasing.

M* ir { ~ >]h

i_ G&$bf[f% F:";i/ ht .a.aus p!Nhl ODI ' -4 IhW7ow:isiG4 % ,The crew % ($lli iU 'f$... bnsures t closed and the spray valves a(r,e c o, sed,1,TRREE'(3) PZR PORVs.a - , , /, v* - g .-

s ps , Which ON (17of the following describes the MINIMUM actions that MUST be perforrned to re' store control of PZR pressure: "p. d 5.e. - a.

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 - b.

Manually actuate Si and return to EOP-1.0, " Reactor Trip / Safety ' Injection Actuation.

- c.

Increase PZR level, then place the PZR backup heaters control switch to CLOSE.

> .p....

,

7.. ~

. g &

  • * ',

, -

. . , e s % c.

Incorrect. Air entrainment (vortexing) will provide low pressure ~ y".)

> and flow with fluctuating amps.

' d.

Water hammer would produce erratic conditions.

. . . . .

. e h M i:d 'i < ~; ~ [s 5 c p Urj I-w 't , ' ' d, p u,dk - \\ wy f f.f . &. g.) g4'f = [n %. . . . . .A

  • [

' , % sh r .. ' s 4 /s % ' %

'*w s " ) . % - > . i;, w?s %... Q. n& I55.?$ ??E Y. ~ 4 5 . n/ ' ' on w . ~ m f ,g ? Yhbby'f5h" dh Y $p$+$;75;'M{- - - Ek ?

3.5 - ;;Q.?M v

v s a +J2 y %w.k.Eddhd.h, '.W.Yr I 4!p ,% w.v. = - $ n~ Se r e e, c m,v . r,1 .r .e a.

-

  • N

..

  • ['y..<5.K n.

Il#: I.PwE, E- 'p + ,D *: I.

2 r[. VD;}5 d,[ u.? % w mn ,DM*;Nl.Q , -< e . / D

y enn*JCer$,$h{yf*. e/j3g:v>;:n,J 2ygs'." '_%

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i CyPvms-O ~%3 Men #m % cgp

4 "

J - *,, mue w 2

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n d @s p e@a %!$ s a s FQQf,a.A

==:r: hr gl <A hr N%eg 5% nan,rg~ss%q f t [ y'l VtR s c4 sts/ c tr f w f?'YMC..,. Ri@h$ ~M sti i-4

h*

i.

h$$$5q Aw%z lE_ fl A(.

W > rb . - $p"T uh.p %msa?"p x..+*3' -a - a a vffwk, ,f*

u h i ii y *s,.n.. . i /,%,- y enit!jgt\\.$I g ji - . as - hl - %,f t' ni ' e m ? tti* ? t~ t s* . %' ' ?l$lhiY u?

. . - i,%; n W/ x %rd F / - \\ . %.y.

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j.,5;w --/ $ .- %. 3, e a e - pQ

. . " 147 . .

o-

_ _ . _ . . . . . . , -. ,

_b , - . -

- . %.... : ' Question Number: 98 - , , '

  1. 5090:

QUESTION:- POINTVALUE: 1.00

.- . . .

Given the following:'.

. ' ,, - The plant,is in MODE 5; ~ - . " ~ "Il"4SW is. u.fsg .f.

i' '

- , , ' ' % p

    1. }, "

, C,SpP*is OOS and racked o .. - . . ). .. . % 8 y: _ , ' ' - - i , . ' A" SWP is not running, but is in standby, whilpmaintenance is .- , ,. . i' Investigating an MWR, fg. ' .. . , apove conjjt]hns, which 6 j f the,following describes thI uto start i: ~ Given t ' . LOGI 'A" SW pu . MI [ h~ ' - , MVGOO3J43SW to EFW sup fy){openT5fncident with' DS- - I SI/Blnfi50t@949MM i [*p"kb$$$f a.

- - hEMF GEM. y-8-Wfs m[l . ,7 ' i s n ~ rEEW,:supp# ., incident with , . vy a .. VG)103L S ~ h - b.- persco . . .n 3D , h?y Q lack ^" [ _ i '"Ga M y '. ' ~~ low s 5I{on $:6 6 bider)t no Sl/ Black kb {)prels:(h ' '"'" c.

fe d- . . --_4 ' i #5090 -[ ANSWER: " \\ - - ' s , ra. - (1.00) gV . n v

  1. 5000, COMMENTS:

1 T,%

.]'-: -

Modified. ChaEghd order [of{Sistracto'rs:

i -. c. & d.

are wrong because the_ low pressure only opens the , valves, b.

is wrong because the auto start on 1037A open is locked out by sequencer.

,. - . "

_J 148- . , a s Jet =- ~ .---.- --' . - - - - -..

. - .- - - ., , , - . . . . ,

. fQ.. " Question' Number: 60 j ' . . ~.. '

  1. 5352-

- QUESTION: . POINT VALUE: 1QQ

, ,

,. .. w . ' .Givsn the following: .. . ' ' - , . , , ' . ( , A reactor trip has' occurred due to loss of offsite power.

.. ,. .. - . ' ' ' ' ! - . . - g t at. n w .re.

' aquate.

' ). f, x . ee -

Sil id E - % f . . f,5

  • '

.. .<.

.% . / ~ e

. .. h DA is energized by the "A" D/G. % . ' ' '

- j - . . . k.

- * h The "B" D/G falls to start and reenergize bus 1DBW) 7 - . , Q - - -

. . . . , crew has just tripp@,e,d the M"EPssnd has, ensure ';. - . . 7di $M ~ - ods sii{k the;PZR PCs asiirr n N ~'@"' - kf_ .. O T . - . ,,. . Pril / r, - - D lineu M . . , , he f6$owingjjant)aramete s,3##pw .?T PWi u .. pxytJD ) - y . - 3.M,g . .,. , YA$

M?hg 4

- " ' - - "- - - PZB "5 {p * j hy ll$F Q( increasin ve slowly.

, hc N3* pZR-s; 980psig and ecreasing, er"

^;,ey ' he q%Q {*W'Ef(3) PZR PO \\.0 ' &- %..- - The crew $nsures; P - s -

  • *Ql

. R . R '. 1- ' the spray valves aIe c oTed, p .r Which ON (17' store ontrol of PZR pressure: of the following describes the MINIMUM actions thatsMUST be performed to re "'% . ' ' . a.

'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'

, , ib.

Manually actuate Sl and return to EOP-1.0, " Reactor Trip / Safety

, injection Actuation.- - ' ~ c.

Increase PZR level, then place the PZR backup heaters control ~

switch to CLOSE.-

' - ..'- .

g .. - 98 ' i '

.: - .~ , _ _ _ _ _

! . . . i . .* %) d.

Place "A" ESF LbADING SEQ A RESETS to NON-ESF '

LCKOUTS, then manually energize PZR backup heaters as necessary.

. . . .

  1. 5352 ANSWER:

'. '

' - . ' ' d.

(1.00) ' ._ ..

$w

> , , CD M,ENT[t 'p m .c .s rd f.~ f% -

' g tt k i ~,, Qgf j', .

  1. 5352

. . .. ,, , nap %'

' ., . Sig ificaptly modified.' Changed and reformatfedyt.e,,m\\and disirac - .. .

, - ino ichanges to distractor a.

// ,

! (* . isk-Important Operator Actions #2 (RE: ' TWR TG10894) h, .

- ^% W_.. -r--%.sr"'?Q g use #B/(heaters, - SSMo

%nR!*I@R\\r

- y "% Inco.3 Q, Sjjen.f r.ia,tet. p a u w g,y ~ b.

, g rre ' p %. d$$$Eff %. bsw u:2 (, s

c.

IncorrectgPZR Hea,ters7wil,l[,riotitH E ALocko6tFiliti(6 e{to;befr'eself$u;p u til 17% level C

(w) . :M.

max- = 1; gh %g.\\ t d. %dp%. t m ph .D kW W h% A^ ' , r rr ~ neup;mean.sithb GRP 1 B/U.,,.? V) %;hedtEe t. Agorga (at-powg '(StNrt" and'GRP,,2 is in Nornta trec % rs are th;Normil-$ft'e /*'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 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 + - - - o/ sv'"\\- action.

d , m M v\\.. m r* 4L ' ,Ti

h.

_-L ,. - . l%

f -'

.

. a4 --, .

. . . -

i ~ \\ . . $ . ^l,,d.

Question Number: 61 . ,

  1. 5333 QUESTION:

POINT VALUE: 1.00 . . Given the following: . . The plant'is at 40% power and all control systems are in automatic.

' ' . . . . . w.. n n The PZR LEVJL C Bli Switch is..!p the359 + 460 position.

. t f T L

' % . u. 6 % b,4. c s The NROATC4o6 serves that actual pressurize /rdevel is decreasing.

e - ' ' - . v - - Which of thefo,llo\\ . . / \\

. wing conditions could cause this to occur? ( /4 . .gv r ses , a.- R LCS LT-459 fails low.

kM b.0} RCS Te?lz%*RTD failsk~igh4cW~MDs % g d:cr

  1. /, m

.... smw 2MQ - - C%dm% N

1e

% dw s A(4:'p,aMedt %f Temet

,ic.

PZR PCS'PJ:444 failsjow.c s wyn 9 4,9 ; & ,m NIS Power-Range't@!4 fails ~ high,,,,,,.hhb[m (h, f.'hhhkN b h'd ,,1 w4 ge h?? V Nd.

U q$N,SWER;Q5$s@M"AD%@3 Q p %??;@iQh:289di .- %,)

  1. $3"33s 3$f!j d$G ' Nf, m.

5-jg$if h/ d<, ()) WW l$ %g66[.1.0"d)gQf@$;ympNO9 d. N$$p ! ' dh &c7 g 9 $. [ o $. _;,.f +, f

e* Wuu tm

% cc.d.w.o y

  1. 5333"I ICGM@MENTSMd6WW1,%c$u?N iM6

"4 \\. Up p"%,.7.jysqMSr Q;/ % ("dx Significantly modified $"Re;mtae: n y i.

~ e % mp wlistem:andidistractor c.

vised % l \\.r# 4< - +,qr e g.<y,N ~] '** Q/% v ,- y 'fl a.

.

'Would cause PZR level to increp.ce.

N v- - - e % + &s r\\ /,s e-b. / No longer causes control affects due to RTD manifold removal / and median signal selection (MCN-21315).- M \\-

  • J s..,

) %u g ~n

c.

'PZR heaters would energize and level viould t due to thermal % expansion.t... A e: . ~. , . q / t~ W: ' d.

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 decrease.

100 . .

. . _ _ _ .. . _ _ __ _7 _ _. . _.. . _ _._ _._ __ . . , . . M.- Quektion Number: 62 ' ' - i . . . .

  1. 5202 QUESTION:

POINT VALUE: 1.00 i '

.- . The following conditions exist: ' . , EOP-6.0 !s being implemented after a loss of offsite and onsite - - ESF AC, power has occurred.

' - .e m~ , .ci' s f M k,., The'operat n\\ fact !*\\ ; ' t g;cres> islin thct. process /ofdepressu'rizing the i - " (.[. 8 '. ', S/hs thi240 psig.

' - . vt . '% ' y: uring the depressurization, an SI signal is generated.

- . .\\ / - .W Why is it necessary to. reset the Si at this point? [ . ^: % Bec<ausghe pItiseque;nt recoveresence ofit ..,-x~~- at . , p , . a.

EFM/.hunng':st-facti 6nsp- ^ g@y a w p.e Resetting $f%m%$@4 plit flow % , f . s,.~JiW ' G A E!SF eg;$gnt.to be ma W.

!Si b.

['( Ni d[dh LE f ecause:thi@h,ll/estor & _./ B wi i, %. c.

$$$ $ O d. 'Igges,eting SFwil,I;en,sgre tpat}hlService $ . j3 fump will beq " #nsure EDG cool;tqg.

favalf5jfe, upon:resto[at,oniofg^oweg"h iow h% i - 22FD}M [$W k I % $

  1. 520g)

ANSWEF . , . ' [/ n$b.

(1 00) gj MP Q - , d.

% ,[QOMMENTS f%M '

  1. 5202

% %l /, p NEW QUESTION R p.

lhcorrect since SI signalis overtidden whe;n the MD EFP RESET

a.

., Switch isTriiomentarily taken to. RESET.

' q y - , o b.

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 started.

' c.

Losing pressurizer level is expected for this depressurization.

- .z - .. ' 101

  • .[5

. a

- -. %.

-.. ,, -. -., - . - - -

.. _. __ . . . . .

. ' 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-6.0.

. . ' ' d.

The Service Water pump is "made available" by D91 P acing it in l . . , . P T-L. Si reset has no impact on SW availability.

. . . Risk lmportant Operator Actions #2 and #7 (RE: TWR TG10894) , . - - .m m [*, . n y .es

~h y ** 4m y . , [.3 '. . T** I [

t

,, %. f4 f s %, /k . .~\\ .** y \\"r pff % . ~ . . 4*/ . .. g" A, \\:

,. ' ' , . \\- (fr b . . % e>f . ) , . . . , r,, , ne al % p'% w' ' geWO*u'E?%n%n.auf ne6a l % uw* ,Nb? A.f,dh? %[Y Td f.is;',V.m$. f ( , w.enf

&;Y .ff$?$?$555D ena$5T.rma e f ?.M[m n e s w ' iff %$4C7f.)&W rN.;esska$ b. f s'?#*1:f ~%,, cp:.k :.,.2..,f'%, s

rv 4 * e tM + 2 s -h % I f j$:M5'*$

, +t.. . F. g.wc m;ug g eh & r s.

. ., a. w ;w . .c % O bE3 /;~.w[Y ;h E [[>'N'M# MM.

- . M @ @ n w;si% [*( $ 2C p %,j gf @ (j f p > % ? b - f.

ig I J . %

n. >

h O Gye w agw c:- cwm %a . { ;,! h $! '. t . ~g. {m-* n;%,y,wl r., ,r.ntsD.~i. m w,.,y.~y ' -> yu k , j.

a,. OA %., e"n p ,a u L ' d.I I j;.5% GA&NS afadjh $ f% /,/ &, i f?., M f M.

t.MPV t $. j $N +0h: k$$ki , N bC{'?hlj,{{Iff$k?lbf $pl

i-&? ' \\ vvp G ~

&g . . . , , -fi - s\\ /m . / /y Kwd '?% \\., +, s( v ) f wa.

';*"p Y A .,

  • 'v, b
  • i.;i."

.d., < ; r . ., s a~

.s}

' . . 102 - . . .

- - . _ . _ _ _. _ . _. _ _.. _ _. . - ,

, . , , ,, , , . . . . . . ' ' - , "O) Question Number: 63 i ' .S ' '

  1. 5203 QUESTION:

POINT VALUE: 1.00 - , , .. - . . . ' ' The following conditior)s exist:

. ' , , - Ths plant _is at poiver with a normal electric plant alignment.

- kf$,unc[ato 'B (1D 31% C,KOUT" actuateb.

% bc . ' L+ s

  • Which ONE (1) of the fo,lloping statements describes thkdafus of eq~uiprhent

,. .. . . - - power'ed by 1204%Cfanels APN 5903 and APN 5904 undetj,fconditions above? " . .& h ALL equipment remains energized ' ( % , i k through the inverter.

. . b.' . pms'ntj,Lernigi(s drz f,[om;th backup ' ' ' ' ' wer .. ,d.f IDthe iriverter, IfurNON-VITALTloads willt e~shed.

' su pwngy' r b ALL fxiu pid$b;reri enerJe3Ehine inverter's alte3 ate c.

h@ou npyj AC sg;{,idiE%g&W+2%dmW$Oy % p e1 N O.sourc,eg,tpmentgemains?eriergizekfro the inverter's ajt..) te y~

m - ^:2:S d.

AL gqu eJpa h hIoii h3h$IirNs/fEr'/ifutiNO 7AL loads will;bs'

"

" .)5$d?m ^&b&g h (5NV { ~ f

  1. k I

@ \\\\) ANSWE

  1. 52

- ' '@ i (D , D V a (1.00) / /i f.

% uj![.. a %,, W G -

'. #5203 COMMENTS: g - gl/', Q - NEW QUESTION h / QA pequires examinee to analyze impact of S1BX U' O, in that it will a.

t

  • pte9ent reenergizing the 'B' train 7.2.KV4uses. Also requires

, applying *kriowledge that the ir!vsrter-will Oltimately swap to ths DC inpuCN y' _

'

b.

Incorrect since all loads powered by the associated APNs will still.

be powered from the associated inverter.

' - c.- Incorrect since the alternate AC source (1FB) is also from bus .1DB, which is locked out.. . > :- + , 103 . -

  • .

.g.

- , , w ,. e , ,-n- - - -,

- .. . . . . . - . . . . . . 9 ), d.. Incorrect since Dbi will not tie to bus under these condition's.

' rN , . .

l ,, 'u . . . . . ,

,'. ' . i . . , g g

' 6'

I e

' s ~ . . $ h% , , m, R e , -II, f T, - " Jr -'d "***

% . w% g* - NJ* '4e f*

. s.

,. s.

. 3 gM ' (I[ (- ', '*s . ,, s.n 2 . , ' , s . - u . .~ , [f , . ' ~ .s s .. ,. .. , g.

4I kWHung ,., f '

f' . , , $ ' NNw ' u.. c m W M c &, ~@i@eGh,;) sew? . 4 ' s i . we ~ n. ~n.; g f;aISA s a! i p -.*% gg ?% tfa.MB%z'n * (w'% im~%r's; 2. A,7 ei: r

L

w

cuw!

W YtQ.cr .e y l'g; <-~. ftf5:Q gyt;m' (3 eu.

x &

  • %%A 9).% %qw y:n,

.n - ,e ,n ,..,, 4:V1 (.i y F . s ; W.

.y i 4.

$$$h hwgf[I'YM4 I'"yN i N S M. 8 'Mh* dN5h3dif5 te$A:r?lf1:%:ka:% spas.<b(b#db,I _y % [&j M

m a m tc, G !rXG=3r' 6 GfE m%w@iq: w amw x.

.. 'T.& dl y LW'js% Qf % r's

    • "=y

\\p.# %;c v ,tt,] f

y h $ })if b Dhd?e Y2M 3. F . id E

  1. $,e+s'"'7

%sn$a

w . .e . MM wpf ,M? [. t v.ns :;p,1, j

om per

y n ri t

' ' U w n.i,n %v. W.s, Cn- '

c ,#- - f .s ! ]. + ' Q.

w; s'e%/%r .s = g g \\,f,/,- .

^ Qv;. < u - - - .. < .e . % h / 4y. .s N >nq ,ts t y % Ae . ,

Y[ E# -- $g'g

  • ~l ;~

b, .

N

,

6 104 . .

$

-

__.

_ _ _ .. _ , , , . . . . . . , . ' .. "'h - Question Number: 64

'

  1. 5351.

. 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 SI.

' m m . it M M t"%. -. . ' si s

The,CRS irpple'me'nts EOP-L0gd directs activities.

. , . . . J V - Q)/ '

- . (o'nkiiinment pressure is 15 psig and sli>wly, c easing.' " . d THc operators verify that all ESF and containtnentTiolation . N systems liave operated properly.

(/

' - - , [ ' ; meMT7..

If the fjtCP are NOT p% ped.at th:,po =t;(prioc'ioEwlllii$clir;#;an o x to.de$rmining

in strategyklvhich ONE [1)N ~ gn6thEfoll8@ing' condit ^ . eN g ggf ,g@ r

. h w% left r0'n"$16l6[$ffContainme ispray'FMT@/'c .4 . ps .. ' a.

a ' f*N, A $$E$ rgMsffR d$$$' Jf % I , dThe RCgbear n s:and3m orsMill.[ D' k - o . 5:S b.

' " M$6 hN$ff'!h h S" [d ' c.$*Ndhb

  • '

hPeElfcentEili6e em rafures:will be exceeb d due to hebt' input ffI"3}I RCf3s@lp EE / 7~ M W w.-$ g R-e m % .

RIirntF@ ItM hk1[e (\\h 'd, overall Rd.e N6 Edde9ojslalYilure.

/* 6 %w would add 1 he, s lea ( . .#5351[ff7 ^6 17 QO P' - ,, , , ' ' ANSWER: P-g- R V ). st (1.00) het

w\\ i

  1. 5351

'C6MMENTS: $ - T N.i ., , Significantly mEdified - Changed stemIhrid distractors a, b & d.

, , , Reformatted stEiin'. 'p[ !^- ' a.

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- .

.

g""

a , ,. -w - r - -n.

-- -- -- ,

_.

-.. - . . . . - . . . . . . ' ') loss of support requirements to continue operation. Traine'e must determine th.e basis, based on procedural progression.

t-c.

. 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.), . . . . .. .. Seg! inj,ect,on i_not.stop ed.,.- n,, , d.

' i s % - N Yh fr ' - - .. , , , , , Q)f - 4'/,

- . x . . , . N - e . . . . . . ~\\ ' ' ' .

, i.

'e ~ / ' 8' (' . w. g.

ew ? E f'"idlW AtN. N..,.' tim.-@y$2 r.# fj J e,v'8% .m w = % " '* *.m:ru=n l ,e.

me kQ,ag,11&y.p' g'abM7g %%dd"**- 'C27 < 46g5th 4A. g, . .Z.

f' ' e m q ets a c.,R.f . fl?O0Ny kl'2id y

bi (

(M,t n. m.e u r ec n,? ,- .,., T.

GQM fsFa % 4..s@t@w +gs r% eu.m - h d! h khhk3hd b; s bh 4M @M >7yw%.s w w,, w w m.,g$w....,n,g. (vi g - rr m . :, a., .. g m =,.J;;rg-pE.N< vu4. es Q 7c.3'p+ A Q %vay [; ' W. ';"N ..h, _ v*,t y 4w e , yLQ*d'5Ab:m2. -w %,D. g w !.. p

~ M

p fa.k %. k? I er'%

      • m t p. y g-f =3p/

f %v# m} Ay el) u + .k)g;lN{Q Q,fp*t by,; Yi. . d Y . yc'?n' Mfc, pn a., .. . n.,pM,k 'hMhhN,hh,f'[h, .% .e n I k yd..h_ n # tj~% , s%c.;, (a/, //

R, jr

y>, ,v .c ts.

's: r ,'..

y k/p*s** " e w %. . . . ~. ,. ( ' y , N $ s e s, p1 k

ti; > , oEz i .* t-gyy

M" i ,, h h ,, .,ai /' Jmf q T:.

c

. 106 .

- . .. . -. , - - -. - - .. - ... - - .

. . . , , . , .

' Th Question Number: 65 ' - ' J?- ,

  1. 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:

.. . . . . . ..&-Tlirottle Valve 2865.' ' ' . Mayually t rottfpith A L@., a.

eT - \\& (L . . ' Magufly1 tottle with PVG-203.jj[[# ~ , ' . . ', b.

' - g . . . ,, , . s . . . . . . . . . i eset the EF PUMP. TURBINE SPEED CONT LGOVERNOR , , ,

,

.VLV by rotating the manual adjustment knob f ly,q ' ' i , , t counterclockwise, then clockwise. Then, transfer control to the - . . . hw @%ME6EENNE$h pWh' ~ . / / d.

Rese th@E PUNIP' TURBINE' SPEED:C'ONTROL GO RNOR VLVig(y"$$Nise){h'elicl6ckNis*E,E 8E ng ihe. manual ad[usfrhE6 kN8b fully I ' - counler T c '( on th'QCEj )#MQ' Adhcc: ?.j;. h',1 l

  • ink.,

L SWER:"I epf* & t-~ & .n;:3 - #53.4) - "

.

i . id? R y gg* y , . . w A $

  1. WP pm.% y(.1.00)' ~.5 g

a.

d - - % > . COMMENTSr M.ti kh* $D E

  • '

trf i - , P'] &p .u c: d.

-IncorrecCsince Hag,erqdirectly controls _ governor which is failed.

' .. 'l . 107 ' ..f'

.. -.. - ,y . 7-f

s-,9, -y , , ,:mr4-. - ~- - - -. ..

._.

_._ _ _ _ _.

, + , . . . ,

. , % Ouestion Number: 66 ' ' &/ .

  1. 5343 QUESTION:

POINT VALUE: 1.00 . . . > . . .. , Given the following: - - - - . '

An'l&C Technician, while performing an STP on Pressuriz.er i

- + , , ) PT-455, accidentally trips a bistable for PT- - Prsssure Transmitter,iUfe,tyh h results in a Safety injectio - . . ~, ' 45Q,, Prescuriz']res ' -

  • $ b b L EM N

.. , . " Thgoj5erators are preparing to fan / f 'to EOP-1.2,'"S

- siflop

" -

-- - . . - , .. . T,emination." - %.w.

. ' -

'

s - f . . , - a.

L.

.. n - . he following will occur when the NROATC atterhp(ts#to res Which ONEL ' . . / E ' ' signal?-- N

s , . , ' . it,fvillyOT fessl~ angry ~ ~ ghlWo - . c$nSl;'diffon.

,eIESF actuation logic,t is normal . ~ F a.

[ f' . $ #3Id5}@ M + f WWN / Mgw SI wIkh T[iSIe OkPZRfdres$$b 1985 psig, an"d'The

- b.

PZRIffMIN A(BfSG,h'e~s*aYS', id^de"d in BLOCK.- %' '* < y.

- ow e e , , ~%&&j%?12 ueniau% . % & u - ~TLMf;. 'gset and:bliickisu seq $hy[ (tid ..m%?)

  • SI will

.

c.

h Q ' '$$$3I$fk d MIfSMlli resst<an $hdk subsif(uent auto a d.

e y w ~ +- nw-Ess a n . *4 - - ' - MW-Mc N 3Eid$h

  1. yd1

^ L kh./, D' -#5343 AN5WER.

\\ % Qi VJ ' ~ b", (1.0b).

v'vw.u i'W c.. i4 - ). - . . v.

. .. ,

  1. 5343',hO sy[]

COMMENTS:

, Significantly modified. Changed conditions of stem tind. original distractof d. Resequenced choices'b, c, & d. 5 - '\\ .. T (1 - Normal Wo,uld be ready for eithe,r-auto or' manual actuation.

a.

'f

?

MA W

- b.- Sl w,ill reset.

. d.

Incorrect Manualis never biocked.

' .,i , se 108

4 h

1 4: , < +. -,. .-~ew- - -, ,-r ,, ,,.-, rwr,.-4 ,---.4e.

._,r-,= - ,- w -- y

-._- __ . -. . __ .i ... - - - . . , . , , . . . .

$g. ' Question Number: 67 J . -

..

  1. 5340

- QUESTION: POINT VALUE: 1.00 i , . . . . '. . High speed operation of a Component Cooling Water (CCW) pump is administratively .l ,.

, permitted: .

e - - . . . ' ,:,, a. - ' During hot leg and cold leg recirculation for the CCW loop supplyjg esse ifal. loa 70. C"(% j - - L+ rA L I L d1 e f . y (Otirjng'hotIeg and cold leg recirg hT . litioryfor the CCW loop- , b.

' ' . . ' .' " excharigerc < , 5j - .. ' [c4 ONLY during cold leg recirculation for the CCW ot6p supplying _ , '

- g - - Y essentialloads.

%/-

. f d.

Ycduring 651dils Bli5Glil 4// nofis%$6fial Iods a@nd iiERHR,;hisi4EE6 ange p' plying ..

ANS

I O

  1. 53(

N$$)l )N@1 hh d ' b.

- fggg yfjj2}$ hgs 'h 'y! i e

  1. 53$4h kyk 6MMENTh.hw h *f,.) ^,

( I

Modifiedibm -%Tero$sequeNhngtall$ yN M ggl9 g,5 w-a .{s)-- wj mp;.4

ya N$;5 era orn%p g <w4svdlA.m e a gg p s Risk-Imiso ant: ti6ri {(RE IWR TG10894) Off h J k b, Loop suppfying 'esslelnltialj ads,an'd non-essential load ~' \\[#h.b. 'to FAST LAW EOp-2':s."No changes are made to I!ndifphhen - 4- ? '

- / 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.". ~

  1. -

ud % y.

/h pr Y 4.

. %j.

' ,5 l-~T

_, g

~,;.

~;;. jAj.

. . . - % 109 .

.* %

-.._ _.. _ - _ _ _ _ . -_.___.;._.

, , . . - . . , , , . . . f t i - n$); Question Number: 68 ) - '

.. - , '

  1. 5339-QUESTION:

POINT VALUE: 1.00 ' - . . . .. o _ d ' ' Given the following conditions: - . \\

. . . - A"'CCW Train is the ACTIVE Loop. - " - - . . - ' . . ' J AnpMLi sOpeT4tioriaCchick isteing performed.

' - C,. J [ 'i f. 1 L ; G I T

- t j 'Wknjleptessed, the NOR-CS pusbbuttin sticks'and causes ,, '

'

- . hl' 2A to indicate > 1 X 10' CPM.

Qf.

f ' " ' . . f./ , .y The CCW Surge, ank' vent will then: ,g . . , , r ' - . . (V/ . Close if the Interlocj!!sgeMIP tsMWPLsyitch is jn,0No A a.

/ b., Clqsejfdhetin@terlock switch is in.'OEEagste2 -

WR% m b % p g%) W; p - ~/

- , M $ eg w#" awa f-wegmey, t ref5-gdsgh,P as

Remaintopentsln(ce,'NO Surgankihighlevel alarm is present.

N.

., . c.

,f $m^GyegJ 'ad&# s. -@t,h C % *' ,ug ./ % - .e n.

d.

4 Remain:open;beca'use:BdTH RML 2 Wand RML-2B are 6eeded .

y , hgd(30 closphil3CNS'Ufd5TiNIErith

  • '

(O y$gy;WER:%;jiyqPJ2,=% sa M F " AJS ak j fhihf* d $

  1. S339

'h 'h lib8b y,) pw 9;i m a,h r%ugg ',

s h.

% b.

an mu \\ y\\ Vf ,, >p rc % t + e x- - ig

  1. 5339 COMMENTS: pptr du,J f.

J // . V ..qi H lu ~W j*/A/*r [/- f i . ' '

. . % [fNEWDUESTION.

t- - \\ . -.- Interlock in effect when Switch is in ON position.yu/ .a 'q s.

. c.

Valid distractor since leak might cause high level, and examinee 'thsy believe tiiere is an interlock betweeh/hvel and valve.

. %

2.e - d.

Incorrect"Mcause' 5[uide Tank vedt does NOT require both Rad.

Monitors to close.

. + e ,, 110 . . .- M - - -,. - . _, - _

-. _ _. __ .. _ _ _ _ _.. _ _ _ _ _. _ _ _ _ _ _. _.. _ _ _ _.

-

. . . . ,, _l 1,~ '

. . . .. ' . ..

w N..t.. Question Number: 69 ' '

, '

  1. 5215
QUESTION:

POINT-VALUE: 1.00 - . - .. .,.- . ., . 4., EThe following conilitions have occurred or currently exist: ' - l - . , . A L'OCA has occurred and subsequent failures resulted in.the ' -

crew implementing EO{)-14.0, Response to inadequate Core . .... . , L.

i ' ., j , ' -The.cJewis preparing to depressunz.e/the, S/Gs to co'oldown the $ ' ' , ,

. + ' - '

' ' *% gf CS.

' ' - . , .own, what actions are taken to prevent injecting a[ccdif ' ?, _ During this.co ' ( - , ,y

nitrogen into'the RCS?

V# . "

. . di'dhe accum71st6rsildth'EkN$$kosg{"inrIprior l.

i f*/ a.

e dd'rEidfiiatiodf 'YmfP A - Sp; app a;ri a . f

, b.

Isola h mdho priorkht d$ ssurization h q ~~ q ~ /q gg y y ,s w,wnn n, , . top't,e; e" essurizatio :st 140lpsJg in the S/Gs and RCS.

..., c.

- eru ( . wJ WAgg v ! h %f'5$clies 3 #pressurizatkrINrfi op the o I fhT$/G NR leveF d.

$P#

A , "" W &{5$6[IS _ . " ilI ~ f*% .#5215s*% . NSWER

MEY -

, , ,"" ' - CFCE$' u 'I % (1.30.)(9) h! ' c.

g.s .

.. ~ " gQ- -\\- V -. #5215 /p -- ' COMMENTS: . . , e % e -

    1. p

A}W QUESTION hs ' r / y Risk-Irhpbrtant Operator Action #7 '(RE: TWR TG10894) T 4.1.

' . This actI6Mwould beitaken afteIthe deprEssurization and only if ' a.

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 . c.

. .~ - 111 . t

-- t _.

.' I - , - ,s , *, -, , . .~m', , -,

. - . , . , . . . . 3.)

given information.

' . d.

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. loop.

' ' - .. . '

O e - g

l $

. '9 t .- 4t,, p A.

e

. *b / - A E 1. f%f t'

. '.~\\ vr*g '% (J/

t q/;. . ,,. - . . . ..

  • .yv

. . . .. g %.v (,f ( % .. , . . ' ' ' 5/ < .

7.

, , q e t k . $ }./ Qqqqy% - e Ma-b (Q M+ w^.w-- w @p c m g A l

  1. /

g.. ,ie D; e,7 %

w s ~ g

,*%gyngpgf g ,x.s L g w AR;;;?sprsy . .Q.m%9.1;&L 'ff* dhd Nf N

4 @jg % k,[w$Y fhk ' ( %, .% w% @v %s h s/g y "m %;s%p .%>) ' l%- W8 n din L.w, p .m, k- . h p,ss a!b ? $ n.s @c < 5 l E u: $ j A s ) - .d n .-nc - - - . W.

%kk%f Cappp MM f Q$ G,s Mi%g% s, L ad: .- d v*WFuATF hat &Re:awctnC% kD $$p,s, y,em'y e t i h TJ/Jy~MIdh n Il ph.

Qa,r,h'Mr# D* AFg1 mu J ih D

%.,a % y,t,uc v,Le.,, g$ N" w eg ma u..m u,, n, +w,hy,[,)d es xp \\ sw s mm a u N h [m,

' m' ,. ,f .e G/. g5ttb ,a 1 <w.

Lf) - QQ /3 W s ""n,Aq m >, o g @r-y+ .a ' .. G yA*p V $ g g.

, . . s J.

s n, , . ,. p -

d

. /) s' -% ,T* #_ ,....

  1. Y. '

\\ 4 9., , , . - '4 f,.e+ T*Q Akj q' );- ' h,

' &%

6 pm . 112 . .

'M

. ._ _ -.. -. . , , , + , . . . n ' .

6 3..w) ' _ uestion Number: 70 Q . , , '

  1. 5349

- QUESTION: POINT VALUE: 1.00 ' ^' j.

.- , . . . . . . , , , , '

' ' ,.. Given the'following:- t; . . '. - - ..

. . . Anl inadvertent SI has occurred.

' fn

- -

. . .- \\ . TbgC3Shas eted,tr{epIar'dqperators to. ensure Feedwater . . . ' . . '. ! - %Q,, , L ' ? ' Is atio i ., , ,. ... . Ahr$ unknown reason, the ESF statufligbifa(e not iridicating l ~ T I \\ ( A -. hj properly.

' '. . .. - - % ' .' .;, . , ' Without the ESF status lights,' select the preferred method of checkingdhe status of

Feedwa@risolation he FRVs a ;LthelRB,DbuWVskincluding thgreason . . MSWM /A f g,./. auwsawdk&Q g $ " / , ,* fisiidic~ tions - They are; driven ' actual valvs%n M/ a.

Con a

h Controd,shindic..ations$.dn[v.en

I i igna~fgy$ g%%&st. $ g d9The,Wa\\g:gg () e y controlle: demand- %I b.

y 8 n:

. v ps g%p - A 9, p== - d % ndW AA m.

QQ . c.

r)dswitch' lights 7 ey<are nvenS9 va.lve. stem positionqimit .

h ( v. I e- - I. }. u%mp4Handswitch,pm<lijn isThe,1..z,2aredriven'by./jsmaximum or mi mi, - d.

\\: d'shiEMi%gIihldy 3$M . ,#5349[h7 lhe . ANSWER ". , n.

, . . .. (1.00) L '

Y f N COMMENTS:

  1. 5349 N

+ M-A ' ' ModifieBI Reseguenced all choices.

y,v( zs . . b . i.. e C'A.ontroller ha,s NO input fr6m stem limit switches.

a. & b.

- c.

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.' .d.

Handswitch lights are not related to demar.d signal.

s.. , = 113 , g

. ..

- _. . . _. _ ..._._ -. ._ ,.. - .

. , ,- . . . , , . . % %c-- - Question Number: 71 . '

  1. 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 im.4 , ' "B" D G.has tripp d on low oil pressure.' (/j./. - - . . . ..

  • * *

- . . . , .yY q

. -: Given t'ie above donditions, which ONE (1) of the following de j 'sdhe status of - . ibe ~ the'TDEFP n(Supply (PVG-2030) and its ' associated FCVs? / . , , _, . ,D PVGkO30 sagg

  1. Ed?@ JCVs 7j

' a.,5'[quiomatically$$$$$$A3) man 5idfi[kt'tidd[ ~ b.

, manually openeMY2$$fah localth[rN0hES5[ A , c M-automat.ically openedgsf f.. mmpg-m aw w'oper)"fsignal ,n; nnw;. m re_ceiv.ej

  • .1

' d ;ag - manually opeDedqdhaglyygen #gr wmm$ signal; y.

- m gan - Ws eceivefope . '; j:p r _ -- y 3 m ut a 2,9, m% us vng q2 m y; wr@Mf ? a y

  • g'x

%

y c.

j" $l h / j \\\\ ) Pfd d . ' '- .#5318k#r . COMMENTS - %wM h - - . . .~',[.a r.

- . ' / Risk Important Operator Action #2 (Rd: TWR TG1089 g/ ) - d.7b. Incorrect. Viv 2030 falls open on loss of air, reh' ves open s !oiEU.V. on both ESF busses.

U ' ' Y ~4 a Correct.)FCVs are.lf0. and receTve open signal on U.V. on t$oth c.

ESF busses.

'!4 P d.

' Incorrect. EFW FCVs Auto open and don't need to be throttled . open manual _ly. - .

. ;;5 ' 114 . . . ,M s-

y y y w a w-we t +-a s-e v - -* +- -- - - - -- ' - - - '

- - -.- . .. . - ,.. , . . . .

. d.....) ' Question Number: 72 ., . '

  1. 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 conditions.

' ' , ' , .o y tw,W) 3m) c..>w.i j

V*" r s . , While'performJng STP-106:001(f Moveable Rod Irisertion Test,' + , , ' TWO 2)Tods in Bank D group 2%ef Eclared Inoperable due to. ' ' ' + (-@ir$f{ immoveable.% jf.b d

T ' \\ i ' h; The SS has decided to commence a unit shut [owiTwithout rods . N.

In order to meet ACTION requirements of T.S. 3!1.3'1 ' ' . What ac(tions will be requirgd while huttl0g?dow qpiff jgg ' /) hA i '

.mm gj / . 1j. n ma 6tain programme $-mm kgps%g; Sg BorateMd;$ c2a Tav a.

- >% NW db* /% Diluteitojco&g!%p'py t g$. . ntrol ax,al fluxadifference%,qp %) wk

T \\w.e b.- . .c ap J i q sY h hNNhh:N%bbEh$$hb? U ' 'e' S c. dfgrate'toicontrolfaxial: flux;differenceP4 - .

% d.k'4.9 g.dif0te:to mainiain p,rogla hkhhhk 4"

%Q5ti? 44) W 0hk y N" f I --ANSNEp y

  1. 5225

(1.'dC) N'.% n/h-hN hir@% a.

  1. 5225(/*

9a yvDW + .. g gd.

- p-

, ,; /A. COMMENTS: ' ~ -

'fy g*, ',8EW QUESTION ~h# / . . At EObrihe power defect will be > the decrease,in Ze%non and require a . -

. dilutichMiich makes "b." incorrect.

. 4,1.

.

' Yb i [? is corredibecause need to BORATE to compensate for Tave a.

4... increase.

. b. & c.

are incorrect because AFD not greatly affected by

. Boration/ dilution.

. o: d.- is incorrect because Tave will increase.

,

',-

r

115 . -

. .

4.

m e y p r- ,ey.-. 4,. - .,- - . ---e--. -

. - _ . _ .- _ _ -. __ _ _ _ , , , .. . , , - . . .

- -

.. e , Q Question Number: 73 ' .u

, .#5224~ QUESTION: POINT VALUE: 1.00 - ' ' - .. . , A ReactorTrip and Safety injection'have activated due to low PZR pressure. All . emergency systems have responded proper 19, and reactor coolant pumps have been 7-o.

secured. = Reactor Cool' ant System pressure continues to steadily decrease,-but P2R.

' ' , level continues to rise.. - - . f&h Which ONE (1) of thefollowingphconsistentew& "k ; ditio '

.

iththey,e con . . l)/ . V . , , . k~hksiarizer PORV seat leakage:4% - - ' ' .. T a.

' . . . , bh

  1. '$-

h Pressuraer Spray valve seat leakage.. ) . ' ' - . < D 'd'*""" M@MQA6"ljj"yd*"*"""k, . . . - C ' , 9./m/ , re?ofC' RCP seal injection:pene6ation d.

, > yuy - pycn n.;u 71.ae, ANSWER * f3 ""gp]..esagg . - % . R Q1%phy,,4.R y'p(fj@g$ (i

  1. 5224 gb p

yy k a.

Qy

_' _E ' @g.

& gyne?p ' . s . w,q 5 c-

  • *. ' '

,. bMMIN e:.emE+$$fM

  1. 52$2h)

'U" g e m *I 55' .a n F "

  1. e*

., L NEWiOUES. ON I a 1 ~ s ! Nr - 'EWi hh % kb N% ~ Q ) Change $$je tbYn an fif$tidi$tr$f$5 M ! . ' Correct - PZR vapor space leak is indicated; trainee h ~ ' \\ . . ._ . - conditions give.n to determine probabia leak locati6'n. ?pust an <* a. e - - r

' ' Qw ' b.

Incorrect - After RCP secure,d, there will be nRspray flow so 'pfessure will not be affected.

p mr* 4..,1, ' , '

1, gt .

c.

IncorrecWheaks in this area would cause PZR level to decrcase, . . . 3 ~p-y, q r t d.

Inccrrect - Leak here would impact primarily on VCT vs. PZR.

. . 116 , - m .

..- __ __ . . t

. .% . %) Question Number: 74 . ' .

  1. 5319 OUESTION:

POINT VALUE: 1.00 . . . . Given the following: ' . , , ' The initial reccior startup has commenced following Refuel!ng

' Outage 10, pe,r GOP.3,,,m (-,, . , - % 6 s h 't 4 h; u t'% . '

. . Critical gbeen ta,.deta a,t110% power.wlth' Ban,k D at 142 s .

. ken.

m %f efj a r . . - Q)' %,.8 y ' - . , ^ The CRS directs the NROATC to increase reactor power to 14 , ah. 3%. ' g") , %,e % ' . stable SUR alloyyeiay@his point.of the sta . . What is Sjeynaximutp;W % bow should % (3DE& ~jF.M+<J // iods be ',anipulated? m3 b g '& ' }}& 7.%.o't. ??g ~ > - m ,s. ' 0.3,DPMp.f step,j 0.3 DPMR1/2! step.increme,,n,

L. s - u y a inc mn- ,, a.

- ,% (% - ! 'Yyud 4' %, ,y y ~,a - " - ts > " f., '.i;s %y {~%n., e , b.

. c,M,,,0, DPM,u..if step @anc%&.*h&j{{Q;};e - ._2 dgy *i&W () ~ n, t Ej90 f.n.,me.nts.an '<i," g 3 ( m re.1 g,.f b.

%%, -4.e... .. ,m .m ' g4TNp , d. VJ1gDPM,1/2 st6pjrlcrements i t @l'x/ 0*'T

<,

  1. 5319*j 4ANSWE.Rfp%;, ;w,% y u l h1 W 3w up m:d

.& s . /p~, e ewm w- .2 f.y p g/p[!J3.+MR5f O'~Dt Ly%b",h/th+h([Mt %y (-.}f.

. , (1.f0) ( [' " ,. m v.I..i ~1 ('j..i , - O '. #5319 g/ f COMMENTS:

,w

- . N( m % '- < rt, % l V,. . a.,& c.

Incorrect. Not per GOP.3.

W - ./ g..s b.

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 evaluaiad.

d.

Incorrect. Used prior to criticality.

. 117 . e

_ _ _ _ _ _. _ _ _ _. _ _ . _ _ _ - _. _ _ _ _ _ _ _ _.. , ' i ' .. . I . Q.)

Question Number: 75 ! .' ' ... , i -

#5121

. QUESTION: POINT VALUE: 1&Q

.- ' . l . . . The Shift Chemist has notified the. Control Room that 'B' Boric ' Acid Tank (BAT) has i . . 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 ' < PolitioIrtti's{& L) Lw Q l 7 r is k ' < - valve to the OPEN direction /and initial the " Verifier's- ! ' ' ' a.

klglafs" blank o'n the Valve Lineup Sheetq/ g ; ( { ' I' '

h. Reposition the valve and have the ABUL opere,f 9torTerform the-t t , . U % verificatioh.

' ' - -

. , ' ' * ' mmmsv%i $ $ )nq h %) pervisori~andve@positio(jhe valv - ' / - c.

I . Shift 1Su < - %(Q+f emg M& ,,an m l d.

Infor:Ti 155t dupervisor, repositiond e, valve to the OPEN - ,. + ] positi5h50iiiiilIjftiltiiftlie*"Verifie(pNMbsifIriltfaisjblan - N NQh % .lineufshiisip{ '

. I""' ANg[ER: (3 f[f, l_ k) U ' f.*]$

  1. 512

. , c.

' ; 1.0D)', : l [}1n O" hlG ,,,, '

( J

s.m J t a

- C0$ py hh f{ - e-

  1. 12 t __

t Significantly modified ['f3evise sten 1(angdistractor b. Also c'haked ~

, g y j order of distractors, Modi $. {ron, Obestion 2061.

f- ' '. ' . .qp.

. - . , .. ' Shift Supervisor must be notified before repositionfrIgp valve ' f,. while performing an independent verificat:on o alve lineup.

l < .- ? n' correct. -The verifier t aes not initial forboth operator l d.

- Terifications.

$4 . . .

?% x ..M ' <4

  • F

. %,,:L.

- p.f - . s , ! ,.

, . ,9 , ' , n + - , ,, 118 . t ! . . ! . . ~.. .

... i

u

...,...u.w.... .c,._-,.. , ..~.-...-.-u.-----e - - -- -.---------e------7 , _ _ m - - - . ' ,, -

-_ _ _ _ m . C.d Question Number: 76 - - . ,

  1. 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,ef.

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 . " I ]l , _ , ~ . n , n'the turnover sheet, to acknowledge that'!he oncoming watch a.

, has at least been briefed on conditions, and thertiell the h oncoming CRS.

v) ,

, % s . . Q b.

. Sigq,the turnover sheet and reemphasize major ite s ith the ' NRdhT5d $ dRI5![4'],:%99ff!!!. '/ o'ncoming,%.. _.4

f - .t.) l %,m.W.- '%y '.m.- ^ y %

  • ., *

.. Not' sign the tLittl@over; sheet until confdrifng with the off going c.

Supe'vis8'rE9 W:R E2;t; &:> c +: 'w S 5(D r I EW Wl ' awn;,J c; ~. ! % >n sa

. .m.

' $ot sign. (the,turr o/ehsheet until the/As.sociate Manager,(Shift km d.

%;n.0erall8risWAc)tifiddC9i.945@a /M 7,: i , " ~!S O G,.y qq::r.aw+[ w.xe%R %. o ,m.. P

.: -

%g mfp ga

w u ANSWER $fg %p g h [ % n u[I U s{(W k @Y [ ? ). fr5

g b. P.

rp,73-$

  1. 5227

' C < r t e u ea 9be TNYffWQ ~d@,5 [%N c.

  1. 522h[y\\

nW f [[. a w m = h h' , [f ' COMMENTS: , .

%.p.c.~1 e \\,. , a> . . -vv v' e,je NEW QUESTION w - % e.

. f% r /<.-) per SAP 200, Conduct of Operations for shift relief %>t s No , . y~',+ r , Yi v,. --

. , .b '.c% .- :x.;. ' ., ., pq ~ 119 . .

.: - . . .. .. . . t.

. . - 'r - . Question Number: 77 [ 9. x' ' , i '

  1. 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 '

' wa(g,\\#p?ta(e* ' Le / \\ ' . Clea, rTang g on brea r.r'emove MCB " HOLD" tag, open l ,, , a.. , " V,/ ' ..' .! ', - - b . . .s u t , , . . . dlear danger tag on breaker, open valve locallp'solear dang ,f . .. . . . on valve handwheel.

' ' . .. b ',' tiiksket removsk' RC'$ye handwheel, clear da Q c.

Clqar danger tag on ypj ' Vtg %, y - ~~~"jijifidpen$yy$ike, ' lit f j 4/ r/ ggyW e ' Cle]affdange, n fofrJa onggeager % t e lva-m m a handwheelt leavehalve in,ker, cleardag,%Q' . {n d.

- WamcQ@% position.

) , , presehf m, G.engx n;s.n)q; gag.Iy (w) . .% 5 ANSWER;q$p g ;z 3 *R W+ j ww py

  1. 5228.,

j . . f.

kun.m gl>yha ~m.S.

,& t, vw w.~ - - aa gpm

W) s

i#gt ft L, c. % )$iDN(M00[Wg g ! l11qlNOr a2Wd$;h' e<, ' ' " " $ T'2!@@M&p*Rd@hd[E/AM4e ? R;b COM91ENTS:d4 9 X 1 LA %/ </

  1. 5228)'.

' / ~h L b' ., - - Q NEW QUE5TIO % ' Incorrect ifnce($Yh!N\\h 1G.i b' % . - [' e. a.. not all tags.wo'uki have been cleared $ fore velve - ^ ""' 4.

.r,. 'Is repositioned.

s V.

- ,' / t . .stQ Incorrect since the valve should_ NOT be operated 4with a tag / hanging in the handwheel.

TA . M u

R6 quires e,xarninee to apply knowledge 6fjagging procedure and '# c.

., knowled{e!that 2802B.must be OPEN for" operability.

z, -4 j.4 g , d.

Incorrect since ' valve must be opened for operability.

. . u 120 . . .- , ..

_ _ _ . _ _ _ _ - _ _ - _ _ _ _ _ _ _. . . . -_ - - _. - - . . .

. . . 'T') Question Number: 78 '

  1. 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 Criteria.

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 switch. for this pump and r - - ita subsequent statusi' f p ** f d l 1 C Gf )l.

C,

/ - . . ', " - .. w

Ang}ra,nye R&R markur is hung. The pump IslNOP a.

o erated if needed.

(g , b.

%n orange R&R' marker and a red DANGER tag are hu g.) he pump is - . Q. INOPEgABLE and cannot be used for.angeason.I_ ,)/ ' A 35d@I hd [c,[*/ An orang @6.iR&R [har@k .

OPERABLE ONEY In 'B' MaintenandeMdeKWbut should only. tie',used I An orange R&R' marker an?"'..]W&$il W' b a' red: (*l' $. N % DANGER ~ tag are hun %. umpis d an9 iant MODEfbbjjhould L.2 erye$gyy s%'ijua'tior)g%g{y$m,7yy[ OPERABLE 7? f ($) e hE"[! [.,., y'QdNSWERDQ k d, d(e i ~ !s 9 .7 J} A

  1. 5306 4D i } :h.,f

. %NM y x -86O T 8%%(LOO)Mff : O L tsad a.

we u.a NePf M P

> v ' COMME $m :[,'/j// {'%5df@' f/} ' 3'{ ,)f,<(? S

  1. 530
  • ,

(/,f[y.Significantly modified fr%,.,)Juestion - p - . om e v- - . ' with all distractors. Order of the distractors was also cha&g)e'd 'ff) ' Qm SAP 205 defines an inoperable component tagged With an ORANGE "R&R Entry" Tag as inoperable but can be operated if'needed.

Y 4i , , , T. ' '?, -- ~,

P

yn . 121 .. . b

_... _.. _. _ _ _ _ _ _ _ _ _ _ _. , . . . , -4 . . . . . .% Question Number: 79 ' ' .U

  1. 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 se, cond d'g Q,Q Q('tiver /e/ ' 3 j g , ,- .y .T %,.?"perations repr6sen a a.- . ,' . 7'( ' s - ' . .

.b., ' f)/ealth Physics representative.

%g/ h ' T p , J[A, Any SCE&G employee who has completed SOT. *% 3. - , . - n . y - . . , , . Q d. -. Qealth Physics rep).(ese0@tative and-a sec ' s' . repIonent.ativeEffs $2 i@fW di? /' . g g g$n g g: M 3rdpBE%.*gvt .p sia e n.%%3h

  1. 522d

. ANSWERN r{p &p 4s cydy * Mrm;p.> - gn' e% s ' q wm % kb h % IGl h$h [( b.

%(*") , U COldMENTS%is%j@gh 7 - ' Jphi$ D

$B .m.

I-= -

. ".M ^' M gyl W I

  1. 5220)

- V&rfj ?' sis 2f" did F Sidhifdan}0^mo%(:?;n $k dddifi dIt $ p [ y. g, $ rid all1o#dr ek'31ces.

' U - l

  1. 3 A

= M. e* y mg

,'

s %*" < b, * e r OAP,408 IttOlii6Efl b61ijira"el2)ifEP)ysliIs#:individ,ua . . r.

esignates%,attw at poweEG hiil representative.' N' . . r} e-4 Ji v.. ..e# '/.j/r s

V ~ . - .. g - "g 6.t s g- , , , s .,ey v.

. - . O x) - - w T*- ' u . m $l* S.L.

-

g i.

v . . , . f.c> a , A.,. < ~: .< y%

  • n

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122 ' n - .., _ _ _ _ _. _ - - - - ' '.

. ,, , . . , ~. . . , . . .. , 9..:..

Question Number: 80 , '

  1. 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: . TechriTcal Support;Ce%m,% , - - .d > k.qi., nter.p m (" %

. gL ? - .w Q (/){ , 'a.

', . . ... ,, _ v* ' ... -

. . .. '

Syl 'Supervlsor's Office.. %. ' ' -

. . , Emergency Offsite Facility

- ... . , , $$"' $$s5BC$5flfl ? ' ' k/ . EAic35,h O . sh Vd

  1. 5120 ANSWERNfyjyr"u 7s

[Dp{jjh.Jw'

s d.

,f ) {IP If .b COMMENTS, $"?wgf{lj/$gyhi0 kbg k f b

1h)f () . - -, fS- "

  1. 5120)

. _ Sigh lfi# anti /modifis$;ffontQdest;Yy&?& f,h f "# j Ql>j py 'U ' , ion 1787. Re'viselfstem and dMtractor ' a. A)y&I: hah ed ordsOf[ dis' Ira ^cfors.

' f

  1. F#

'

\\ >%\\ bajmy 1 ww% ,% .

  1. was, C~;act. pp)y874%

~%ny gr y s to OSC. Fire B'rigaddfe'dd5Hrh'p(keams7nciddin n.

ivahon:-al Per EPPS fot l'(i.(f)%rts:topontrol Room until dSC)s e o'

  • [

activated.

P . - ._ . v.

. . g- .. n/ - ~\\ k# m e" 4L ,f.

},q ' n y - .

    • Q

. , t , *- ' j - 123 .,- , i

_ _ _ _ _. _ _ - _ _. - _. _. _ _ _ . . . .

. l , . ' [ .. I .

. . %... -) ' Question Number: 81 ,

i .

  1. 5230 QUESTION:

' ' ~! - , . All of the following are major assumptions made regarding Fird Emergency

. Procedu'res implementation EXCEPT:

- , < e ... - 'a. - The fire affects onl h~\\equ,lpme)%. c + y 'A - -

r-ntd opers% f**ds[st,eplac,ed by swing components.. .d ' ' 't ' e ible or . . i

i., All, j

,

. . b.

i ., 1,)/ '

f ,

- - . . . , ia'Itions as described in the proceduie<.canig'perforrhed as I' " c.

. - , /g; '; - written.

. . , . , The only accidents or failures'that occur are thosa,c% r ' '- ' - . aused by the ' ! .

Q$Gt$$$$$h dh? l -

  1. 5230 / / ANSWE 32gef A;ki 4/~[[ ]

4. ug$ % w#5e# . -M

i % - s f

m4 'Ogi ' COMMENTS %gi }=mq'iG8Dld7 #;!sgy2r % ()=) ! g / e ' f%., - R$ k

"' , ' <

  1. '52'302

. !yd mygg .

4,

.a ..J <w i 'TO3 . - _ ir$4 . n e in i p;w 1%gg ., / ! . NE QUESTIONA d;;;M

=

d

g Wc dsareNg Mf sted a6na'<}rf}asskmptions lo '

. a L6A a. Corre,c&g:^5 aApE Id r are y tien to.Jegpond tddires in either tra. ~EP-2.0, t M F E s,r u u. iry@ /,.3.0, 31 - Shutdo{wn an,o)dyr;fth'd;pla(t si 2.1 - Shutdown nd c[o. j [ f ,. _.. d*:cooidown thh plant using 'B' Train equipment) " , -vv = > / A,g. .,.. . ' ' ,

. N*# - %& p . ) k r 4 1' . TL b; Y ' t q ..pk c.t -

._ p

i + .

, . 4 . <

g~

-124 r

.

.3 ~ e Tde __. - . -,- ,,,. -.,. ~ .,. ~.,. _ .- -...... - - -. ---- .. -.. .n. .- - . . . . . ,-m' y) Question Number: 82 .. ,

  1. 5229 QUESTION:

. - . Which ONE (1) of the following is an infrequently performed test: a. STP 105.0'.4, Train A Slave Relay GO Circuit Testing ' ' b. 'STg-12.5.010, Iritigra57Sifiguards Test Train 4 ~ - , b r%f i i I L. 2 / f.. ' - - Diesel Generato(r Opetability Test . . . , c. ' ST -1.25.002, ' ' ' - y e,u,J - s . , , . .

STP 222.002, Component Cooling Pump Test , . sr ,

  1. 5229
  • ANSWER:

M, ' , , (/} b, - Q*%m(100) (Ndm m-g- G{f 5g t an##..:: e mth ~n f / R7K g;sti! h ,f~ f.,., - . m.:w h. w\\ m

n . WWW@Rq

.g %

4:g. > . COMMENTS:#pdh z

  1. 5229 u

MM dcw&+n ~k$.,,} h(G,p e% N. p. , n ::a p , ,N, NEW QUESTI,0Ngy ,e * % f ,y - w e .t v a ~. - Jl'. e:,/th pArt +A 4..ec., dim ;'%8' (Referen e: {SA,P;1233Se(m..,,e 1y w << - " 'N jig & ' * s a. %l Performed overy 2 days;Pg "%x:l'"L %. <, ctio~n A4 J' , N.y sawn

,

%vW R M y, - g

.e

/lh4 f C" "\\ b. h. 0$kh d?h.h $ h (Mu-/ W _ .' definitton of "infrequentlyD: ARe uiresdhe exan)tnee to apply;Mrji51 edge of testing for given%T5st"fQ'rdedthp) test 1s performed every 1 P'e S E e tg \\\\ , surveillances 'Fdis,ou t/ .m >c ij,q q e- .. . \\@r - . Performed every 31 days. wg,' p r,f~ r,j) ~ < v- - c. < ".s sk/ Wl.- Performed eve'ry 92 days. N g.m N4 s s, 8 A i= "5 I N,, f4 ?. x ig eq ., (- w

  1. q

- . y . 125 . . O ev . . . , m) Question Number: 83 'g .

.

  1. 5129 QUESTION:

POINT VALUE: 1AQ . The NROATC is attempting to vent the PRT IAW SOP-101, when he notes that a valve not identified in the SOP needs to be open to complete venting. The CRS

, decides that a one-time procedure change is needed. Which ONE (1) of the following is t.he MINIMUM review /appr. oval necessaryjor this procedure change? ' ,m .em LM [am,/ 7 ,f h'g p. .ti, - % g' g/ f, ut a 1 nManag,eer,* Operations. . , - .. /,, - a, - .V ~ - Q ';uty Shift Supervisor. g z ,.,g - t , , . . ft s, %'t Qualified Reviewer AND the Duty Shift Supervisor,/ f - - . (/1 Pyceh%. dure Gro,upjp6p+eeg~sorJAND.theElanst mew 7 . . ~~n f }s d.

  1. 512!],}.

yy h M ' WQW ANSWERf@ &j@d ', 7,,,,t L

Iw sy@@jfs? +

. 4.MW, +,,4,,.., (- t "F, - %ge,N.r./ . 5 p,gp - u c , W % @(1!DO)&> c' w .w r. / Vp r:. 7,4 es. J COMMENTSi&g/,g,,g:pc?, pg.w v (**1 , R Q Q *i Y ?$ $ $ h $ ? & ll:9 D MGMWa & T q

  1. 5129~,

E ff{ . ()) Sigolficantl distri'6to^r%ymodified;from Otlestl6n11898. Changed' stem w w:trwy% w w[- m aldnd d.dyj 0 l! I / ?/"" M r e'go.gS' f = WgF' %9kr;9 y%

a temporary chap. e to' del.e. rm.in,.n. 5.one31me c \\ }\\ Requires examine . m. hat - ss-et , - ?, - ge pn(the:nnla ~C.{{l[&ppf. th'is'to requirements in SAT l-139. es;y, V,. Qt ,G,3 - ~~ \\ '. / e. SAP-139 requires a Qualifibd Reviewer and the Duty Shift Supervisor as y. minimum review / approval for temporary approval of a proce' dure ' ' ctiange. $) , / %% \\ v> :. p- "'ss", J-~.h,A

+wl '$ , a .d.q. * .5, d. ( ..,, - -

y

. = 126 . . w _ - - - " _ __.. .- _ _ , , , r . . . l - ! ' . t ]) Question Number: 84 '

...- , '

  1. 5130 QUESTION:

POINT VALUE: jaQ ' ' ' .- . . . . < Electrical maintenance has requested that an individual stand by the breaker on "A" . . charging pump in.lleu of hanging a Danger Tag on the breaker. Which ONE (1) of ,. the following must concur with this approach?

, . , ' h. ' ' Aqlpin Shift SuRrvisoD c1"hg[. i ! I u h sl.L.I I k , ~- ' - . j 1 OtityJhift' Supervisor,. gf[ $% . . . .

' , b. - . - - , , %& ' . . ,,cA. anager, Operations. ' fN , & / , ' . y - TL Manager,' Maintenance Servic'es. %f - ' . . ANSN @gss@k[j! g{j7 [

  1. 5130f

. . lk/ sWNX4 jyji g

N k '

  1. 51,3(

COMMENTfhj[,; i$h6 R{ j d b 5+ . Nhh '*h?&J f odifi d,frord QDestl6.)v?%# L, k , %8MT& ,~.,!d y~ fr - - ~ Sig dis #qlficagtly R2285MChanged the stem ud" aMr~a. CHAEgWhih;56b'di$6sisn'r.35"Dufyghift Supervisor # h t

Reqh,hhl!9 rgstexanzinee;to$h k $ I h N, determine ihat the

dcb7 . d h]# definitioifdO$Mur@is'dut@S'IS?;'o' a6Bedia*g;T SESAPgf0f'(Section 6.6), t% SuperviNFlidisEt' isTe'sigies; therefore, CRS loo, \\"\\. ' viablo of a choics)is[ths/dhi 10-lo pio^ vide concurrence witfi.(Human. . Red Tag. D@gT Y - , , . ... . . . . . .

fw % t ,/ [tw/ , v.4, %' y, %p n%. , . y%. - x se ., y r7 y .

eq

- , . .,. < d 1. ,' % 127 , - I - . -

a - - - , - ,94.- y -+,- y- - - * iw p9 w w yn, , y ,.,-y-,-_----,3 ,- ,,,,,-----+rr 1-=*e---- -ne-*v 'e-4F--%*-e u, ww . . . . .. . . .. ' ' m . 'g) Quest. ion Number: 85 - .

  1. 5133 QUESTION:

POINT VALUE: 1.00 ' . , The RCS has been' cooled down to 130*F. Prior to detentionirig the ' ' reactor vessel' head bolts, the RCS must be bcrated to a minimum f of great'er than ' ppm or keff must be less than , whichever is niore restrict,i.% ve. 20j0Qf>q.ki{*"iE:(Q,,'* ,: cm - ?i - a. . . , , s . . b. 20,0_01 0.95 s,, . - g%,,(4 . . . I 2500, 0.90 8./ w. . , $ ' V'd. 2500,. 0.95. .- , ' ' . _j . ANSWER y%pSDgw.,;tp;' 'QQ"" h"g,7 MN Q SE / ' '

  1. 513hp f,

g gy . N .,% - %g64% namq.pa ' 9-Sib. kl$ &$r f'-*;y. }&&h~ ' 1%e b'

' COMMENTSi h 6 %:.# g .s p %. q u a (, 9/prsy ! fg w -, -

  1. 5}33's

, SignhficaNd bI $hdY$h$n Changed distiEpc.t.orhFd'/;$,y. "cf45dPfe! i NNn 165 '7 N' j (]o) Nje seqGsncede hoices. c < ym W. n u m.i mm1 .m e kh Ih)hfb ,h4-3 a &id J% 250 yppd s$; un :%,.%.morethango)hpi % &M..:p Y'm.d,,&. acygg wg Rig Q A y 14 0 *f,, *'and a t\\\\ b. IiE&Itfi Mamlnti6Eto 6stidrmine that < g f de't en t i6neq' hh'ddPM'Ws si f 9['rement s f or R ef tIelingfiir M and applying'n'9W)T#in161mbmMe' qui t.# \\

SDM ( T. S*. 3f GOP-10 and Tech Spdc/re minimum of 2000 ppm boron er Keff less.itha'ri' quire

/[' - - ' -

95. /' . g Keff.90 is lower than required, de ' / 4. \\ ,74t v. '""* h Ak.. s'

f,.,t * .1., .f 'v v . .. u f 9.~ - . e 4 67 128 . . . * . .. ,,, , - -- r w - e m c. - -,, -,.- ., , --- ._m---- -: -. c , - - - ,, - y y + % 4 - . , 921 W . e - im; -

+.

.y. % >"'3 < , - g/.g 'i

id

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u g . 5~N n/ . h.p/ >

.d s .v . . , v

. . . . tg5 ~. &g I) f% .Q < % w t. p' .g ~ "

t i ffr JV /% n% \\\\ N, n,\\

.t,.n N.\\ l'.q,..////.

T/& . I ,L. 3p'. s;%mm'9 ;p%{ )A.y:-.2 ' v %e A w - Aym y[

/: , t - w-u ma.

  • W~f<iR s#{

eQ y3p hww %W mh ! nh,;), 4 %" ,p*)/ hjl ii V }$kA de M;y".,.TW

p l.4 % "'n@U. '<Y$ykp7;p@i2%,d,.5+Vb5$u$ DC A ! ,N ' 2-N 4)Q;QM.v $ lggfg?Qy@-.iNOITSEUQ:, WEN j dic }d% ?$ '"*""t h .y, v%. A. w w , ' t d p s p r. % p / .A [Iidhe DSITtEMMOC Pr2325# N-[?D@Wp$frPf h.l(MIM;SM 7.}. 4 ) $ m Mp i%O .d ~%W:BN

FUind$SPl;P, '1R(%,le g% %f( N.v;m% / o%hS.M g AN. .-

4(n:a,[??. xim Wi%awM M m( MSkA /2325H yW w ' $ ' ' ~.nepo ed ' ' .'esolc,lel ar.%, . , - a .c "A

' 'g/ , i - Y,y)sbireS .b, I ds. %' .nepo

V } iipic k,p , ge% . r / ! Q( *[* } (h

. .* U be seireS .a ' %q )i ' s m. e i,; " j )" ' . . ' lliw taht ' ' ni-,B511,e-GVM ot tnadnuder,~evlav a gnivah.yb dengised si,n.m'ets'yS FSE eht cnatsmucric ralucitrap siht nI nep6 ton did - oitcus > , pmuP gnigrahC ot TSWR,B511-GVM taht seton dna IS.launam a'htiw langis citamotua eht pu swollof CTAORN ehT .gnitseT SPSd gnirud hbtiws a gninoitisopsim fo tluser a sa srucco'IS'tnetrevdani nA ' ' NOITSEUQ 2325# .:,.. 3'%' ~ 68 :rebmuN noitseuQ - . . < . . .. . . . . _.__ _ _ _ _ - -. _ _ _... __ _. _ - - - -.. _ . . ,

, h e ' . ' ! C9.) Question Number: 87 ' ' ' .a.

  1. 5048-

- QUESTION: POINT VALUE: 1 00 l ' . i - .. . . Given the following:

- , , - t ' The plant is at 75% power with rod control in aut'omatic and '

- , pressurizer pressure at 2240 psig. ' ' > . DuNlog/b (#1 LF iluhths crew rnust rapidly reduce - ' . (joid (at 5'd/rnin') to < 38% pow'er'# j3,c0 r

  • '

fo [ - - > . )V % ,4 . . , '

-

- . . B RCP #2 sealis working as designed. "Q [

A', During the power reduction, the ARO falls to eng.v~l e , .

. . ( ape th l , .g d.ecrease load rate circult, d , - Aftef.the ARO(R@inSYMENW %;the NROATO notes l ' $8% r"4I' / ' [f'**f. reduces LOAD'SETitotSO ' . PZi preEddin'ireasing boths hea(tu$?'lQI;[6f h %plrliff0Alseh open, and backup f% G%9 $.. "" . WRgth%M (R

. A fewifilid ~ g{aterithe,NGO4TCISid[P 2@" E i t w that PZR level is'd$% - ' ?@g and dedrAsis ng)si8hgE!f%s$N}$ . U - %vpwmb pg<a . at my ha. ] 7; h u . s - The ackup heaters; tare energ zed.beca ,p e %. i; N@q - ~;m 6: 1 py %m$d ~ A;p h, y - t %. ,f Ww

d}~K@tage$idsiirg@eri t JhEPZR(cdus h} b.~ 1, , efeEltin ' a +5% level dik/lation. . a. ' ^ D . gustTQP % The resulting oWs' urge iro ' the",PZR caused a 5% lehlN , ' [A. deviation $I %)J [ (iV - , , , Pressure reached the low deviation ( 25 psig) setpoib< , . . . ' - A> df) The rate of the change in PZR pressure causes,the control - d,,1,, \\ circuitry to turn the heaters on. , "\\}"

~

. . f .]<

  1. 5048 ANSWER:

'N 7? 'M . <m . , , a. (1.00)- . L - #5048: COMMENTS: ' . . b , 130-

, . - , l . . i __ - ~ , w w - t , ,-.,4- ---4 ,s,__y n._,-. ._m,_ ,,,.m v .,,,, m..,.,.w., -r-.mmern,,- ,eny,,w--.., , ,,c ,.-, . . . . . . . % Significantly modified - Changed stem cnd distractor d. Resequenced "F' distractors c & d. . Student must relate the effects of the transient to its effects on the RCS and PZR level. - - - - . . , . . b. is incorrect since an outsurge would not energize the heaters - , is.i.ncorrect sink.~1her,*Is rig "R, ate,", circuit associat ' d. is p - . sgc r pressure an3 heatqsp, , , g , ,. , , , , c d"is ln$rrect sin' e there is no indication'of.fallu*re%, '.. ~ ' " c . . j,- - ~ ~ - , , s, - i . . ~'\\. . '

. ., , SUMG%$h$a--@d$$ ) ' $w*y*.g(,';40)+Q,Q[

81 Q (" !. -- n ., pr. nW / ' Q ~ g m g. g' % ~ [I,u;,- .; %e a m.. p,io vn .f. y + . p.s Je. N$h, b j.d,M;fg ' [% t lN li'%g, p f %[hk"[yj[fllRM% ..- w a a . / "*y* $(bb[kb, 'bM P - % c *',W f' % A5ctmI }4d?U!O.Q' %./ .eem j Lg , 62r3 /j hf d.' (ud' b J6$@ifj@@{g;M@t W: . .%. / Fo s$ i @j. # gt p' M' ,) QN$1 Q$ s% o df 4.r]-> g# egeu_awMg::fkkhn. tn,,b $[ a d, C e v? %an/Alb. 4 ' '\\ *,*e**4,q u W a \\- m- .. . c, iW,/@L'm n \\% x, 2. e y' . g-s- g . >' g.y .x . . g. . ~.. . . 7) y(s ,q' , h. >h r,4 T. D."z . , 3V .

  • '< L "

x ?. ., %, .g ' ~' * y , e~ w; $*Y '

,. 131 . .

. .. __ , . I % Question Number: 88 ..u

  1. 5217 QUESTION:

POINT VALUE: 1.00 . Given the following: Plant load is currently at 43%, and the crew is increasing power - .. IAW GOP 4. p%. - c. Antiungiato X5f 61&[} binIR,CS A.OOP B FLO LO",is lit. . c , , (Art a!6rm is also received on XCP-626,'FJrst out Panell

- . . . no y A\\. vThe NROATC verifies that flow is low . I' s n , 425, and 426 (=75% nominal). /. .\\ > , (, '. . k. en ? . .

. RCS: pressure'i(In _,n. lowly.n# 4,p r/ . creasing >s y f ONE (1) of the follo$!D%T SrP9bE# M$ 'A Al/ $%g:n y/$ h/M,should the Contr'o wing. actions Which'cbnditions: S i fMMM (",h ' these N Da / :g:v&T,e' ' eg%,' m (p,;s d the reactor:;;a;l1" , YM s ' h. D :# 4;.r 9 Q. lmmediately, ~ manually,tripj&yys=c1Q (ud) i a. s l" * . (f,~") b. $,, A,_ tQMfy?,y 4 o dm nm, n

  1. a n

x... 1mmediafm$;manuallyJripithe;teactor ancj;toltiate SI. ~ v A(, e < c. %. a LGJ~O ', g L 9 Fp. y i',.<py.,? , Lo m . . n .. . 'EIRbducs power?f ;tess chan 38% and ty. 7~B' RCP. h+e p -* 0+- c. 'N$ld]c$k?:l'less;thari;38%y0$b'(' l: .% $W lt 1$ (fl4,vll'f k: manually trip the re and e Re u e tbwer to i d. G :! Id

  1. 5217Vl ANSWER:

l N P M-u4 - w v 'i s,,* . . f,/ja. st t* ya> . (1.00) f% * ' /3 %)

  1. 5217 COMMENTS:

"q b ge s. ,, NEW ddESTION d,A. , ' ' $ ]'? Requires' examinee x.to analyze'that a valid reactor trip signal a. exists and determin'e 'cwhat actions to take. b. No indications to support St. ' ' c, These would be the actions for a #1 seal failure. - - 132 . . . ._ - _ = _ _ __. _ _ _. _. _._.._ _ _ _. _.. _ _ _ __. __-._.,,. ,

.

, , . . . . - i - { D d. Would not be prudent to decrease power prior to reactor trip. ..d , , ' 4

+ e 4 $ g i , a e $ . -, peg [t 3,l r_,. . .es,\\

.$ /,

  • )'t

' t

u L }

% t s . fr .. . . . . d,pP , b . ,, Q, y , .. r , , - - ..\\' f/ ' - e .%. b T

I . % r . , wir , , ' h$% e, e,m Wi~p2 MT h M. 7 ./ . ' en f. % . +~.r oo . be.e,. e,,p u,.m,}g,h Q,,, . m' g 's' O ? - m y ' %j ! '$,' lih&g }r;. 4Wf+'~s f;-'.h? l n cva/93

p$4$Y[M vb ' , %M)?.jll,14 l q~wh w , Y6 A , f q %s.,,A. !Q;Mn}%9 . !! - % Me9# % se 7Q T,..y:ribrq c .p + M4M+~r u.p,fh8)e.fM#$:,a@[v?.,d.s.my r. g,e -h2 (g,,g) % . tw n[fDRfind4fN;WlEN / .e**} ,% . * A - ' g /. $w\\Wy[ - n) nr s-=. .m a '. . Cd5'

        • "

4.. QJ b p ht @,'y d % M M,5 K O G L1

t i" M4 - r[Q:dghc , Q %[p$%) %,, , "W*C 1i

iK W+ O~ 4

/ p"f A wkW g%Tr%@h,#k 2 { l. bi

" 5

'+ d w ,

Sw$ W,/ 7, //A i. - a.,,y w 1 em g.e r U+*r<"tmun9,'-{wt:n,,J own .re: W= \\ ma g, /s*j%% . [,;#.frVf*, ~ 2;M* % h h.?p.k.eif:*%q %,,s!1h.,> [.E ' l\\fe %*u . wg n a-I . ,. g, .. 8-y,. g . . ,.. . . v,'im/ O - w . -Q + < N g u . - A f' d 1, ' ' e,.,/{" l,, V ' <y. ., k .C ( A , ,c r. . , 4 9 % ,y ' 133 , 1 4

  • t

. _ - c.vn-r - - - -,. -- -- y y,..-y-m- ,-.r- .--.~m +-y,-+,,w,-g- --gr- ,w--- v- -, - -, - .,

..

,.,. - . , . . . .. ., -; ,,y.. .,, .. ... . , , . ] Question Number: 89 ' '

  1. 5078 QU$STION:

POINT VALUE: 1A0 ' ' .- - . . . ! ~ The crew is responding to a loss of all ESF AC Power per EOP-0.0. Which valve is C locally closed to prevent limiting personnel access for loca! (ensure habitability) - operations in the Auxiliary Building? ' IA\\(p C h((RB CCDUL)PLYWEADER VALVE 9600 C a. '., ~l i ll2 ( f / e, "' - . . . b. MVG 9GD6 CC (RB CC RETURN HEADER VALVE)

  • '

' - . ! c A-8105 CS (SEAL INJECTION H ER OIATION VALVE) , . .ah 'I ' /*Y ' d. MVT 8100 CS (RC PUMP SEAL RETURN HDR IS.O[ VLV) . ', . + . &{- % ] &% {??$$$$$$"m?m%. n.,8$ .- . . f - . r</,.,*4{.ANSWER?'% e#%.m3 W% T*. ' WW e s. ~e m RJ f# W.W

  1. 5078 W:

n%%m;Sq 49, ~.,} bb ' & ~ . 4% ew :;w eq h6 d Y g + %, N; a DD k.6

~ t / .,% n? g @ (m; /./A%m i7 ?%MpMr%g$W 9 ..m

-~.,

A

  1. 508)

Cg(MMENTSg'$h[M/IhMhit hIh (2i77 M[c ~1

f$

,) N Signidc/N . . hhtl s Also%hEng/ modified.fChar)gbd stein nd or[ginal dfstractor d. D ' ed?ordet of^c'! dices. 7 [6 /M7 r% e .c 4g ,ht %3 pg.pg( w(anigM,, ~ y% s e y &g

.;fj t

I Phase B Conta v.a.,lv,e:ls:no,ll,iosed t,o: isolate seals, bu Incorrecl3. +This a. J ~ ~ inmenty.eolation later in EOP-6.0. Alsosa check valve prefdnts'floWin this'.dife';tib6. - I ' d c - \\ y, w- . . y \\ . . , . . ' / b. Incorrect - This valve is closed to protect the CCW' System from I) steam vold formation due to RCP thermal barrierheating. y& / . c. }ncorrect - This valve is closed to protect BCPs from damage 'Wiisn starti,ng a Charging Pump,during recovery. . <m .,.. ...... <. < >s . d. Correct ~ Trainee rhust.: comprehend the bases of EOP-6.0 step for isolating this valve, (vhich is to reduce radiation levels in the Auxiliary Buildirig (habitability _or personnel access). . , ' - 134 . . . . . , _ _ _ - . _ - _ _ _ _ _ _ _ _. _. _. _ __- _ ._ _ .. _ - -_. . 3) Question Number: 90

  1. 5300 QUESTION:

POINT VALUE: 1,00 D/G "B" has just been loaded to 2500 KW during performance of its Operability Test (STP-125.002). Which ONE (1) of the following describes the response , of D/G *B"if a Safety injection (SI) signal is received under these circumstances? - y ~c n ,% e. sq 41 s D'/G, *B",lmrnedl aately sheds ailload a'nd shifts to the ' r .- ., a. ,EMERGEfiCY START mode, " T..j/ ' - - . dj' ' %..;1 w ' - l h E .,A,b>G D/G *B" immediate y s ifts to the EM RGENCY, STAR . and is loaded by the ESFLS. ? (^3 NJ,c \\. - . . (r3 c The D/G *B" engine trips then,ltestarts in the, EMERGENCY N RT,modeJs~niffs(foad5' b?s,ESFLSD.., 7/ ,Y. d thi t , ~)? v :: ; s.,h. y, ~ - ~~ ~y y - .? y-n.c y The D./G "B1':c,o. gin,e trip..s, then restar'ts'inithe EMERG .(* d,' Y . m. .

  • ,

.,/ ( START mode. and runs unloadedt.. '; (.y;p g 3 .( e

u. W ms-,_ s > a,

p.s , .,

  1. 5jGO,,

2ANSWEF3pfg gg- . - gp Q g(f. W;g x ; ds,.;W y y.)< y [+1iOD)m;;gg,j: U,e) a. W.7 %w,

, i -

m.u;% >

yCOMMENTSr'M h lt ( A,.;;n , . dw . +~~m; (. * : _w I 4&N % ya.w,,. a . n.. . h I, r f p. m :.~y./ n:~*

  1. 5360g

,_ b t .3,7 t, /.%..,-l, s ; ". ' 6 i..~. ". ~. : % w)< _. _ _.. v .. rr + > % C'orrectAThs D/G breaker (trp#s'under.these con Q-a.

{jk;%%,Yt(/ . \\ #^ ', b. Incorrect;'The D/G does. NOT~liad on SI /.J, ~ ' \\ /p/. .s .s ,, . . these conditioris. The loading sequencer undergoG ' Incorrect: Bus 1DB is still powered from offsite so c.

s ',.

es 'an St s ) / sequence on to the offsite source, not the D/G.S u N ,~.. d. 'fhebrrect. The D/G engine does. not trip +under these conditions. , vt a.. . , $,. l '

a- ~. 'W . 9 135 % -- ._ ... - . _ -.m. - . _ _ ___ __ _. - _ ._ _ _. - _ _... _. _ _ _ _ _ - - - -_ _ _ _ . , . . . { - Question Number: 91

  1. 5080 QUESTION:

POINT VALUE: L.,@ Component Cooling' Pump 'A' is running, supplying the active loop. Component Cooling Pump 'B' is aligned to the inactive loop. In this' lineup valve,MVG-9503B, CC to RHR HX B, is maintained: - a. Cloe:is to protect. the CCW pump from runout conditions d(frins"'iinTSI. signal. ' .. U, g."' yQ y t' l~ , \\,. Close'6o edsure adeSTa(te[RHR/ pump seal cooling , b.

, withirl'ONE (1) minute of an% ~ ' ' Slrsig$ gal. . , . . .} %s

i s , ch 'Quen to provide cooling to RHR Heat,ehchanger , during the injection phase of SI. / - m.,e ~ . > d. Open to prevent deadheading,the CCW purpp 'when %r '

started on,arSIrsignal4lRy $crYgg gj nim $bwyu 6p., @e@dDWhd 'A /~! ' ,,-ram o ' ..t ge:Y S Qv ANSWER: n zu g% g:-f ~d? x

  1. 5080)

W J F G M(t+Wb'mrw & ~ - ~. ea dB.$h2M5M* $ b [CYI ' WM[

  • t d

d. W(2000)F , '* % %

g
w

/ L d Nil@y.at.o.%se4h!!de/g_fe.d:.r,;;r (e)

.ex., @ I M. - -%- . o ' h O' kN. evrgm w:3

f /,hif f RibhsImportantNp)erstor fActilon'#1 s'ik2[.7 TWR TG10'894) %;;.L;su s,r. t IVf ,i e ?g %.w am,r s significa.a,~dy(',mo.. 5 n (m\\ a...m e . nt diff s-nChangedhat~em and order oft .A choi dep66Added h riss1 dish;fseterJg> ('es/dlI,i@y'athliffnot aligned to,n(% kg " s i /T ' CCWloophasgnoRecircj?N o n '- ., g,e g /. essentials. " W 4lf (,A - . . - ,r%)%s

. % / r '. A ,5 - 7*%gmw* j / h %,d Ny .. k , .,s.,, eu -. , 4 .-

  1. '

bq .,. -

.x N

. 'E g y 136 . . .- e-y-- , - -, - , y w--- - ,, ,r- , - - - p- -, - - we _ __ _ _.. _ _ _ _ _ . _ _ _ ... _ _... _ _ _ _ _. , . . I Question Number: 92

  1. 5081 QUESTION:

POINT VALUE: 1JQ t The reactor trips during a Stator Water Runback from 100%. The protection signal generated from the open Reactor Trip Dreakers

will cause each of the following valves to close (directly or

indirectly), EXCEPT: '

a. Main - rbine.4topayal.ves ..,4 s b. bd "";},a(Dumps)*! Bank urand1 dan;k ( %,..

. b. Steam - s"' % . p '\\ V

. c. \\(%,'iV,Feedwater Isolation Valves when Tavg Low . ' " Ma ! . Main Steam Isolation Valves when ha d(Low-Low .~u R '

  1. 5081.

D (* } . \\ ANSWER: - $fM!@ f . f if ) d. . exr m a v A.~ 5? '+a COMMENTS 6.y}f< /MN,,Wi?

  1. 5081 d

NEW QUES'GONf[yl;f d* h.Ut,'gg.dQ@jy (A N%dC' i$$[khfhY P*= g g e rG0M \\ V M:M / n '% 6IncorrectM P4Iltc..auses;TurlMne trip. Turbing%jtrip - % F=~- id ip a. jhigndl%1'6sesial-lf.scip)4alvesi . t L,,, (./ ) ShBank 3 and M(M IRM

  • ldh 55$M$p/

kNbj

  1. '

b. 6 Incorrect (WPp4 }@c[dsesibloc[k of ~If9 hIjva14fd whe$3.n[Tav(Uiph Bapkt/3Mnd Bank 4 dumps i$d'. Dtimp e tD d6ddin th' Mcas'e) } # i t k*' " Aposaibl@dp & Q Q\\ edj diiring cthe"xunback. ? W '3% "jfli:3

  • ?

Isolati6h sIg,n'4hw3t;it los,Tavg causes Feed (wafer .

Incorret:t -rP-c. V 51IWhich clo'ses FWIVs.

(*A*' - \\/e ' vvv . ' v~ .v. . - r., . //d. Correct - High Steam Flow with Low-Low dhvg is a 6.e S, Steam Line Isolation signal. P-4 has[srnch impact. % / ds , s ,, d. > j'{ V , , , me^ wt <.

_. ' . i.. . -- ,

    • g

~. > e% t . t O 137- .. .. w -,,, ,--, --.,, , ,- ,,,., ..,, -, - - - - , . Question Number: 93

  1. 5083 QUESTION:-

POINT VALUE: 1.00 Given the following:

The plant is at 2-3% power and holding, awaiting power escalation because the MDEFPs have been ' declared INOPERABLE because the wrong oil was added to the<pumpsbubblers. - .gt..s D, r f ["j j n. f'T f e

The contr61aswitches for'the MDEFPs are in P-T-L. . " y y* Q_jf

s(~Th~e'#rDEFPpumpproviding300gpmwl.ow. f

a s M*% Suddenly EFW flow to S/G A (FI-3561),pNincreases to , " s 780 gpm.due to an E/W line break. ( ) . s v, f(asume all automatic.factionc> occur + as dI i\\ n. i e J s,/ ;t D d;h 'Ib.A A NNN.,$pI(Y % / ' - , ms

.. - - - Which dNE (1) of 'tikeYfolldwing EFW operation undes".these conditions?W L ' @ describe's? subse"qbent l ( ; + <rN q) s ~ ' :;8 1 < %,.H, t .

a ~ , ,N',, The Y1 TS/G EFW 11ne;will'beifurther damages'by a. > w. ate'ri hsmme'r, duE..tdFthel h'i~gh? flow. (wj j. A , i mm ,. : ,,y o ,,. , hw) b.b@4 The TDEFPIwl'll'xstilGdel'iver'th'efrequired desi'gn % t ;m-c '.. ym e, A, y a .3 m., .y - i.'floV,jtoDCindj'C',)SGs.T-t,4 #, P7 4b c...n* 3, .r.-~ g.s % The.WD.EFPawillif a. l(q L-ue > toc,.op'eration at runbu,.t g. ye J. ,. e T,. r, t / p,, f 7,,,, s . c. f. s,I c. '3 ' + m 4 .t . .n.-,...., rr. %) % , m .a ~ e "condita,,onsi " (\\)i The water inVentoryd)v"'}M ~~ %*' %

lyj,g Q z (*i
5

. n<thelCST will be exhdusted, d. V. leaving %o safetyk dade-lsburce of makeup %ater. g \\ /, se j . ,. ,

  1. 5083.'

ANSWER: y x ;b./3 %.

(1.00) . g, N. ~ "

,- . \\

  1. 5083

' COMMENTS: v .;,; ~. - Signifkcantlylmodified. ' ' Revised stem and distractors a, b, & c. N ,! . ,'u a. Water hammer not caused by high flow. b. Design basis assures 380 gpm to intact S/G b; limiting flow to faulted S/G. T.S. Basis discusses faulted S/G. 138 . _i. . _ _ _ _ _ _., _ _ _. _.. _. _ _. _ _.... _. _. _ _. _ _ _ _ _ _.. _ _. _. _ _. ..__ . . . . , I '

% c. TDEFW pump design flow in 910 gpm, runout flow is ! higher. High flow interlock shuts FCV at 730 gpm. .

. l 'd. Service. Water is a safety-grade backup supply. ! , i . , , .

t a d%

    • t, y"*%

'

r

,, .. ... g$ 4 ' , .. m> g ['s 3 '

' ' $ O . . . . 7 ~ i !t h / f N % $ $,k E ",,s# k . ' ,4 ~ w4 . Mykhibfgt9} INis ! ' /%

+- %4.. gs!. m+ / .J w, &. m.,,, m..<;os . .,. wn - g

,r 9sg ., ~ 3 *;w - ,e, ! wo v,y p> yy q kAfh$fy,4f*f{l fbf '.?,fb g g L c y q p o. @7 9). p ; b. %.- +p - . l . . . , - . w .g .tpgwe, :n < yy y y s c + eepy;g a s > umm v,, :n yevs An ne ag - e. s ,> n , g, > .. f h?, !kf* Ax, k [j 3I$$$N NA , se . ' - ' u- + - - - , . . . ' ' , _

  • /

' , %w. . ,. . %'!'t k> / t . '"*J . 4, A, 8;'*.k * I *.?

jL ,, +r <%4 ,,,,. - e,, , e'AN ' ., , 8 4 . 139 i ' , e 't 6 b ..

. _ 9y 4$ ei=- r-1ig-= y =y+ys-r- 'y g-w-=- g gi vr=wr g'% v ==+'v+ = +t*w4T 't-T+rW*

w Te-Mnr w e

  • -1'w-v er -

d'*--w-*

  • w--*-

- -+-w-emv+ -r-=+ --r-4 P - . ' i % Qucation Number: 94

. j

  1. 5086 QUESTION:'

POINT VALUE: 1.00 A normal reactor shutdown is in progress. The following i

conditions exist: ' e 'B' MDEFP running. l 'A' MDEFP and.TDEPP in, standby. e .. o, ,,p g rg pq f.m,~' s,. 75 gkm"E{Vtflow suppliecl,~to5 e,a'c,h S/G. e .  % v* v/ , s. r /G', levels - 60% and stable id..ali]3(S/Gs. ' e Which ONE *(l')dof the following describes the prop,er,s . EFW flow and systemrsiipdhseifaspurioussafetyInjectionsigndldecurredat this t$me? Assume rio operator action. $rg ib.% emwn~v. tW %f") .q %d 75%pm,,to eachhS/.G!f romsf B"? - ~ MDEFPA only; EFd flow

/ a. J././ co6trbf"Oa19e's (FCVs) '6hrcttl'edM

  1. '*

- acc 3-u r e.,. g v w f . #.,:: WD ~. s '* * m 7, ,1 Je 49 ' ,~' Approximatelyl'/150"gpm toteach1S/G from 'A'(knd 'B' r. ' ' " " b. p% MDEFPsE6nly'; EFWgFCVsy,bhrottled. % ^

,y.a. n ,- .

_ p.; ; % * y g.m , / Appr,oximatelyN 275}y,, ,. Y L.,. % ..~"e v.s yt o -- gpm to.feach>S/G from 'A'fand' ' B'

"~ *-

c. ,m x lI p fMDEFPsS6iily{{EFW?FCVs0 fulls op'en..y.,, Z.3 . ,l - ( . w,.m g w ~,. - & q;w a9% j ., g. p.u ; - m,. 4, p m ..a n,,, d. 'p^Xpproxim,atie;l'yj 550! gpm"to ? cach.'S/G'f rom ' A' afi& ' B' ,. Mlpg L.,4DEFPs andSTDE5'P"; !EFW2fCVs ful-1"bpen. D-ei % ry ni %l h fy.".h l[ nyy %$ r . y &hlb50'& l[s // n,qf{\\t\\':J w,,,d[$& 9// {.h ltj , '"$ ' Q' i - ' P. %s

  1. 5086#e ANSWER: C.

u< i u.l < bl L r \\ A ./ n, q/e - . -. , e'7 'c. (1.00) ra N //'..~. 1 . r < ' .

  1. 5086

/ COMMENTS: y s V"

, -a g i' ~L Beth MDEFPs start onran SI signal. a, lncorrect - "[" .,..,. , , b. Incorr'ect,- EFW palves receive full open signal on an SI signal. 7 " ~ 9- / c. Flows based on design flows of EFW pumps (Table IB3.1) d. Incorrect TDEFD does not receive an SI start - signal. 140 . . ) s.* -. w aa -aw -a-a.a.. s, - s m--o- - ea + - m m a ~ a-s. <.a n. s a-.~.un-a..n.o.w~m.,x-n.~=mu.w~<--a-a - ,.m,J) -- . ~ , , .. r ',.8 4 e b g b - . ,

,Y g W4 ?

She / '%, ,5

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, 6 8 r - - - - - "-- .. - - . }; % _ .- .. - - -...- . _. - - . .;. y Question Number:.95 '

  1. 5200 QUESTION POINT VALUE: L_0._Q

, The following conditions exist: ) ' .

An. Operational Basis Earthquake has occurred. ,

The OBE has caused'a SBLOCA and the crew is - implem'entin7EOPh)T1'""*Pos,taLOCA Cooldown and ' . D6pretihuh12afionil ~P'* F t v) u ~ f1r /r / . - Assuming that do'i.othfr event occurs, which46n'e (1. of s -

' following desckflie's how the RHR pumps will bd%sudd)eque. the. . ntly operated?QJ (/N , ~ Q, / .

s

  • %

, They will.be manually securg/d andJmust,beNnanually @r ' a. .. r$ started,g hneeded e E'7$ pf i b# $ ff They;sver'l}.ber?4'*WW' -ab Y W%.w E kk Mi b. wil run until th'elRWSTMhemi-automatic d,' sw5pl 06ccurs then m5ridally0 secured and rest'arted M @ @q~ 4 NL~ ' s'" " ,' Theylw111 de manuall.y decurele.y'GTl& & ; $ % N A. 'T**, CIf$f%f V diand will %, ! c. [,.Mutoriiat'iddlly;iestprt3 Ter/Stdamline pressu[l# "A f* k h f [, > ,. % u tyv.w u. d. %'V" 1DB S'ccurfalted IwfiiEh they ;dtisybe manua1ly a rpn b i f,A N

  • r6sEarhedfifvt,.he D/Gilcl6ad7t'li,s' buse s.

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  1. 5200-
/j

' j COMMENTS: / - ph,.- %r NEW QUESTION sA % Restarting RHR pumps after they have,-been secured during'a SBLOCA is the most risk-important operator action in PRA'~(RE:..TFR: TG1085i4 ) .- s , ! A, k

a. Requires examinee to determine that with a SBLOCA, pressure will remain >250 psig and will be manually started when aligning for COLD LEG recire. b. Incorrect. RHR pumps will be run until the crew verifies that RCS pressure is > 250 psig, which is 142 . I .... .. __...__...._._.._...m.._. _ _ _. _. _ _, _. _ _ _ _.. _ _ _. _ _ _. _. _ _.. _... _ _ - . . . . '. i . 'h) long before semi-auto swapover occurs on a si3LOCA. ! Incorrect'since an SI signal on low steamline ! c. pressure la blocked at 552'F. j , e I ~

' ~ d. Incorrect since they will automatically restart on

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%rf.. r >- u.- 4. -f .E - t *% %. . %* 'p .R > ,n . .s < < 9'. ~;;- 3,;; . pq - + ., + . $ . 143 . . ' . ' , ,. - , e . w 3r ,3.. .,r- -.- ,,,..m, ,r = ,.y _ - - _ _ _ _ _ _ _ _.. _ _ __. _ _ _ _ _ _ . , . . . %) Question Number: 96 ' 'd

...

  1. 210 QUESTION:

POINT VALUE: 1.00 During' normal at-power operation, Charging Pump."A" is being used for normal charging flow. The instrument air supply to FCV-122, Charging Flow' Control Valve, is lost. , , The abiitty of Charging Pump ~"A".to perform its intended function in the event of a.saf' g ardsJactII'^tI6n ~. signal (SI). is : e . ^ * * L [' ( aucethe[Vav6df . . roVfd iIl* fail closed', and,' a.- . - . . 'i,.pdmp flow will go to t

  1. ihjection line.

- .. . %,<f y * -- . . Not of fected because the normal ch'arejing 11nts. is , Q isolated on an SI.

  1. '"F l

> . s t Degra'ded because the charging pump wi rheat . t. c h. ' ist,rit, continuesstegrun itfdno flpw pricy ' the 7 S Y AMU ?.Y Qif[Gl~ f j^ p, f. . Q y.o j;.cyy.ggg3

  1. %"

d. Degradh ecausagthe charg ngppump will,not,be ' ' q~7" ableits31 $. dt'dsealtwaEeE 'nto the RCPs - /,5 %e. Q299 tf 4 KM 4g % o .hW f

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  1. 210 Ah n.

Jijd W 8W[. s.4 v a l v e!! ,ionhiiQopenL N/A since charging iDwh a. s ljips $ l's'olJifed "M 2 7 5 8108. ,

  • b.

Correct % Re reo 'r fpee' to research the ' . drawing to 6teMdi'nb f a'ilure mode of vd:lv~6, 4* . . -% configurationofsystemandanalyzesafet[ i' ' ' - / functions which may be affected. ] l c;/ Contintious miniflow doesn't go throu% d \\gh.FCV-122. %A s d. .. Seal injection doesn't go through FCV-122. y 7 m;-- . . (Rev. 1, replaced "va'lve does'n,ot receive a safeguards actuation sisnal" with' " normal" charging lino is isolated on an SI" i'n' choice b to make it more technically correct. 07/16/92) . . (Rev. 2, replaced " fails low" with "is lost" in stem to make it more clear. Replaced "CCP" with " Charging Pump A" in stem. Also deleted "not" from choice b to make b correct, 3/18/93. , ... 144 '. . . * g - - __ e .--, - .- - 9._. _. _... ~.

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. , p . . . N')) Question Number: 97 . g. '

  1. 5358 QUESTION:

POINT VALUE: 1.00 ' ' - Given the following: . . . ' The plant has been shut down and cooled down in preparation for - - ~ a Refueling Outage. . ' ' The CRS is.dirp"cting sEtions'pe.r GOP 9 for mid-loop operations. ' Initi' ll ')' flain $f.Rl3 ids @ service ~with ho^ leg level 1",above a - . .cehter ige:and'4850 gpm flow. M fij/ ' , - .- . The% P,OATC notes to the CRS the followingsconditiom N - - . .s

g v g s,n- .s rs , ' RHR pump motor amps: high and stablep% -g .RHR flow (FI-605A): upper end of indjc,aI , , - . , . . RHR pump disch, pressure (PJ-600A): low an~ table These[ +' cations are caused y;@Tw m y g. S* .c h i$ ?] ' ' k $ '

  1. ,rcen$$h A

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  • * *9 * Sam &y

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, t (f d' b f Y h' h; I l i

  1. 5358V ANSWER:

fv r \\/s vva if - . . f % / v.

, , '/) &g% < p. (1.00) /* .

  1. 5358 COMMENTS:

eA wd. ,,\\. - Signific'a$tly modified - Revised stem to runouti(% vortexing) ' conditions, chang ^ed answergand chapged aistrshtor b. Resequenced choices a & b. Al ' E, f Y . a a. Produces high flow and amps, b. Incorrect. Amps and flow wow.i be low, but pressure would be . high and steady . m 146 . .-. a . .l % ' _. - - _ _. _ _. __ _. ._ ____,_. _ _ _. - _... _. _ _. _ _, _. _ _. , . . - , - .- E

. . M Question Number: 99. !

.W ., , '

  1. 5355, QUESTION:-

-POINT VALUE: 1.,00 i , ... -. . Given tihe following conditions: . ' ' ' e The plant is operating at 75% power with a normal

. , Condensate pump lineup. , - , I x )%, STOR(dElaborQrie -r'eceived on . fK.L1, HDJII HI",and "CNDSR HOTWELL

" LTp. innt} - - ' , M c# #rr - - . . . . . ' " " Dedefator ' Storage Tank Leve'l indicates a hich o - ... F . dvel (10' 6 "). Mi( ' ' f/

( - !- - For theses.gcon itions, which ONE '(1), of the followi'ng[8hscribes , . . the finalN ondensate p' ump. lineup?, -%/. ' . , .. D^. i !! yg m . a. cess, ) cendtirsatggpump3rynningel'th thq/ common- , ' [/f mijg) ' ' ni W (TFV di:20 OPEggf 'M

N %gh sV ONEq(1)aMcondensaty pu runhin@ - f ' N b. minifl~ ~'We""l'LQSED.gQ~ ny *g'with the ' on f ( i f'

oondens, D $ 2p.'

.. m niflod"ii1Y5'jEN[ $$ g with the comm. ,, c. 4TWO 2 ateypu r n on ._ . @,3 . b# o'&'

  • d'

Mfh P ,m .. . , d. yf0p(2 nsatetppmggrunni th the cpamon.

c Einiflow, val,ve{0LO

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  1. 5355 ANSWER:

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  1. 5355' '

Q ENTS: . S[gnificantlymodifiedfrom-Question.#993b&.#5135. . - Changed the stem from "A &'B pumps running" to-" normal lineupf" Changed all 4 choices. gQ , e4 b - r . a. Incorrdct' ]il.DEAER STOR TK LVL will-trip all but one run' riing.conds'nsate pihEps, but ' flow will be sufficient to keep miniflow shut. - ' '. , ' ~ b. Requires examinee to determine that at 75% with a normal Condensate pump lineup, two pumps will be running. Also requires knowledge that HIGH (vs. _ p - HIGH-HIGH) DAST level-will: trip all but one s.:. - - 149 , I s. r,_ y .w-eer.% .- E.w,-, v.-,-r-. -..w-my,,, -.,e '- ,,r i-w . . - ,, _ - - - - - ._ . - . , ., - . . . , , , "2 "N+ ') running condensate pump. IFV-3120 begins to open at 8800 gpm,. decreasing, and is full open at 4800.

  • -

At 75%, one' condensate pump will be delivering . greater than 10,000 gpm. , . . . . c. Incorrect. Only one pump will be running. ~ ' . .

  • d.

Incorrect'. ~11niflow valv.e will be open. - . e~ s., '?'?,sfY'e, , ?)E L(:().d.. j

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, % 150 % . . -h ._, y) Question Number: 100 .

  1. 5357 QUESTION:

POINT VALUE: 1.00

The following conditions exist: The plant has exper'ienced a SBLOCA.

-

The Control. Room crew is cooling down the RCS IAW postiLO6A'YC6didown and Depressurization, ' EOP-2.1, g n Isg pu .a j te tek i [. ej ,- .No iator%slhape.-been received duc * (E)intiexpected annun'c%. =- e o . act 1ons taken in EOP-2.1V'f '

T . ~*~ Ah . .Q f ~ Main Steam flows' have been approxiiha%tely 800,000 ' s , lbm/hr from each S/G. .i ~ , ' RB@voressureisabout1.5cpsigfan,4%,,, VPW n\\*( All actions directed by*dE Q ' the EOP have ., dyccessfullgimptemente ' / g ./ e d increasing. f ' % ;g;kb$idg d scrib6$hhh$tatus of 'the#Sain Mqt p myM: . eNfN Which one (1) of t SteeifIsolation Valved (SSIVs)' HUEing4theYreriiainder of th{ W $$$$ c;d,.i: Mpg;y,,llwlW;e. g?.r ("u,y coo 1down? ' t v 25 M m p.4 k- @,,. ., W%.& mpae m a.%3At< 552&FWP-12iwillt; activate'j andetihe MSIVs-will A e(. Q$,6iose. Y T'MWiDN'Nd ' /*e ?m( T bD s 4 4 $ DN ^~G e p.., e , %W.h 8 .,,,& vg e b. SG5h.w M9 dN the@,NSIVs wille%c3.cfse. Wats 675.# steamlin[eiprpssure, 9t f ~ h

- M N pVl/ '

%%1!,~,;&W:.1h.a,,L.:D.;TMP% ' &u y zapp. - n . 7 :.:.:.. m m TherMSIVs;+w1 rema2.nsopenanntil RCS tempeYature \\ c. is"leiId5than3bOjF$Nhen*RNR'isplacedin}e'rvide. >J' & W ?NY~Y NY .The MSIVs willdllhma^1n open unless RB pressilre d e + pr p- \\ f+d. . exceeds 6.35 psig, and then they will C #'

?' - automatically close. [""h > ,. - g g,g p3,

  1. 5357 ANSWER:

, %<f A $ d. 4 11. (1.00) M, ? . %:~4 , .- e a

  1. 5357 COMMENTSc, A

.d 7, i ,.r ts

%

- NEW QUESTION Risk-Important Operator Action 1/ (RE: TWR TG10894) - a. P-12 wouli make up part of logic to close MSIVs, but only if a high steam flow (1.6E6 lbm/hr) condition also existed. Since steam flow has been 151 . - ~ . _ _ , . . 800,000 lbm/hr, a' Main Steam Isolation Signal ' ' would not,be generated. "' b MSIVs would close at 675#, but the procedure. ' ' directs blocking'Steamline SI when < 552*F. . 'MSIVs are not close'd until COLD SHUTDOWN. ~ c. , , " ' 'd. MSIVs will close automatically on high pressure in RB. (6.35.,psfl[1 (HG{ 2)JT,This signal is NOT ' " Block 1b1f. ort }~I".-/ ) /.. '

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