ML20133P336

Exam Rept 50-261/OL-85-01 on 850618-20.Exam Results:Three Candidates Passed Written & Oral Exams

ML20133P336
Person / Time
Site:	Robinson
Issue date:	07/17/1985
From:	Vinnola A, Wilson B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20133P327	List: ML20133P324 ML20133P336
References
50-261-OL-85-01, 50-261-OL-85-1, NUDOCS 8508140264
Download: ML20133P336 (82)

Text

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ENCLOSURE 1 EXAMINATION REPORT 261/0L-85-01 Facility Licensee:

Carolina Power and Light Company 411 Fayetteville Street Raleigh, NC 27602 Facility Name:

H. B. Robinson Facility Docket No. 50-261 Written and oral examinations were administered at H. B. Robinson near Harts-ville, S.C.

Chief Examiner: OM

& =_DM h 7 / I bl 85 A. J. Vinnol V V

Date Signed Approved by:

ai.

O!@d' ve BpceA. Wilson,SectionChief Date signed Summary:

Examinations on June 18 - 20, 1985 Written and oral examinations were administered to three candidates, all of whom passed.

8508140264 850723 PDR ADOCK 05000261 G

PDR

-1 2

REPORT DETAILS 1.

Facility Employees Contacted:

• R. S. Allen, Project Specialist - Training

• J. F. Benjamin, Principle Engineer - Operations

• R. E. Morgan, General Manager

• C. A. Bethea, Director - Training

• V. L. Smith, Senior Specialist - Training

• J. B. Allen, Senior Specialist - Training

• Howard Whitcomb, Resident Inspector - NRC

• Harry Krug, Senior Resident Inspector - NRC W. M. Blaisdell, Senior Specialist - Training I

• Attended Exit Meeting i

2.

Examiner:

I

• A. J. Vinnola, EG&G

• Chief Examiner 4

I 3.

Examination Review Meeting:

At the conclusion of the written examinations, the examiners met with W. M. Blaisdell, J. B. Allen, V. L. Smith, and R. S. Allen to review the l

written examination and answer key.

The following comments were made by the facility reviewers:

4

)

j 1.

Question 5.14 Facility Comment:

Recommend Item "d" also as correct answer since initial Keff was not given nor was there a statement in the stem of the question 4

directing one to assume initial Keff.

f NRC Resolution:

l i

Even though the initial Keff was not provided, Jan assumed initial Keff would result in the correct answer.

Therefore, only one answer is correct and "d" is not correct because there is enough i

data given to arrive at the correct relationship.

i f

f

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

3 2.

Question 6.1 Facility Comment:

Recommend changing correct answer from "b" to "c".

Reference Drawing #5379-685.

NRC Resolution:

Typographic error corrected.

3.

Question 6.19 Facility Comment:

Recommend accepting "b" or "c" as correct answers.

Reference for "c" 002, Page 11, 12 or Drawing #5379-1082.

NRC Resolution:

Choice "b" is the correct answer as stated on the master answer sheet.

Choice "c" is also correct.

System description - 002, Page 26, states the operator will take action to add a predeter-mined amount of sodium hydroxide (NaOH).

This was originally i

understood by the examiner that NaOH has to be manually injected into the spray flow.

However, the facility reviewers' reference does indicate that Na0H does, in fact, automatically inject into the spray flow and the operator then will throttle the amount of NaOH injected.

Answer "c" was added to the master answer sheet.

4.

Question 6.31 Facility Comment:

Recommend deleting this question as there is no correct answer to choose from in Column "B".

Reference Drawing'F5379-2759, Sheet 8.

NRC Resolution:

The facility reviewers' comment is correct.

The examiner misin-terpreted the referenced drawing to indicate that manual "P"

signal caused the MSIV's to shut simultaneously.

Part "b" was deleted, therefore, Section 6 total points available was changed to 34.5.

I

4 5.

Question 7.05.a and 7.14 Facility Comment:

One of the facility reviewers stated he did not believe an operator needs to memorize this information and did not believe it should be questioned on the written examination.

NRC Resolution:

Examiner Standard ES-202.B.4 states that although the candidate is not expected to have normal procedures committed to memory, he/she is expected to be able to explain reasons, cautions and limitations of normal operating procedures.

No change to question or answer key.

6.

Question 7.16 Facility Comment:

Answers "a" and "c" are correct.

a.

Immediate action says to manually insert rods if in manual.

c.

Max power allowed prior to and during retrieval of rod is 70%.

limiter will not allow increase of >70% until rod drop reset on NIS.

{

also, it says to verify CAOC and Quadrant Power Tilt are within limits. This is done after the rod is retrieved.

Reference A0P-001, Section 4.0 NRC Resolution:

Choice "c" is accepted as a correct answer in addition to choice "a",

because the rod drop reset is performed after the rod has been retrieved.

The QPTR and CAOC verification is the first subsequent step listed in A0P-100 prior to rod retrieval, and therefore, does not restrict power level, if they are within limits.

4

,v.-

1 5

7.

Question 7.18 Facility Comment:

Recommend accepting item "a" or "b" as correct.

A0P-002 directs the operator to Emergency Borate if two or more rod position indicators fail to indicate control rods inserted after a trip.

Reference A0P-002, Page 3, 4.

Also recommend accepting Item "c" as correct answer because successful completion would immediately mitigate the event and this action is taught and evaluated during simulator training.

Reference HBR Simulator Exercise Guide #HBR-RT-2.1E.

NRC Resolution:

The question stem references FRP-S.1 operator actions in the event that a manual reactor trip is not successful.

The master answer sheet lists choice "a"

to be the correct answer.

Choice "b" (emergency borate) is listed in A0P-002 as stated by facility, however, it is listed in FRP-S.1 as the fourth step after the operator has verified reactor trip, verified turbine trip and checked AFW or FW pumps running.

Item "c" (locally open reactor trip breakers) is not listed in FRP-S.1, but is listed on the reference provided by facility (HBR Simulator Exercise Guide

1. HBR-RT-2.1E).

If the facility trains their people to perform choices "b"

and "c", in the event a manual reactor trip is unsuccessful, their training (HBR Simulator Exercise Guide #HBR-RT-2.1E) and A0P do not agree with the Function Restoration Procedure, FRP-5.1.

It is, therefore, recommended that these references are to be revised in agreement with each other, and is listed as an open item.

To accept the facility review comment is to admit that FRP-S.1 does not provide adequate guidance to the operator, and that the order of operator actions in FRP-S.1 does not have to be followed.

However, because of conflicting training and plant references, the question is deleted.

8.

Question 7.21 Facility Comment:

During the review the reviewer stated that a stable or increasing RCS Delta T is an indication for monitoring RCS natural circu-lation cooldown.

1 6

NRC Resolution:

The facility was unable to provide a reference for the comment and it is not listed in the EPP-5 procedure, therefore, the comment was not accepted.

9.

Question 7.27 Facility Comment:

Recommend deleting this question as it involves a task (operation of spent fuel crane) that operations personnel are not responsible for nor trained on.

The steps in FHP-034 that address the operation of the spent fuel crane are performed by Maintenance personnel.

Reference note in FHP-034, Page 3, Item 4.1 then reference Page 16, Item 5.3.6.

NRC Resolution:

The examiner verified the proceeding comment to be correct and question is deleted from the examination.

Therefore, Section 7 total points available was changed to 33.5.

10.

Question 8.27 Facility Comment:

Recommend additional answer; " Pressurizer pressure control is operable," since the question stated critical >350 F.

Reference Technical Specification, Page 3.1-3a, Paragraph b.

NRC Resolution:

The facility comment is verified to be correct.

The additional answer accepted is " Pressurizer pressure control system is operable." Any two of the three answers required for full credit.

11.

Question 8.30 Facility Comment:

Additional answers for personnel who may relieve S.F. as Site Emergency Coordinator.

1.

General Manager 2.

Manager - Operations 3.

Manager - Maintenance 4.

Manager - Technical Support 5.

Manager - E&RC 6.

Operating Supervisor (Unit #2) 7.

Mechanical Supervisor (Unit #2) 8.

I&C Maintenance Supervisor (Unit #2)

7 i

9.

Radiation Control Supervisor 10.

Environmental & Chemistry Supervisor i

11.

Engineering - Plant Supervisor 12.

Engineering - Performance Supervisor Reference AP-001, Page 14 The PEP states that the shift foreman is the interim. We teach in j

lesson plan PROC-LP-9 that a shif t foreman may relieve the on-shift shift foreman as Emergency Coordinator if none of the above i

personnel have arrived on site.

This is for the purpose of allowing the on-shift shift foreman to involve himself in more

)

detail with placing the plant in a safe condition. We recommend that shift foreman be allowed as an additional answer.

\\

NRC Resolution:

j The comment is verified to be correct and additional answers accepted.

4.

Exit Meeting At the conclusion of the site visit the examiners met with representatives of the plant staff to discuss the results of the examination.

Those j

individuals who clearly passed the oral examination were identified.

There were no generic weaknesses (greater than 75 percent of candidates

.l giving incorrect answers to one examination topic) noted during the oral examination.

I The cooperation given to the examiners and the effort to ensure an atmo-sphere in the control room conducive to oral examinations was also noted and appreciated.

The licensee did not identify as proprietary any of the material provided to or reviewed by the examiners.

O I

I i

i~

EtlCLOSURE 3 i

U.

S. NUCLEAR REGULATORY COMMISS ION SENIOR REACTOR OPERATOR LICENSE EXAPINATION Reunewed G y.

FACILITY:

_EDEINSDH________________

' * '3 \\SUSde\\l REACTOR TYPE 8

_EME-kEC3-_________

2. T. 9. A uen, Tc, 3,

y,L, sq DATE ADMINISTERED 8_R1/D& LIB _ _ _ _ _

4. R.S. A h en EXAMINER:

_11hMDLAA_Aa_ _ _ _ __ ___

APPLICANT N54 E' IH11RUCIIDH1_ID_AEfLIC&dIl Use separate paper for the answers.

Wr ite answer s on one side only.

Staple question sheet on top of the answer sheets.

Points for each question are Indicated in parentheses after the question. The passing grade requires at least 70% in each category and a final grade of at least 80%.

Examination papers will be picked up s ix (6) hours after the examination starts.

• OF CATEGORY

% OF APPLICANT'S CATEGORY

._MALUE _IDIAL

___SCOBE___

_MALUE__ _____________CAIEQQEI________

.32aQQ _ _21400

___ 5.

THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDSs AND THERMODYNAMICS C

allaQQ__ _22400

________ 6.

PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMEhTATION 33 C i

1k120'__ _22490

________ 7.

PROCEDURE S - NORMALS ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL l

.11622__ _22 ASS

________ 8.

ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS tac liQaQQ'__

TOTALS l

l FINAL GRADE _________________%

All work done on this examination is my own. I have neither given nor received aid.

APPLICANT'S SIGNATURE

i e

2a__IHEQRI_DE_BUCLEAE_EDMER_ELABI_DEERAIIDHA_ELUIDSa_ABD PAGE 2

IBERUDDIBAEICS QUESTION 5.01 (1.00)

If reactor power increases from 1000 cps to 5000 cps in 30 seconds, what is tho SUR7 a.

1.0 OPM b.

1.2 DPM c.

1.4 DPM d.

1 6 OPM QUESTION 5.02 (1 00)

In which of the following conditions is the Moder ator Temperature Ccefficient most negative?

a.

BOLs high temperature b.

BOLs low temperature c.

EOLs low temperature d.

EOLs high temperature QUESTION 5 03 (1 00)

Whi ch of the f ollowing cause the fuel centerline temper ature to decrease over core life?

a.

Fuel Densification b.

Clad Creep c.

Buildup of Fission Products d.

Higher Linear Power Density l

i l

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IMERBDDIBAHICS QUESTION 5.04 (1.00)

During a Xenon-free reactor startups critical data was inadvertently taken two decades be low the required In termediate Range (IR) level (1xE-10 amps).

The critical data was taken again at the proper IR level (1xE-8 amps).

Assuming RCS temperatures and boron concentrations were the same for each sot of data, which of the following statements is correct?

a.

The critical rod position taken at the proper IR level is LESS THAN the critical rod position taken two decades below the proper IR level.

b.

The critical rod position taken at the proper IR level is THE SAME AS the critical rod position tak en two decades below the proper IR level.

c.

The critical rod position taken at the proper IR level is GREATER THAN the critical rod position taken two decades below the proper IR level.

d.

There is not enough information given to determine the relationship between the critical rod position taken at the proper IR level and the critical rod position taken two decades below the proper IR level.

QUESTION 5.05 (1.00)

Which of the following statements concerning Xenon-135 production and recoval is correct?

a.

At full powers equilibrium conditions, about half of the Xenon is produced by Iodine decay and the other half is produced as a direct fission product.

b.

Following a reactor trip from equi li br ium conci t ions, Xenon peaks oecause delayed neutron precursors continue to decay to Xenon while neutron absorption (burnout) nas ceased.

c.

Xenon production and removal increases linear ly as power level increases; i.e.s the value of 100% equilibriur Xenon is twice that of 504 equilibrium Xenon.

d.

At low power levels, Xenon decay is the major renov at method.

At high power levels, burnout is tne major removal methoc.

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IMEREDDId&51CS QUESTION 5.06 (1.00)

Which of the following nuclear parameters are ALL contributors to differential rod worth?

a.

Local gamma flux, peak gamma flux, slowing down length, thermal diffusion length.

b.

Local neutron flux, peak neutron flux, slowing cown lengths thermal diffusion length.

c.

Local gamma flux, average gamma flux, slowing down lengths thermal diffusion length.

d.

Local neutron flux, average neutron flux, slowing down lengths thermal diffusion length.

QUESTION 5.07 (1.00)

Which of the following statements is correct, concerning water as the cod er a t or ?

a.

Water has a HIGH scattering c r oss-s e c t i on, a LOW absorption cross-sections and a LARGE en er gy decrement per collision.

b.

Water has a LOW scattering cross-section, a HIGH absorption cross-section, and a LARGE energy decrement per collision.

c.

Water has a HIGH scattering cross-section, a LOW absorption cross-section, and a SMALL energy decrement per collision.

d.

Water has a LOW scattering cross-sections a HIGH absorption cross-section, and a SMALL energy decrement per collision.

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IdERdQQIn&d1CS QUESTION 5.08 (1.00)

Which of the following statements describes the r elationship between integral and differential rod worth?

a.

Integral rod worth (at any location) is the slope of the dif ferentist rod worth curve at that location.

b.

Integral rod worth (at any location) is the total area under the differential rod worth curve from the end of the rod to that location.

t c.

Integral rod worth (at any location) is the square of the differential rod worth at that location.

d.

There is no relationship between Integral and differential rod worth.

QUESTION 5.09 (1.00)

Which of the following statements concerning Shutdown Margin (SDM) is cor rec t?

a.

Tne maximum SDM requirement occurs at EOL and is based on a rod ejection accident.

i b.

The maximum SDM requirement occurs at EOL and is based on a steam line break accident.

c.

The maximum SDM requirement occurs at BOL and is based on having a positive moderator temperature coefficient.

d.

The maximum SDM requirement occurs at BOL and is based on a red withdrawal accident while in the source r ange.

1 QUESTION 5 10 (1 50)

For the following definitions, give the term that is defined.

a.

The amount of reactivity that is needed to go from hot zero power to hot full power.

b.

The f ractional change in neutron population per generation.

c.

The decay of a neutron into a proton with the simultaneous ejection of an electron (and antineutrino) from the nucleus.

I

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ta__IMEQBI_DE_BUCLEAE_EDMEE_ELASI_DEEEAIIDut_ELUIQSt_AbQ PAGE 6

IUEE5DDIbatICS l

l QUESTION 5.11 (1.50)

Indicate whether the following statements concerning delayed neutrons are TRUE or FALSE.

a.

If the reactor i s supercr itical, then a larger percentage of delayed neutrons is f rom the shorter lived precursors and the value of the effective decay constant (lambda) d e c r e a s e s) a s c o m pared +o a e64i es t r eae4cc.

b.

Due to the significant decrease in the percentage of fast fission occuring over core life, the value of the effective delayed neutron fraction decreases over core Ilfe.

c.

Del ayed neutrons are produced after fission as a result of the radio-active decay of fission products.

t QUESTION 5.12 (1.00)

During a reactor trip recovery, the initial 1/M data point was 1.0.

After a 1-hour delays rod withdrawal was commenced.

Upon stopping rod withdrawl to take 1/M data, the RO reported that the second 1/ M d a t a po i n t w a s 1.1.

Which of the following explains this increase in the 1/M value?

a.

This is NOT possibles the RO must have made an error when taking count rate data.

b.

The buildup of Xenon during the 1-hour de l ay added more negative reactivity than the rod withdrawal added posi ti ve r eactivity.

c.

The source-detector geometry is incorrect.

d.

An inadvertent dilution is in progress.

QUESTION 5.13 (1.00)

With the reactor initially at a keff of 0.99, a certain reactivity change causes the count rate to double.

If this same amount of r e ac ti v i ty is again added to the reactor, which of the f ollowing will be the status of the reactor?

a.

Subcritical D.

Critical c.

Supercritical d.

Prompt Critical

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h__IM E Q 81_DE_d MC LEAE_ E DMER_EL&til_ D EEE AllDtia._ EL u1D 3 a._ AHQ PAGE 7

IBEREDDIDABICS 1

QUESTION 5.14 (1.00)

I During a reactor startups the first reactivity addition caused count rate to increase from 10 cps to 16 cps.

The second reactivity addition caused count rate to increase from 16 cps to 32 cps.

Which of the following statements describing the rel ationship between the reactivity values of the i

first and second reactivity additions is correct?

a.

The first reactivty addition was larger.

b.

The second reactivity addition was larger.

c.

The first and second reactivi ty additions wer e equal.

d.

There is not enough data given to determine r elationship of reactivity values.

QUESTION 5.15 (1 00)

Concerning equilibrium Samarium-149 (Sm) reactivity, wnich of the following statements is correct?

a.

50% equilibrium Sm reactivity is one-quar ter of 100% equi li brium Sm reactivity.

b.

50% equilibrium Sm reactivity is one-half of 100% equi l ibri um Sm reactivity.

c.

50% equilibrium Sm reactivity is thr ee-quar te rs of 100% equilibrium Sm reactivity.

d.

50% equilibrium Sa reactivity is equal to 1002 equi li br ium Sm reactivity.

QUESTION 5 16 (2.00) i If steam goes through a throttling process, Indicate whether the f ollowing par ameters will INCREASES DECREASES or REMAIN THE SAPE.

a.

Enthalpy b.

Pressure c.

Entropy d.

Temperature

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IHEE50DINAHICS QUESTION 5.17 (1.00)

A v ar i abl e speed centr if ugal pump is operating at 1800 rpm with a capacity of 400 gpa at a discharge head of 20 psl which requires a power of 40 kW.

If pump speed is increased to 2000 rpm, which of the following best doscribes the new pump parameters?

a.

444 gpas 22 psis 55 kW b.

444 gpas 25 psi, 49 kW c.

444 gpas 25 psis 55 kW d.

444 gpas 22 psis 49 kW QUESTION 5.18 (1.50)

Indicate whether the following are TRUE or FALSE.

a.

During a RCS heatups as temperature increases, it will take a smaller letdown flow rate to maintain a constant pressurizer level.

b.

Increasing condens ate depress ion (subcooling) will cause BOTH a decrease in plant efficiency AND an increase in condensate (hotwell) pump available NPSH.

c.

The difference between pump suction pressure and the saturation pressure of the fluid being pumped is ref erred to as net positive suction head.

QUESTION 5 19 (1 00)

Which of the f ollowing describes the changes to the steam that occur Detween the inlet and outlet of a real (not ideal) turbine?

a.

Enthalpy decreasess Entropy decreasess Quality decreases b.

Enthalpy increasess Entropy increasess Quality increases c.

Enthalpy constants Entropy decreasess Quality decreases d.

Enthalpy decreasess Entropy increasess Quality decreases

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j

s la__IdEDRI_DE_SUCLEAE_EQMER_ELAMI_ DEERAIIDHt_ELulD34_ AHQ PAGE 9

IMEREDDIBA51CS QUESTION 5.20 (1.00)

Which of the f ollowing will cause plant ef ficiency to increase?

a.

Total S/G blowdown is changed from 30 gpm to 40 gpm.

b.

Steam qual ity changes from 99.7% to 99.9%.

c.

Level incr ease to hi gher than normal in a feedwater heater.

d.

Absolute condenser pressure changes from 1 0 psi to 1.5 psl.

QUESTION 5.21 (1 00)

Tho reactor is producing 100% rated thermal power at a core delta T of 60 degrees and c mass flow rate of 100% when a blackout occurs.

Natural circulation is established and core delta T goes to 40 degrees.

If decay heat is 24, what is the core mass flow rate (in percent of total rated flow)?

a.

13 b.

2.0 c.

3.0 d.

4.0 1

QUESTION 5.22 (1 00)

L'h i ch o f the following statements is correct if the cischarge valve of a contrifugal pump is being partially closed from the full open position?

a.

Pump head decreases as' head loss decreases.

b.

Pump head increases as head loss increases.

c.

Volume flow rate Increases as head loss decreases.

d.

Volume flow rate decreasses as head loss decr eases.

l l

l l

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s la__IHEORI_DE_HUCLEAR_EQMER_ELAHI_DEERAIIDHt_ELUID34_AHQ PAGE 10 IHER50DINAMICS QUESTION 5.23 (1.00)

Which of the f ollowing does NOT provide assurance that the enthalpy rise hot channel limits are not violated?

a.

Axial poner distribution is maintained within limits.

b.

Control rod banks are sequenced with proper overlap.

c.

Control rod insertion limits are maintained.

d.

The MTC is within its analyzed temperature range.

QUESTION 5.24 (1 50)

Fcr the following definitions, give the term that is defined.

a.

The amount of heat required to change 1 lbs. of water into 1 lbs. of steam at a constant temperature. -

b.

The ratio of the Critical Heat Flux to the actual heat flux.

c.

The ratio of the peak heat flux at core elevation z to the core average h e a t f I ux. ( S pe n (,oA 4e. 4eem desme4,')

QUESTION 5.25 (1 00)

Whi ch of the f ollowing would cause an INCREASE in the conductive heat transfer RATE across a slab?

a.

Decrease heat transfer area of slab.

b.

Decrease delta T across slab.

c.

Decrease thickness of stab.

d.

Decrease thermal conducti vi ty of s t ab.

i l

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IHE850DIB&BIGS l

QUESTION 5.26 (1.00)

Whi ch of the f ollowing s tatements descr ibing the thermal stresses induced in the reactor vessel during a RCS cooldown is correctt a.

Tensile stress at OUTSIDE diameter and compressive stress at INSIDE diameter.

b.

Tensile stress at INSIDE di ameter and compressive stress at OUTSIDE diameter.

c.

Tensile stress at DUTSIDE diameter and no stress at INSIDE diameter.

d.

Tensile stress at INSIDE diameter and no stress at OUTSIDE diameter.

QUESTION 5.27 (1 00)

During the life of the reactor vessels the RTNDT increases due to radiation exposure f rom neutron bombardment.

Which of the following is the main contributing elesent that causes this increase?

a.

Cu b.

Fe c.

Ni de Sr QUESTION 5.28 (2.00)

The reactor is operating at 30% power when one RCP trips.

Assuming no reactor trip or turbine load change occurs indicate whether the following par ameters will INCREASES DECREASES or REMAIN THE SAME.

a.

Flow in operating reactor coolant loops b.

Core delta T c.

Reactor vessel delta P d.

Operating loop steam generator pressure l

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1s__IBEDRI_DE_duCLEAE_EDWER_ELAHI_DfEEAllDHt_ELu1DSa_AHQ PAGE 12 IHEREDDIBABICS QUESTION 5.29 (1 00)

Tho reactor is operating at 50% power with rod control in MANUAL and turbine controls in AUTOP.ATIC when a S/G PORV falls open.

Assuming no rooctor trip or operator actions, choose the answ er below that describes the resulting steady state conditions.

a.

Final Tavg greater than initial Tavos Final power equal to initial power.

b.

Final Tavo greater than initial Tavgs Final power greater than initial power.

c.

Final Tavg less than initial Tavg, Final power equal to inital power.

d.

Final Tavo less than initial Tava, Final power greater than initial power.

QUESTION 5.30 (1.00)

The Technical S p ec i f i c a t i ons allow operations for a 2-hour time period with a Quadrant Power Tilt Ratio (QPTR) of greater than 102.

Which of the following is the reason for allowing these operations?

a.

To allow time for corrective action in the ev ent of Xenon r edistr ibu-tion f ollowing power changes.

b.

To allow time for correction of a dropped or elsaligned control rod.

c.

To allow time for boron concentration changes to restore the QPTR to less than 1.02.

d.

To allow time from correction of RCS flow imbalances.

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i

2 m IMEQRI_DE_HuCLEAR_EQMER_EL&HI_ DEER &IIDHt_ELUID3a_ANQ PAGE 13 IHER50DINA51CS QUESTION 5.31 (1.00)

The Technical Specifications limit on the Heat Flux Hot Channel Factor varies depending on certain parameters.

Which of the following sets of parameters vary this limit?

a.

RCS Flowrate and Rod Bow Penalty b.

RCS Flowrate and Fraction of Rated Power c.

Core Height Location and Rod Bow Penalty d.

Core Height Location and Fraction of Rated Power i

l 4

(***** END OF C ATEGORY 05 *****)

i ha__ELAMI_SISIE53_DESIGHz_IDMItaka_A80_1HSIEUBENIAIIGH PAGE 14 QUESTION 6.01 (1 00)

If power is at 100 % and the Steam Dump is in Tavg ecde when the first stage pressure channel 447 falls lows which of the following best describes tha response?

a.

All 5 condenser dump valves and 3 steam gener ator PORV's arm.

b.

All 5 condenser dump valves arm and trip open.

c.

All 5 condenser dump valves arm.

d.

There will be no ef f ects to the Steam Dump systes because there has not been a load rejection nor trip.

QUESTION 6 02 (1.50)

Indicate whether the f ollowing statements are TRUE or FALSE concerning the Main Steam System.

a.

The flow nozzel (venturi) in the steam lines is used for flow instrumentation and will reduce steam flow in case of a steam line break.

b.

When all the MSR motor operated purge valves reach their fully open positions the air operated vent valves to the condenser will open.

c.

For loads below 10%s all the MSR timer valves shall be open.

4

(*****

C ATEGORY 06 C ONTINUED ON NEXT P AGE *****)

&c__ELAHI_111IE51_RE11GH4_CDHIRDia_AHQ_INSIEUBEHIAIIDH PAGE 15 QUESTION 6.03 (1.50)

Match the Tavg.-Tref. deviation f rom Column B whi ch would cause the valves 1

A ? he mg be. wore.h me 8ew(sWow So< e=A v open during a l oad r eJ ec t i on. wwuss Aeviak'- 'oin giv e 44 t.

in Column A to trip o

feaponse. M c,W.wn ca one.

Column B (degrees F) i.s weaded Column A o g;4, s.

Only the 5 condenser 1.

3 valves 2.

5 b.

Only 3 of the condenser valves 3.

10 c.

5 Jondenser valves 4.

14 and 3 PORV's 5.

18 6.

30 7.

35 Q UES TION 6.04 (1.50)

Match the type of Main Turbine control in Column A to i ts corresponding turbine generator condition in Column B.

Column A Column B a.

Speed control 1.

Turbine latched, GCB's closed, imp in b.

Turbine load (%)

2.

Turbine latched, GCB's closed, c.

C on tr o l valve imp out position (%)

3.

Turbine latched, OCB's open, imp out 4.

Tur b ine unl atch ed, OC B's open imp out

( ** *** C ATEGORY 06 CONTINUED ON NEXT P AGE *****)

t ha__EL&dI_SIIIEBS DESIGda_CQMIRQLt_AND_IH11RUBENIAIIEh PAGE 16 j

QUESTION 6.05 (1.50)

Indicate whether the following st atements are TRUE or FALSE concerning the Main Turbine and Controls.

a.

The reheat stop valve and interceptor valve actuators can position these valves in any position from fully open to fully closed.

b.

With the turbine auto-stop mechanism latched, the p ilot-oper ated dump valve closes to build up fluid pressure under the cylinder pistons opening the reheat stop and interceptor valves.

c.

Lubricating oil is used as the control medium for the inter f ace emergency trip valve in the mechanical-hydraulic trip system.

1 I

i j

QUESTION 6.06 (1 00) l If the Main Turbine Emergency Lubricating Oil Pump has been running and than the white lights on the RTGB go outs which of the following is correct?

ASSUME no further operator action.

a.

Pump discharge pressure is greater than 25 psig. and the pump is still running.

b.

Pump discharge pressure is greater than 25 psig. and the pump has automaticall y stopped.

c.

Pump discharge pressure is less than 25 psig. and the pump is stopped.

i d.

Pump discharge pressure is less than 25 psig. anc the pump is still running.

QUESTION 6.07 (1.00)

During Main Generator startup operations, before it is tied to the grid, which of the below adjustments will zero the regulator second stage output?

I a.

Voltage Regulator in " Test", using the Manual Field Current Adjuster.

b.

Voltage Regulator in " Auto", using the Voltage Adjuster.

c.

Voltage Regulator in " Test", using the Voltage Adjuster.

d.

Voltage Regulator in "Off", using the Manual Field Current Adjuster.

t

(*****

C ATEGCRY 06 CONTINUED ON NEXT P AGE *****)

ha__ELANI_SIIIEBS_DESIGBa_COBIRQLa_ABQ_INSIEMBENIAIIGH PAGE 17 QUESTION 6 08 (1 00)

Which of the f ollowing statements concerning the CVCS is correct?

a.

If the DEBORATING desineralizers are in operations the le tdown passes through deborating domineralizers, then through rixed bed domineralizers and then into the VCT.

b.

During plant cooldowns when RHR is in operations none of the RHR flow goes through the CVCS non-regenerative heat e xchanger.

c.

The CATION domineralizer is normally in service to remove fission products and some corrosion products.

d.

The letdown orifice isolation valves (CVC-200 As B, Cl receive a Phase

'A' Containment Isolation (T) signal.

QUESTION 6.09

(.50)

TRUE or FALSE 7 The effluent of the Excess Letdown Heat Exchanger may be aligned to either the Reactor Coolant Drain Tank or the Volume Control Tank.

i QUESTION 6.10 (1.00)

If a loss of power to the CVCS Diversion Valve (TCV-143) occurs, the valve uill fall i n t h e _________-( c ho o s e on e o f t h e f o l l o w in g ) _______ position.

a.

fully open b.

Reactor Coolant Filter c.

"as is" de mix bed domineralizer

\\

l l

l I

(***** C ATEGORY 06 CONTINUED ON NEXT P AGE *****)

ha._ELAHI_SISIEdS_QESIGHz_CONIRQLa_ANQ_1HSIEUBEHIAIICh PAGE 18 QUESTION 6.11 (1 00)

Choose from the below choices the correct order of the following CVCS coaponents located on the letdown line, beginning with the component that is furthermost upstream.

CVCS Components l

1.

Non-regener ati ve Heat Exchanger l

2.

Regenerative Heat Exchanger 3.

Di version Va lv e (TC V-143) 4.

Low Pressure Letdown Valve (PCV-145) 5.

VCT Level Control Valve (LCV-115) 6.

Letdown Orifice Isolation Valves (CVC-200 A,

B, C )

7.

Letdown Line Isolation Valves (CVC-204 As B) 8.

Letdown to VCT Relief Valve (CVC-209) a.

Is 6,

7, 2,

8, 4,

3s 5.

b.

2, 7s 6,

is 4,

8, 3s 5.

c.

2s 6,

7, is 4,

8, 3,

5.

d.

2s 6,

is 7s 8,

4, 3s 5.

I i

QUESTION 6.12 (1.00)

Which of the following is NOT coo led by the Component Cooling Water System?

a.

Waste Evaporator condenser.

b.

RHR pumps.

c.

Emer2ency Diesel Generator lube oil coolers.

d.

Waste Gas compressors.

l l

1 l

\\

l l

l

(*****

C ATEGORY 06 CONTINUED ON HEXT P AGE *****)

1 he__ELAHI_31SIE55_DESIGH4_CDHIRDLa_AHQ_INSIRudENIAIIDH PAGE 19 l

Q UES TION 6.13 (1.00)

Indicate whether the following are TRUE or FALSE in regard to the Instrument Air system.

i a.

When the air compressor is opeta/Ing in automatic it will run continously with the air receifver pressure automatically being maintained between 98 - 102 psig. by the unloader.

h.

Ins trument Air low pressure alarm will be received when the pressure drops to 95 psig.

QUESTION 6 14 (1.00) l Whi ch of the f ollowing statements is correct concerning the Liquid Waste Disposal System?

a.

Normallys fluids in the reactor coolant drain tanks are pumped to the Waste Holdup Tank.

b.

Manual operator action is required to pump the Containmen t Vessel sump to the Waste Holdup Tank.

c.

Nitrogen is routed to the top of the Spent Re sin Storage Tank for i

purposes of agitating the resin prior to transferring.

d.

The 80RIC ACID evaporators can be aligned for processing liquid waste.

t QUESTION 6.15

(.50)

TRUE or FALSE 7 The Containment Vacuum Rellef and Containment Prassure Relief Systems automatically maintain the pressure inside the containment between

-0.3 psig. and +0.3 psig., during normal power oper ation.

( ***** C ATEGORY 06 CON TINUED ON NEXT P AGE *****)

hn__ELAMI 311IE51 QESIGHa_CDNIRQLa.AML181IEU5ENIAIIDH PAGE 20 QUESTION 6.16 (1.00)

To purge the radioactive gases from the Hydrogen Roccabiner and piping if acc es s i bi l i ty f or maintenance would be required, which of the following would be used?

a.

Portable inert Argon gas.

b.

Instrument Alr.

c.

Portable Oxygen bottles.

d.

Plant Nitrogen.

QUESTION 6.17 (1.00)

Indicate whether the following statements are TRUE or F ALSE concerning the Stoan Generator Level Control.

a.

The manual control signal will override the high water level valve closure signal, and allow the operator to take control of the flow control valves.

b.

Even though there are four input signals (tur bine first stage pressure, actual water level, pressure compensated steam flow and feed flow), the control valve is controlled by a 3-element controller.

QUESTION 6.18 (1.50)

Indicate whether the f ollowing statements are TRUE or FALSE concerning the Ecorgency Diesel Generator.

a.

The main tube oil pump and cooling water pump are driven by the diesel's upper crankshaft.

b.

When the diesel receives a manual s tar t s i gna l, the signal will also l

start the di esel's ventil ation equi pment.

c.

Three controls on the diesel speed governor are synchronizers speed droop and load limit.

(***** CATEGORY 06 CONTINUED ON NEXT PAGE *****)

ha__ELAMI_SISIEBS_DESIGHz_CQMIEQLa_AHQ 181IRUBENIAllGH PAGE 21 QUESTION 6 19 (1.00)

Which of the following statements concerning the Containment Spray System is correct?

a.

The sodium hydroxide in the spray facilitates the converting of soluble iodine into insoluble iodine.

b.

The sodium hydroxide in the spray minimizes chloride stress corrosion of stainless steel piping and components in the event of a LOCA inside the containment.

c.

The containment spray pumps will automaticall y s tar t on a

'P' signal and sodium hydroxide will automatically inject into the spray flow.

d.

Due to the variance in the time that the spray pump actuation signal may be generated during an accidents the diesel generators are not capable of supplying power for the starting of the spray pumps in coincidence with the starting of any other load.

QUESTION 6 20 (1 00)

Uhich of the following r adiation monitors will NOT immediately cause a a control room alarm when the monitor reaches the al arm setpoint?

a.

R-16 Radioactive Liquid Monitor (containment HVH units).

b.

R-37 Condensate Polisher Waste Radiation.

j c.

R-30:

Fuel Handling Building Lower Level Gas.

d.

R-188 Was te Disposal Liquid Effluent.

(***** C ATEGORY 06 CONTINUED ON NEXT P AGE *****)

hs__ELABI_1111Edl_DEllGdi_fDdIEQLA Abd_INSIEMBENIAIIEd PAGE 22 QUESTION 6.21 (1.00)

Using the following 7 actions, which of the below sequences is the correct soquence for a rod withdrawl?

Seven Rod Control Actions 1.

Movable gripper coil energized (L a tch ed ).

2.

Stationary coil energized (Latched).

3.

Lift coli energized.

4.

Stationary gripper energized (Hold).

5.

Movable coil DEENERGIZED (Unlatched).

6.

Stationary coil DEENERGIZED (Un l a t ched).

7.

Lift coil DEENERGIZED.

Soquences to Choose From a.

4, 3,

is 6,

2, 5,

7.

b.

4, is 6s 3,

2, 5,

7.

c.

2, 4,

is 6,

3, 7,

5.

d.

3s is 7s 5,

6s 4,

2.

QUESTION 6.22 (1.00)

Whi ch of the f ollowing s tatements concerning the Individual Rod Position Indication system is correct?

a.

The rod bottom bistable is adjustable and is normally set at 10 steps from the bottoin of travel.

b.

The rod bottom bistable only provides indication functions.

c.

There is one control b an k bypass bistable associated with each control bank except control banks A and B.

d.

The control bank bypass bistable provides a blocking action on the turbine runback signal and the inhibiting of the automatic rod withdrawal when the rods of the associated bank are to be operated near or below the rod bottom bistable setpoints.

(***** CATEGORY 06 CONTINUED ON NEXT PAGE *****)

ha__ELAHI_3XIIE53_DESIGHA_CQHIRQLa_AMQ_IHSIEMBENIAIIOb PAGE 23 QUESTION 6.23 (2.00)

For the statements below concerning the rod control system indicate whether each is TRUE or FALSE.

a.

The nonlinear gain unit adjusts circuit gain depending on turbine power.

b.

The bank overlap unit sends a signal to each slave cycler f or purposes of selecting a master cycler.

c.

The rod drive mechanisms receive their power from two parrallel motor generator sets through two parallel gener ator output breakers and through two series Reactor Trip breakers.

d.

A logic error would cause a power cabinet urgent alarm.

QUESTION 6 24 (1.00)

Which statement describes the signal path from the Source Range detector to the Source Range level meter on the main control board?

a.

Detector, Pre Amp, Discriminators Log Integrator, Noter i

b.

Detectors Log Integrators Pulse Shapers Pulse Counter, Meter c.

Detectors Pre Amp, Log Integr ators Discriminator, Meter d.

Detector, Log Amp, Meter QUESTION 6 25 (1 00)

Whi ch of the f ollowing statements is correct concerning the Nuclear Ins tr ument a t i on?

i a.

Source Range level trips are au to m a t i c a l l y activated when power is below the P-10 permissive.

b.

Blocking of rod withdrawal is initiated by ei ther Intermediate Range channel on high flux level.

c.

P-10 permissive alerts the operator to the fact that he must take administrative action to manually block the Source Range trips.

d.

When the P-8 permissive light is lit the low flow reactor trip has a 1 of 3 coincidence.

(*****

CATEGCRY 06 CONTINUED ON NEXT PAGE *****)

6 __ELAMI_S111E53_QE11GHz_CDHIEQLa_AHQ_INSIRUEEHIAIIDb PAGE 24 QUESTION 6.26 (1 00)

Whi ch of the f ollowing is correct concerning the cperation and construction of the Power Range Excore detectors 7 a.

Uses Argon gas inside the detector to limi t " dead t ime."

b.

Has Boron Triflouride (BF3) gas in BOTH inner and outer volumes of the detector.

c.

Operates in the proportional region of the gas amplification curve.

d.

Uses no compensation circuitry to remove gamma curr ent.

QUESTION 6.27 (1 00)

Which of the following would occur if a rod dropped when the Main Tur bine was in " auto-imp in" and power was initially at 50 %7 a.

A load limit runback (cutback) will occur.

b.

A load reference runback ( c u t b ack ) will occur.

c.

Both a load reference and load limit runback (cutback) will occur.

d.

No runback (cutback) will occur.

QUESTION 6.28 (1.00)

Indicate whether the f ollowing statements are TRUE or F ALSE concerni ng the Reactor Protection system.

a.

The 108 % Power Range nuclear flux trip does not provide protection until the low range trip is ma'nually blocked.

b.

The Intermediate Range high nuclear flux trip can be blocked if 1 of 4 Power Range channels is above 10 %.

l I

(*****

C ATEGORY 06 CONTINUED ON NEXT P AGE *****)

ha__ELAHI_SISIEBS_DESIGda_CQHIRQLa_ASQ 151IEUBENIAIIDH PAGE 25 QUESTION 6.29 (1.00)

Which of the following is NOT an SI actuation signal?

a.

High steam line flow coincident with low steas line pressure.

b.

High steam line flow coincident with Low Tavg.

c.

Low steam line differential pressure.

d.

Containment high pressure.

QUESTION 6.30 (1 00)

Whi ch of the f ollowing flowpaths correctly describe the NORMAL power supply to Instrument Bus No. 17 c.

From 480 V a.c.. vital bus, tr ansf ormed to 118 V a.c.,

rectified to 125 V d.cs inverted to 120 V a.c.

b.

From 480 V a.c. vital buss transformed to 118 V a.c.

c.

From 125 V d.c. battery bus, inverted to 110 V a.c.

d.

From 480 V a.c. vital buss transformed to 220 V a.c.,

recti fied to 125 V d.c.s supplied to batterys 125 V d.c.

f rom battery buss inverted l

to 120 V a.c.

QUESTION 6.31 (2.50)

Cencerning MANUAL protection actuation f rom the RTGBs m at ch the following actuations in Column A to their associated actions f rom Column B.

NOTE Column B selections may or may not be used more than once.

Column A Column B a.

Containment Spray (8P' signal) 1.

Depress ONE pushbutton b.

All 3 Steam Isolation valves close 2.

Depress TWO pushbuttons s i mul taneousl y c.

Safety Injection

('S' signal) 3.

Change the position of a d.

Reactor trip selector switch e.

Instrument air to C.V. overrride

( wi th

'S' signal)

( ***** END OF C ATEGORY 06 *****)

Z a__ ER DGEDLIB E1_=_NDRE A ta_ ARHD REA La _EBERE EN CI_AN D PAGE 26 RADIDLDEICAL_CDHIRQL Q UES TION 7.01 (1.00)

Accor di ng to 10CFR20s which of the following is NOT equivalent to a dose of one res?

a.

A dose of 1 roentgen due to gamma radiation.

b.

A dose of 1 rad due to beta radiation.

c.

A dose of 0 3 rad due to neutrons.

d.

A dose of 0.05 rad due to alphas.

QUESTION 7.02 (1.00)

If an individual had already redkehed a whet a bod y dose of 1000 mrea this quarters which of the following would be the maximum additicnal exposure to the skin that he/she could receive this quarter without exceeding to CFR 20 limits?

a.

250 mrem b.

2000 mrem c.

6500 mres d.

7500 mrem QUESTION 7.03 (1.50)

On your answer sheet indicate the word or words that correctly completes the following precautions and limitations of the " Normal Plant Startup From Hot Shutdown To Critical" Procedure (GP-003).

a.

If the countrate on either Source Range channel increases by a factor of ______ or more during any step involving a boron concentration changes the operation must be stopped immediately and suspended until a satisfactory evalation of the situation has been made.

b.

The Control Banks must be maintained above their respective insertion limits while the reactor is critical.

When at powers

___________==

must be initiated immediately if the " Rod Banks A/B/C/D EXTRA LO LIMIT" alarm is actuated.

l c.

Flux multiplication rates shall not be permitted to exceed ____________

l decade (s)/ minute.

(*****

C ATEGORY 07 C ONTINUED ON NEXT P AGE *****)

Za__ERDCEQURE1_=_hDR5ALa_ASHDRB&La_EBERGENCI_AdQ PAGE 27 BA01DLDEICAL_CQHIRQL QUESTION 7.04 (2 00)

Match the chemistry control function in Column A with the chemical that provides this functions from Column B.

Column A Column B a.

Oxidizing Agent used to 1.

Ammonium Hydroxide facilitate crud removal in the RCS.

2.

Lithium Hydroxide b.

Minimize oxygen formation 3.

Hy dr az i ne in the RCS during power operations.

4.

Hydrogen c.

Scavages oxygen in the RCS 5.

Potassi um Chromate prior to heatup from refueling.

6.

Hydrogen Peroxide d.

Primary purpose is for S/G pH control.

7.

Oxygen QUESTION 7.05 (1.50)

Indicate whether the f ollowing statements are TRUE or FALSE concerning information found in the " Plant Cooldown From Hot Shutdown To Cold Shutdown" Procedure (GP-007).

a.

With less than two Reactor Coolant Pumps in oper ations at least one of the f ollowing conditions must be fulfilled

- Shutdown margin is at least 4% delta k/k.

- Lift disconnect switches are open for all control rods not fully withdrawn.

- Shutdown banks are fully wi thdr awn.

b.

When the plant is in Hot Shutdowns the rate of f eedwater addition to.

the Steam Generators should not exceed 400 gpu (200,000 lbe/hr).

c.

The hydrogen concentration in the Reactor Coolant System must be reduced to less than 5 cc/kg and activity to less than 9 uCl/cc if the system is to be opened for refueling or repair.

(***** CATEGCRY 07 CONTINUED ON NEXT PAGE *****)

Za__ERDCEDUREl_=_HORBAL4_ASHDRHALA_EBERGEEC1_AdQ PAGE 28 RAQIDLDSICAL_CQHIRQL l

l QUESTION 7.06 (1.00)

On your answer sheet provide the missing inf ormat ion that correctly coupletes the following statements as found in your General Procedures.

a.

When the RCS is less than _______ degres F ano NCT vented to Containment Vessels the S.I.

Pump power supply breakers must be racked outs and the S.I.

accumulator isolation valves must be closed with their breakers open.

b.

During a plant heatups the RHR loop is isolated when RCS average temperature is between 250 degrees F and ______ cegrees F.

QUES TION 7.07 (1.50)

Indicate whether the f ollowing are TRUE or FALSE concerning precautions and limitations for the CVCS system.

a.

During plant startups letdown flo'w should be initiated at as low an RCS pressure as possible BUT lt could be done when RCS pressure is 525 psig.

b.

Unless both Mixed Bed Deminer alizers have been borated at the beginning of core lifes care should be taken when pl aci ng the standby Mixed Bed demineralizer in service to avoid an undesirable positive reactivity insertion.

c.

Except during periods of Reactor Coolant dilution or borations the Reactor Makeup control should always be kept in "AU TO M AKEUP", with its con tr o l system energized.

QUESTION 7.08 (1 00)

A During a reactor startups if criticality is attained above the control rod low insertion limits but below the estimated critical position (ECP) lower b an ds which of the following actions must be taken?

a.

Insert rods to low Insertion limit and recalculate ECP.

b.

Notify Reactor engineering personnel, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and continue normal startup operations.

c.

Reinsert all control banks to the bottom of the cores evaluate condition and recalculate ECP.

d.

No special action is required; continue normal startup op er at i ons.

(*****

CATEGORY 07 CONTINUED ON NEXT PAGE *****)

Za__ERQCEDU811_=_BD8dAka AAMD&5&La_EBEREENC1_ANQ PAGE 29 i

RADIDLDSICAL_GDHIRDL QUESTION 7.09 (1.00)

Ubich of the below choices best completes this Technical Specification requirement?

Whenever there i s a l o a d chan ge e x cee d i n g _________ percent of rated thormal power in any one hour period, the Lab must be notified to perform an Iodine analysis in the next ________ hourts).

a.

10%,

2-6 b.

101, 4 - 10 c.

15%,

1 d.

15%,

2-6 QUESTION 7 10 (2.00)

On your answer sheet provide the missing numerical values that completes tho following precautions and limitations, as found in the RCS and RCP startup and operation procedure ( O P-101 ) '.

a.

If component cooling water flow to the RCP motor is lost, the RCP must be stopped within _______ minute (s) or before either the upper bearing temperature has increased to _

degrees F or the lower bearing temperature has increased to _

degrees F.

b.

The MINIMUM RCS pressure for RCP operation is ______ psig.

1 l

(***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)

Ia__EEQCEQUEf1_=_HQE5&La_AANQEBAtt_EBERREHCI_AHQ PAGE 30 RARIDLDSICAL_CQHIRDL QUESTION 7.11 (2.00)

Which of the below choices of numbers would correctly complete the following precautions and limitations concerning starting and restarting of Reactor Coolant Pumps?

I a.

After any period of runnings or after any attempt to start where the motor has failed to achieve full speed before it is stoppeds a restart should not be attempted until the motor has been allowed to cool by standing idle for a period of not less than ______ _

_ minutes.

Starts should not a v e r a g e m o r e th a n ________ p e r d a y throughout the life of the RCP motor.

1.

20, 5

2.

30s 6

3.

60s 5

4.

60s 6

b.

Within any two-hour periods the number of starts should be limited to a maximum of ______ (starts) with a minimum idle period prior to each restart.

Wnen these starts or attempted star ts have been made within a two-hour period, then an additional start should not be attempted until the motor has been allowed to cool by standing idle for at least

_______ h o u r ( s ).

1.

Two, Two 2.

Threes Two 3.

Two, One 4.

Three, One i

i

(*****

C ATEGORY 07 CONTINUED ON NEXT P AGE *****)

Ia__ERGCEDURE3_=_HOBBAL4_A350RBALa EBERGEHC1_AMD PAGE 31 RADIDLDSICAL_CDHIRDL QUESTION 7.12 (2.00)

Which of the below choices best completes the following precautions and limitations?

a.

The Pressurizar heatup rate shall not exceed _________ degrees F/ hour and the cocidown rate shall n o t e x c e e d _________ de g r e e s F / h o u r.

1.

60, 100 2.

100s 60 3.

100, 100 4.

100s 200 b.

The RCS heatup rate shall not exceed _________ degrees F/ hour and the cooldown r ate shall not exceed _________ degrees F/ hour.

1.

60s 100 2.

100s 60 3.

100s 100 4.

100, 200 i

QUESTION 7 13 (1.00)

G P-00 3s " Normal Plant Startup From Hot Shutdown to Critical" states that i

the shutdown banks must be at the fully withdr awn position whenever positive reactivity is being inserted.

When can exceptions to this rule be applieds assusing necessary approvals have been received?

a.

When the Shutdown Margin has been calculated to be 900 pcm.

b.

When the RCS has been borated to the cold shutdown concentration.

c.

When the reactor is in the source range wi th the High Flux at Shutdown alarm operable.

d.

When the actual baron concentration is greater.than the predicted critical boron concentration.

(***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)

1

Za__ERDCEDUEEl_=_dQRBALa_ABHQEBALA_E5ERGEdt1_AHQ PAGE 32 HAQIDLEGICAL_CONIEQL QUESTION 7.14 (1.00)

Which of the below choices best completes the following requirement?

To open the No. 1 Seal leakoff bypass valve (CVC-307), the following canditions must be met

- R CS P r e s su r e i s b e t w e e n __________________ p s i g.

- All 3 No. 1 Seal leakoff valves are open.

- Any No. 1 Seal leakof f flow r ate is less than _________ opm.

- Seal injection flow rate to each RCP is greater than ________ spm.

a.

100 - 325, 0.2s 10 b.

100 - 1000s 0 2s 4.0 c.

100 - 1000s 1.0, 6.0 d.

325 - 1000s 3.0, 60 QUESTION 7.15 (1 00)

If a loss of condenser vacuum is impendings with 23" Hg and d ec r e as i r.g s which of the following is NOT an immedia te operatcr action?

a.

Reduce Turbine Generator load.

b.

Verify the standby vacuum pump running.

c.

Start the standby circulating p um p.

d.

Verify the Steam Generator levels not decr eas ing.

f l

l

(*****

C ATEGORY 07 CONTINUED ON NEXT P AGE *****)

Ia__ERQCEDURE1_:.dCREALa_ABMDRBALa_fEERGEHC1_AdQ PAGE 33

)

RADIDLDGICAL_CDHIRDL QUESTION 7 16 (1 00)

Which of the following statements concerning a dropped control rod and retrieval is correct?

a.

Manually insert control rods to match Tref if rods are in manual.

b.

The " Rod Control System Urgent Failure" alarm must be reset prior to commencing retrieval of the rod.

c.

The maximum power allowed prior to, and during, retrieval of the rod is 70% power.

d.

Tave should be controlled by boron changes during retrieval of the rod.

QUESTION 7.17 (1.00)

Which of the following methods of verlfying a reactor trip is NOT a listed verification in the " Response to Nuclear Power Generation /ATWS" Procedure (FRP-S.1)?

a.

Rod position indicator - Zero.

b.

Power Range channels - Less than 5%.

c.

Rod Bottom Lights - Lit.

d.

Reactor Trip and bypass breakers - Open.

QUESTION 7.18 (1.00)

The first immediate action of the " Response to Nuclear Power Generation /

ATWS" Procedure ( F R P-S.1 ) s is to " verify reactor trip".

If the verification is not obtained and if the reactor will not trips the Response Not Obtained Column directs the' operator to do which of the following?

l a.

Manually insert all control rods.

l l

b.

Emergency Borate the RCS.

l c.

Dispatch an operator to manually open the reactor trip breakers.

d.

Close the MSIVs and bypass valves.

(***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)

I a__ EE DCEDUR El_=_ BDRM A L t_ ABSD EB ALa_ EEEEEEH CI_ A N D PAGE 34 BADIDLQG1 CAL _CDNIEDL QUESTION 7 19 (3.00)

On your answer sheet provide the correct values to complete the following Red Path Summary statements from Foldout A.

a.

INTEGRITY - Cold leg temperature decrease g r e a t e r t h a n ______ de g r e e s F in last 60 minutes AND RCS Cold leg temperature less then _______

oegrees F.

b.

CORE COOLING - Subcooling Monitor TCs greater than _______ degrees F.

c.

HEAT SINK - Level in all S/Gs less t he n _______ p er c e n t A ND t o t a l feed-water flow less than 300 gpm or 0.2 x 10-E6 pph.

d.

CONTAINMENT - Containment pressure greater than ________ psig.

e.

SUSCR I T IC ALI TY - N uc l e ar p o we r gr e a t er t h a n __________ pe rc en t.

QUESTION 7.20 (1.00)

Whi ch of the f ollowing methods would be used to reduce RCS pressure to 1950 psig. as listed in the "Natur al Ci rculati on Cooldown" Procedure (EPP-5)?

a.

Steam release via intact S/G PORV's.

b.

Auxillary pressurizer sprays with CVCS le tdown in service.

c.

Steam release via pressurizer PORVs with CVCS letdown in service.

d.

Safety Injection Pump flows with CVCS letdown in service.

QUESTION 7.21 (1.00)

Which of the following Indications are NOT listed in the " Natural Circula-tion" Procedure (EPP-5)s for monitoring an RCS cooloown?

a.

Subcooling Monitor T/Cs - Decreasing.

b.

RCS subcooling - Increasing.

c.

RCS Delta T - Stable or Increasing.

d.

RCS hot leg temperature - Decreasing.

(*****

C ATEGORY 07 CONTINUED ON NEXT P AGE *****)

Za_ ERDCEDUEE1_: BDEBALa_ABNDREAlt_EBERGENC1_ANQ PAGE 35 BAQ1DLDGICAL_CDHIRDL QUESTION 7.22 (1.00)

Indicate whether the following are TRUE or FALSE according to EPP-5.

a.

Prior to RCS depressurizations if all CRDM fans cannot be started, RCS pressure should be maintained at approximately 1950 psig until 190 i

degrees F subcooling is established to prevent formation of a steam void in the vessel during the cooldown.

b.

After borating to RCS Cold Shutdown concentrations all intact steam generators should be steamed for 30 minutes prior to sampling for boron.

QUESTION 7.23 (1 00)

Ind icate whether the following statements are TRUE or F ALSE.

a.

If while implementing a red Functional Restor aticn Procedure (FRP), a higher priority red condition occurs, then the operator should leave the lower priority red FRP and immediately implement the higher priority red FRP.

b.

In using the End Path Procedures (EPP's), the right hand column of actions is to be used ONLY if the associated action in the left hand column does not result in the response specified.

QUESTION 7.24 (1.00)

Using the following 6 Status Tree Saf ety Functions, which of the below choices is the correct order of prioritys beginning with the highest priority?

1.

Subcriticality 2.

Containneent 3.

RCS Integrity 4.

Heat Sink 5.

Core Cooling 6.

Inventory a.

1, 4,

5, 3's 6s 2.

b.

Is 5,

4s 3,

2s 6.

c.

5, is 4s 2,

3, 6.

d.

Is 4,

5, 2,

3, 6.

l

(*****

CATEGORY 07 CONTINUED ON NEXT P AGE *****)

j

i Za__EEDCEQUEES_=_dQEHALa_ASHORBALa_EBEREEHCI_AdQ PAGE 36 RADIDLDGICAL_CQHIRDL i

QUESTION

.25 (1.00)

If a leak devel ped in the Refueling Cavity and was lost to the containment su3ps what is t e minimum level of water that must be on the Containment Vessel (CV) floor prior to aligning the RHR pump suction to the CVf a.

24 inches.

b.

18 inches.

c.

12 inches.

i d.

6 inches.

QUESTION 7.26 (1.00)

What is the reason for having to have a minimum level of water on the CV floor prior to aligning the RHR pumps to take suction f rom the CV7 a.

The benefits of removing the water does no t o ttwei gh the potenti al bad effects of pumping contaminated water into the RCS.

b.

The sump pumps have sufficient capacity to pump this amount of water within 30 minutes.

c.

This level is suf ficient to provide the minimus NPSH for the RHR pumps,.

d.

The RHR pumps suction line taps into the cont ainsent at that level and any water below that level could not be extractec with the RHR pumps.

QUESTION 7.27

(.50)

How many people must be in the SFP Crane cab when it is out of the

" Restricted Path" mode and operating in the Spent Fuel Building?

l

(*****

C ATEGCRY 07 CONTINUED ON NEXT P AGE *****)

I a__ ER DC ED U REs_=_ h 0RB A L A_ AS HDREA ka_EBER GEN CI_ A N Q PAGE 37 BAQ1DLDEICAL_CDDIRQL QUESTION 7.28 (1.00)

If the Plant Vent monitor (R-14) al arms, one of the required actions is to shi f t R-11 and R-12 to the plant vent.

What must be done prior to shifting R-11 and R-127 a.

Ensure FCV-1436A is closed from the local panel.

b.

Evacuate the containment.

c.

Perform a source check on R-11 and R-12.

d.

Verify R-15 is operating properly.

( ***** END OF C ATEGORY 07 *****)

Ra__ADMINISIRAIIME_ERDCEDUBESa_CDHDIIIDHSA_AHQ_LIulIAIIQB1 PAGE 38 QUESTION 8.01 (1.00)

Which of the following is NOT a basis for the control rod insertion limits?

)

a.

Control 50% load rejection without reactor trip.

l b.

Maintain required shutdown margin.

c.

Minimize consequences of rod ejection accident.

d.

Provide for acceptable nuclear peaking factors.

QUESTION 8.02 (1.00)

Which of the following REQUIRE activation of the TSC7 a.

Elther an Unusual Events Alerts Site Emergencys or General Emergency.

b.

Only an Alert, Site Emergencys or General Emergency.

c.

Only a Site Emergency or General Emergency.

d.

Only a General Emergency.

QUESTION 8.03 (1.00)

Which of the following is the basis for the high pressurizer water level l

reactor trip?

a.

Prevents solid operations while the reactor is critical.

b.

Prevents exceeding containment design pressure in event of LOCA with all RCS fluid flashing to steam.

c.

Prevents loss of pressure control due to spray nozzle being submerged.

d.

Protects the pressurizer safety valves agains t water relief.

1

(***** C ATEGORY 08 CONTINUED ON NEXT P AGE *****)

)

Aa__AD51811IBAllYE_ERDCEDUEEit_CDHD1IlDHiz_AHQ_L151IAIIDH1 PAGE 39 QUESTION 8.04 (1.00)

If a proposed temporary change to an operating precedure does not violate the intended function of the procedur e, the change can be implemented on a l

temporary basis following approval by which of the following?

a.

Any two members of the Plant or C 6 A Management Staff.

i b.

Any two members of the Plant or C 6 A Management Staf f, at least one which holds an SRO license.

c.

Any member of the Pl ant or C E A Management S taf f who holds an SRO license.

d.

The Operating Supervisor - Unit 2.

QUESTION 8.05 (1.00) i Which of the following is the maximum time that a temporary change may remain in effect?

a.

21 days b.

30 days c.

45 days d.

90 days QUESTION 8.06 (1 00)

When performing equipment status checks on manual LOCKED valves, which of the following describes how their position is ver if i ed?

a.

Verifying the lock is in place and securely locked.

b.

Verifying local valve position indication is indicating the required position.

c.

Operating the valve in the open direction.

d.

Operating the valve in the closed direction.

l

( ***** C ATEGORY 08 CONTINUED ON NEXT P AGE *****)

i ac__ADEIH11IRAIIME.ERQCEDURESz_CDHDlI1Qdit_AHQ_L151IAI1QB1 PAGE 40 QUES TION 8.07 (1.00)

Which of the following is NOT a responsibility of the Refueling SRO?

a.

Provide watch relief for any refueling station for short periods.

b.

Ensure proper documentation of fuel transfer by verifying the status board and all log entries in Containment.

c.

Maintain overall supervision and coordination of all fuel movement operations.

d.

Be aware of Source Range Nuclear Instrumentation operations RCS temperatures and baron concentration during fuel handling operation.

QUESTION 8.08 (1.00)

Redundant RTGB indicators which require operator attention are checked once a shif t.

This check is made by comparing the highest and lowest channels of redundant indicators for the same parameter on the same sc al e.

Which of following is the maximum acceptable deviation?

a.

4% of the full range of the indicator's movement.

b.

4% of the highest reading indicator.

c.

4% of the lowest reading monitor.

d.

4% of the average of the indicator's readings.

QUESTION 8.09 (1.00)

The injection of a simulated signal into a channel to verify that it is operable is defined in Technical Specifications as as a.

Channel Calibration b.

Channel Check c.

Channel Functional Test d.

Channel Verification i

(*****

C ATEGORY 08 CONTINUED ON NEXT P AGE *****)

Re__AD51HISIRAIIMf_ERDCEDURESa_CDDDIIIDHSz_AND_LIEIIAIIDMS PAGE 41 i

I QUESTION 8.10 (1.00) i Except during low power physics tests, the reactor shall not be mace critical at any temperature above which the moder ator temperature coefficient is more positive thans (Choose one) a.

+5 pcm/ degree from 0 to 50% o f rated power and linearly decreasing to O pcm/ degree at rated power.

b.

O pcm/ degree for all powers up to r ated power.

c.

+5 pcm/ degree for all powers up to rated power.

d.

+5 pcm/ degree at 0% of rated power and linearly decreasing to i

0 pcahtegree at rated power.

QUESTION 8.11 (1.00)

Which of the following methods of RCS leakage detect ion is the most i

sensitive?

a.

Containment Air Particulate Monitor b.

Containment Radiogas Monitor c.

Containment Humidity Monitor d.

Containment Sump Indication QUESTION 8.12 (1.00)

Whi ch of the f ollowing statements is the correct def ini tion of the Quadrant Power Tilt?

a.

The maximum local heat flux on the surface of a fuel rod divided by the average fuel rod heat flux.

b.

The ratio of the maximum to average of the upper excore detector currents or the lower excore detector currents, whichever is greater.

c.

The percent of full power in the top of the core minus the percent of full power in the bottom of the core.

i d.

The ratio of the dif ference between the highest and lowest excore

{

detector currents to the aver age excore detec tor current.

1 i

i

(*****

C ATEGORY 08 CONTINUED ON NEXT PAGE *****)

1 R e__ AD MIBISIRAIIM E_ E R D CE D UREit_C DH DlI1QHit_ AH Q_ L 151I A IIQ33 PAGE 42 QUESTION 8 13 (1 00)

Which of the following is the Technical Specifica tion Saf ety Limit for RCS pressure with fuel assemblies installed in the reactor vessel f a.

2735 psig b.

2850 psig c.

2935 psig d.

3110 psig QUESTION 8.14 (1.00)

An RCS cooldown using one train of RHR and one RC P i s i n progress.

At 300 degrees, the operating RHR pump trips and can not be restarted.

According to the Technical Specifications, which of the following is the REQUIRED action?

a.

Proceed to establish a boron concentration in the RCS to that of or greater than that concentration needed to maintain a shutdown margin of 1000 pcm at 200 degrees.

b.

Start all RCP's within one hour.

c.

Establish the other train of RHR within one hour.

d.

No action is required as long as RCP conti nues to operate.

QUESTION 8 15 (1.00)

Which of the following is the minimum baron concentration in the boron injection tank with which the reactor may remain in operation?

Assume - proper concentration when operations started and consider the time extensions allowed in Technical Specifications.

a.

21,000 ppe b.

19s 500 ppm c.

17s500 ppe d.

15,000 ppe l

(*****

C ATEGORY 08 CONTINUED ON NEXT P AGE *****)

R a__ AD HIMI SIRAIIM E_ER DC ED UEES z_CDH DIIID HSz_AH Q_ LIM II AIID HS PAGE 43 QUESTION 8.16 (1.00)

Which of the following is the basis of the minimum baron concentration roquirement of 1950 ppa while loading and unloading fuel from the reactor?

c.

Maintain reactor subcritical by at least 10000 pcm if no rods were i ns er t ed into the reactor.

b.

Maintain reactor subcritical by at least 4000 pcm if no rods were inserted into the reactor.

c.

Maintain. reactor subcritical if no rods were inserted into the reactor.

d.

Maintain primary temperature less than 200 degrees if no rods were Inserted into the reactor.

QUESTION 8.17 (1 00)

Which of the following correctly describes the maximum allowable extension tices for Technical Specification surveillance intervals?

a.

Plus or minus 25%s not to exceed 3.5 times the specified interval for any 3 consecutive intervals.

b.

Plus or minus 25%s not to exceed 3.25 times the specified interval for any 3 consecutive intervals.

c.

Plus or minus 50%, not to exceed 3 times the specified interval for any 3 consecutive intervals.

d.

Plus or minus 50%, not ot exceed 2.5 times the specified interval for any 2 consecutive intervals.

QUESTION 8.18 (1.00)

According to the Technical Specificationss which of the following is the minimum shift complement during hot operations?

(SF = Shift Foreman, A0 = non-licensed operator) 8.

1 SF (SRO), 1 SR0s 2 Rus 2 Aus 1 STA l

b.

1 SF (SRO)s 2 SR0s 2 R0s 2 AO, 1 STA c.

1 SF (SRO), 1 SR0s 3 R0s 2 A0s 1 STA d.

1 SF (SRO), 2 SR0s 3 R0s 2 A0s 1 STA

( ***** C ATEGORY 08 CONTINUED ON NEXT P AGE *****)

R a__ ADHIBISIRAIIM E_ER QC EDUR Es t_C QH DIIIDHiz_ ANQ_L 151I AIID MS PAGE 44 QUESTION 8 19 (1.00)

Which of the following correctly describes the si te ranning requirements of the Plant Fire Brigade?

a.

At least 6 members, excluding 2 members of the minimum shif t crew necessary for safe shutdown.

b.

At least 6 members, excluding 3 members of the minimum shift crew necessary for safe shutdown.

c.

At least 5 memberss excluding 2 members of the minimum shif t crew necessary for safe shutdown.

d.

At least 5 memberss excluding 3 members of the minimum shift crew necessary for safe shutdown.

QUESTION 8.20 (1 00)

Whi ch of the following is the Technical Speci f ica ti on REQUIREMENT if the number of operable fire detection and actuation instruments is less than roquired?

Assume - Affected Fire Zone is outside of Reactor Containment.

l a.

Within one hours establish a continous fire watch in the affected zone.

b.

Within one hours increase the inspection frequency in the affected zone to once per hour.

c.

Within one hours log the temperature in the affected zone once per hour.

d.

Within one hours place the reactor in hot shutdown.

l l

(*****

C ATEGORY 08 C ONTINUED ON NEXT P AGE *****)

s Rc__ ADHIBI3IR AIIMf_ERQG ED UE Ela._CQHDIIIDMSa._ ANQ_ L151I A IIQ M1 PAGE 45 QUESTION 8.21 (2.00)

Indicate whether the f ollowing statements concerning the Operating Notes given in OMM-1009 are TRUE or FALSE.

a.

The reactor may be taken critical in the intermediate range if indication is above IE-10 amps; if below L E-10 amps, wait until the source range is energized.

b.

If necessary to operate control rods with systes pressure less than 350 psigs when operating is starteds have someone listen at the reactor head area for excessive noise.

4 c.

Leave CCW to excess letdown HEX (CCW-739) normally closed.

d.

Minimize the use of main feedwater pumps to f eed S/G's while in hot shutdown.

QUESTION 8.22 (1.50)

Ind icate whether the following statements concerning clearances are TRUE or FALSE.

a.

More than one person may NOT hold separate cl earances on the same equipment.

b.

Equipment can be operated f or testing purposes while the equipment is under clearance.

c.

Only CPEL employees may hold clearances.

QUESTION 8.23 (1.50)

Match the RCS leakage types in Column A to the Technical Specification licit in Column 8.

l COLUMN A COLUMN B 1.

Unidentified a.

0.00 gpm b.

0.35 spa 2.

Identified' c.

1.00 gpm d.

3.00 sp o 3.

Primary to Secondary (all e.

5.00 ope generators)

f. 10.00 ops

(*****

CATEGORY 08 CONTINUED ON NEXT PAGE *****)

4 4

Ra__A051Hl3IRAIIME_ERDCEDUEilt CQHDlIIQUlt_AHQ_L151IAIIQBS PAGE 46 l

QUESTION 8 24 (2.50)

Match the Reactor Trip signals in Column A to its basis in Column B.

I COLUMN A COLUMN B 1.

Overtemperature Delta T a.

RCS Integrity 2.

Overpower Delta T b.

Solid Plant Operation 3.

Low Pressure c.

DNB l

4.

High Pressure d.

Startup Accident 5.

Low Flow e.

Excessive Power Density S

f.

Rod Ejection 9.

Loss of Heat Sink l

QUES TION 8.25 (1 00)

Fill in the blanks f or the following statements ccncerning Locked High Radiation Areas (LHRA).

l a.

Each High Radiation Area with radiation Intensity greater than mres/hr shall be locked with a Controlled Key.

b.

Acc es s to Lo cked Hi gh Radi a ti on Ar ea s i s c ont ro l led b y th e ________.

QUESTION 8.26 (1 50)

According to the Technical Specificationss what THREE conditions would require that a control rod be declared inoperable?

QUESTION 8.27 (1.00)

With the reactor critical at greater than 350 degrees, what TWO conditions cust be met for the pressurizer to be considered operable?

(***** CATEGORY 08 CONTINUED ON NEXT PAGE *****)

A4__ADHIBISIRAIIME_E80CEDUSE1t CDHDIIIQHia_AHQ_L1511AIIQHS PAGE 47 QUESTION 8.28 (1.00)

Under what plant conditions is the overpressure protection system required to be operable?

QUESTION 8 29 (1.00)

Whon a system is determined to be inoperable solely because its normal pcwer supply is inoperables i t may be considered operable for the purpose of satisfying the requirement of its applicable LCOs provided two conditions are met.

List these TWO conditions.

QUESTION 8.30 (2.00)

List FIVE individuals (by title) who can relieve the Shift Foreman as the Site Emergency Coordinatory W aceo,J uee w ', %

'P E 9 - oo l. 2.4 w a 4 % ow e.

r a%er we g lis4s o uee 64tvidua, %en %wer 4 4 e. g%G

+e 4, ba44 o4 l

i y ou.y kwow\\ed q q.

l l

i

(***** END OF CATEGORY 08 *****)

( * * * * * * * * * * * *

• E N D OF. E X A MIN A TI O N * * * * * * * * * * * * * * * )

EQUATION SHEET f = ma v = s/t Cycle efficiency = (Net wcrk cut)/(Energy in) 2 w = mg s=V:

• 1/2 at 3

2 E = mc KE = 1/2 mv a = (Vf - V )/t A = AN A = A e

3 3

PE = mgn yf = V, + at

• = e/t x = tn2/t;jg = 0.693/t1/2 2

1/2* " " C( * }( }

W = v f,p nD

((c/2)*(*0Il A=

l 4

ti = 931 sm m=V Ao

-n av x,Ie o Q = mCoat Q = UAa7 I=Iea I = I,10-* E Pwr = w 2 f

T/L = 1.3/u P = P 10,sur(t)

HVL = -0.593/u o,,.

P = P e' '

o SUR = 25.06/T SCR = 5/(1 - K,y)

CR = 5/(1 - K,ffx) x SUR = 2So/ t* + (s - o)T CR;(1 - K,g)) = CR 5I ~ "e # 2) 2 T = ( t*/a ) + ((s - o V Io]

M = 1/(1 - K,g) = CR /G z

3 T = 1/(o - a)

M = (1 - K III effo effl)

~

T = (a - o)/(Io)

SCM = ( - K,g)/K,g a = (Keff-1)/K,g = :X,ff/K,ff L' = 10 seconcs I = 0.1 seconds ~I o = ((t*/(T K,g)] + (T,g/(1 + IT)]

l1*Id Id 2,2 2 P = (t4V)/(3 x 1010)

Id y#

j 2

2 I = sN R/hr = (0.5 C2)/d (meters)

R/hr = 6 CE/d2 (feet)

Water Parameters Miscellaneous Conversions 1 gal. = 8.345 lem.

1 curie = 3.7 x 1010 egg 1gaj.=3.78 liters 1 kg = 2.21 lem 1 f.

= 7.48 gal.

1np=2.34x103Stu/nr Oensity = 62.4 lbe/ft3 1.w = 3.41 x 100 5tu/hr Oensity = 1 gm/cd ifn = 2.54 cm Heat of vaporization = 970 Stu/lem

• F = 9/5'C + 32 Heat of fusion = 144 Stu/ltm

'C = 5/9 (*F-32) 1 Atm = 14.7 psi = 29.9 in. Hg.

1 STU = 778 ft-lbf I ft. H O = 0.4335 lbf/in.

2

ma sT ER S a__IMED RI_ D E_H UC LEAE_ EDM EE_E LABI_ D EERAIIDHz_EL MIQ 3 a _ AN D PAGE 48 IMEREDDINA51E3 ANSWERS -- ROBINSON

-85/06/18-VINNOLA, A.

ANSWER 5.01 (1.00) c REFERENCE NUSs Nuclear Energy Training - Reactor Operations p.

6.4-2 Wostinghouse Reactor Physicss p.

1-3 15 HSRs Reactor Theorys Session 43s

p. 3 ANSWER 5 02 (1.00) d REFERENCE VEGPs Training Texts Vo l. 9s pp. 21-60 C 61 Westinghouse Reactor Physicss Sect. I-5 HBRs Reactor Theory, Session 26, p.

2 ANSWER 5.03 (1.00) b REFERENCE VEGPs Training Texts Vol. 9, p.

2A-63 and VEGP Question Banks 857 HBRs Reactor Theorys Session 29s

p. 2 ANSWER 5.04 (1 00) b REFERENCE NUS, Nuclear Energy Trainings Nodule 3s Unit 6 WGstinghouse Reactor Physicss S ect. 3s Neutron Kinetics and Sect. 5s Core Physics HBRs Reactor Theorys Sessions 20 and 24 - 31

2a__IMEDRI_DE_HUCLEAR_EDMER_EL&dI_DEEE&IIDHa_ELULD3t_ AND PAGE 49 IHE150DIB&51CS i

ANSWERS -- ROBINSON

-85/06/18-VINNOLA, A.

1 ANSWER 5.05 (1.00) d REFERENCE Wostinghouse Reactor Physics, pp. 1-5.63 - 76 H8Rs Reactor Theorys Sessions 38 and 39 ANSWER 5.06 (1 00) d REFERENCE Westinghouse Reactor Physics, pp. 1-5.36 - 50 HBR, Reactor Theorys Session 35, p.

5 ANSWER 5.07 (1.00) a REFERENCE Wostinghouse Reactor Physicss pp. I-2.19 - 21 H8Rs Reactor Theory, Session 14,

p. 3 ANSWER 5.08 (1.00) b REFERENCE Wostinghouse Reactor Physicss p.

I-5.40 HBRs Reactor Theory, Session 36,

p. 2 ANSWER 5.09 (1.00) b REFERENCE W8Ns TS, p.

B 3 / 4 1-1 H8Rs TS, p.

3.10-10 i

l l

l

la__IMEDRI_DE_SUCLEAR EDMER_ELAMI_DEERAIIDHt_ELU103A_AdQ PAGE 50 IMEREDEXBadICS ANSWERS -- ROBINSON

-85/06/18-VINNOLA, A.

ANSWER 5.10 (1.50) a.

Power Defect (-0.25 for power coefficient) b.

Reacti vi ty(or he94) c.

Beta (minus) Decay REFERENCE Westinghouse Reactor Physics, pp. I-5.26, I-3.2, and I-1 18 awan d A - 13 H8Rs Reactor Theory, Session 32,

p. 3 and Session 21, p.

2 and Session 4s p.

2 ANSWER 5.11 (1.50) e.

FALSE b.

FALSE c.

TRUE REFERENCE Westinghouse Reactor Physics, pp. I-3.9 and I-3.4 HBR, Reactor Theory, Sessions 22 and 23 ANSWER 5.12 (1.00) b

.=

REFERENCE HBRs Reactor Theory, Session 42, pp. 4 6 10 ANSWER 5.13 (1.00) c REFERENCE HBRs Reactor Theory, Session 42s pp. 3 &4 ANSWER 5.14 (1 00) a

24__IBEDRI_DE_HUCLEAE_EDMER_ELABI_DEERAIIDHt_ELUIDSa_AHQ PAGE 51 IdEREDDIHABIES ANSWERS -- ROBINSON

-85/06/18-VINNOLA, A.

REFERENCE HSRs Reactor Theory, Sessions 41 and 42 ANSWER 5 15 (1.00) d REFERENCE NUS, Nuclear Energy Tr aining - Reactor Operation, p.

10.5 4 Westinghouse Reactor Physics, pp. 1-5.77 - 79 VEGPs Training Texts V o l. 9, pp. 21-81 & 82 HSR, Reactor Theorys Session 37, p.

4 ANSWER 5.16 (2.00) a.

RENAIN THE SANE b.

DECREASE c.

INCREASE d.

DECREASE REFERENCE Stoan Tables ANSWER 5.17 (1.00) c REFERENCE Puap Laws ANSWER 5.18 (1.50) a.

FALSE b.

TRUE c.

TRUE REFERENCE General Physicss HTEFF, pp. 155, 319, and 320 and Subcooled Liquid Density Tables

2 a__IMEQRI_Df_SUCL EAE_ EDMER_EL AMI_ DEER AIIDu a_EL UID34_ AND PAGE 52 IUEEBDDIBABICS ANSWERS -- ROBINSON

-85/06/18-VINNOLA, A.

ANSWER 5 19 (1.00) d REFERENCE Gen er al Physics, Heat Transfer Thermodynamics and Fauld Flows pp. 145 - 148 A NS W ER 5 20 (1.00) b REFERENCE General Physics, Heat Transfer Thermodynamics and Fluid Flows pp. 145 - 160.

ANSWER 5.21 (1.00) c REFERENCE General Physicss HT & FFs Section 3.2 WBNs HT & FF, p.

13 ANSWER 5.22 (1 00) b REFERENCE General Physicss HT & FFs p.

328 WBNs HT & FFs p.

17

)

I ANSWER 5.23 (1.00) d REFERENCE Surry, TS 3.12-16 and 17 HBRs TS, p.

3.10-13 4

1

ta__IBEDR1_DE_SUCLEAE_EDMER_ELAMI_DEERAIIDNA_ELUIDSz_ANQ PAGE 53 IMERBDDIB&BICS ANSWERS -- ROBINSON

-85/06/18-VINNCLA, A.

ANSWER 5.24 (1.50) a.

Latent Heat (of Vaporization) b.

DNBR c.

Heat Flux Hot Channel Factor REFERENCE WBNs HT & FFs pp. 11, 22, and 24 General Physics, HT E FF, pp. 38 & 231 and HBR, T S, p.

3.10-12 ANSWER 5.25 (1.00) c REFERENCE WBNs HT & FFs p.

19 G0neral Physics, HTEFF, p. 10 5 ANSWER 5.26 (1 00) b REFERENCE HBRs TSs p.

3 1-7 ANSWER 5.27 (1.00) a REFERENCE HBR, TS, p.

3 1-22 and HBR Question Banks # 1-14 ANSWER 5.28 (2.00) a.

INCREASE b.

INCREASE c.

DECREASE d.

DECREASE i

f i

.~.

Aa__IMEDRI_DE_HMCLEAR_EDMER_ELAHI_DEERAIIDHA_ELuinst_ASD PAGE 54 IMEREDDIBAHICS ANSWERS -- ROBINSON

-85/06/18-VINNOLAs A.

REFERENCE General Physicss HTFF - Fluid Flow Applications for Systems and Components ANSWER 5.29 (1.00) d REFERENCE Westinghouse Reactor Physics, Section I-5s MTC and Power Defect H8Rs Reactor Theory, Session 48 ANSWER 5.30 (1.00) b REFERENCE W8Ns TSs p.

B 3/4 2-1 HBR, TSs p.

3.10-17 ANSWER 5.31 (1.00) d REFERENCE WBNs TS, p.

3/4 2-4 HBRs TSs pp. 3.1C-2 6 3 f

e

-,v.

ha__ELAMI_SIIIE53_DE11GHz_CQHIRQLA_Aha_IdilRUBEHIAIIDH PAGE 55 ANSWERS -- ROBINSON

-85/06/18-VINNOLA, A.

l 1

ANSWER 6.01 (1.00) c.

REFERENCE H8R/SD-025, p.

16.

ANSWER 6.02 (1.50) a.

T.

i b.

T.

c.

F.

REFERENCE HBR/SD-025 pp.

1, 8, 11, 23a.

ANSWER 6.03 (1.50) a.

5.

or 6.

b.

4.

c.

7.

REFERENCE H8R/SD-025. p 18.

ANSWER 6.04 (1 50) a.

3 b.

I c.

2 REFERENCE HBR/SD-033, pp. 50, 70-72.

ha__ELAHI_111IE53 DESIGNA_CQHIRQLA_AE_INIIEUBEMIAIIDd PAGE 56 ANSWERS -- ROBINSON

-85/06/18-VINNOLA, A.

ANSWER 6.05 (1.50) a.

F b.

T

'c.

T REFERENCE HBR/S D-033 pp. 12-15.

ANSWER 6.06 (1 00) a.

REFERENCE HBR/S0-033, p.

20.

ANSWER 6.07 (1.00) c.

REFERENCE HBR/SD-034s p.

53.

ANSWER 6.08 (1.00) d.

REFERENCE HBR/SO-021 pp. 4-7 & 13.

ANSWER 6.09

(.50)

T.

REFERENCE HBR/SD-021, p.

10.

~

ha__ELABI 1131EBS DESIGHa_E0HIROLA ABQ IH11RDBENIAIIEh PAGE 57 ANSWERS -- ROBINSON

-85/06/18-VINNOLA, A.

l ANSWER 6.10 (1.00) be REFERENCE HBR/0WG. No. 5379-685.

ANSWER 6.11 (1.00)

X. C.

REFERENCE HBR/DWG. No. 5379-685.

e ANSWER 6.12 (1.00)

C, REFERENCE S0-013 pgs 1-2 ANSWER 6.13 (1.00) a.

F, b.

F, REFERENCE HBR/SD-017s pp.

7, 8.

ANSWER 6.14 (1.00) d.

REFERENCE HBR /S D-02 3s pp. 30-31.

6.__ELAMI_313IE53-QESIGNa_EDHIEDLa_AHQ_INSIEMBENIAIIDM PAGE 58 ANSWERS -- ROBINSON

-85/06/18-VINNOLA, A.

ANSWER 6.15

(.50)

F.

REFERENCE HBR/SD-035, pp. 15-16.

ANSWER 6.16 (1 00) d.

REFERENCE HBR/SD-048, p.

5.

l ANSWER 6.17 (1 00) a.

F.

b.

T.

REFERENCE H8R/SD-027, pp. e-10.

ANSWER 6.18 (1 50) a.

F, j

b.

T.

c.

T.

REFERENCE l

HBR/SD-005 pp.

2-3.

ANSWER 6.19 (1.00) be or c.,

ha__ELAMI_SISIEBS DESIGHa_CDHIEDLa_AHQ_IH1IRUMENIAIIDH PAGE 59 ANSWERS -- ROBINSON

-85/06/18-VINNOLAs A.

REFERENCE HBR/SD-002s pp.

8, 26) p,12.

ANSWER 6.20 (1.00) b.

REFERENCE SD-019 pg. 3 ANSWER 6.21 (1 00) b.

REFERENCE SQNs Rod Control Lessons p.

4 of 11.

HBR/SD-007s p.

4.

ANSWER 6 22 (1 00) d.

REFERENCE HBR/SD-009, p.

3.

ANSWER 6.23 (2.00) a.

F.

b.

F.

c.

T.

d.

T.

I REFERENCE HBR/SD-007, pp.

5, 7, 14, 16, 21, 22.

t

6.__ELABI_IIIIE51_DE11 Eda _CQHIRDLa_ABD_1HiltuBENIAIIDH PAGE 60 ANSWERS -- ROBINSON

-85/06/18-VINNOLAs A.

ANSWER 6.24 (1.00)

De REFERENCE SQN/ System Manuals Chapter 11.5s Fig. 11.5-1, p.

11.5-39 H BR /S D-010 s pp.

6-8.

ANSWER 6.25 (1 00) b.

REFERENCE HBR/SD-010; pp.

3, 29, 30.

i ANSWER 6.26 (1.00) d.

REFERENCE HBR/SD-010, pp.

6, 19-22.

ANSWER 6.27 (1 00) b.

REFERENCE H8R /S D-011s p.

15.

ANSWER 6.28 (1.00) a.

F.

b.

F.

REFERENCE NBR/SO-011; pp. 2, 5.

I l

h a__ EL ABI_11SIE 55_DE11E Ma_EDHIRO L a _ ABQ _181IEU 5 E NIAIID H PAGE 61 ANSWERS -- ROBINSON

-85/06/18-VIhMOLA, A.

ANSWER 6.29 (1.00)

C, REFERENCE HBR/SD-006, p.

3.

ANSWER 6.30 (1 00) b.

REFERENCE HBR/SD-016s pp. 15, 293 and diagram in Elec. Distribution Session 5, p.

13.

l l

3.00 ANSWER 6 31 FE.50) a.

2.

t.

2.

c.

1.

d.

1.

e.

3.

REFERENCE H8R Dwg. No.'s 300-5379-2753)

. 759.

HBR/SD-006s pp. As 5,

los 12.

e 1

l

.i a..

Ia__ERDCEDMRE1_=_HDEMALa_ABSQRMALA EBERGENC1_AMQ PAGE 62 BADIDLDEICAL_CQHIRQL ANSWERS -- ROBINSON

-85/06/18-VINNOLAs A.

ANSWER 7.01 (1.00) c.

REFERENCE 10CFR20, Sec. 20.4c ANSWER 7.02 (1.00)

C, REFERENCE 10 CFR 20 ANSWER 7.03 (1.50) a.

2 b.

EmergencyCO.23 BorationCO.33.

c.

1, REFERENCE H8R/GP-003s pp. 10-12.

ANSWER 7.04 (2 00) a.

6.

b.

4.

c.

3.

d.

1.

REFERENCE HBR/GP-007, p.

25J H8R/SD-031s pp. 4s 8.

l l

'~

Za__ERDCEQUEEl_=_dQRBALa_ABEDERAta._EEEEEHCI_AHQ PAGE 63 BAQ1DLDG1 CAL _CDHIRQL ANSWERS -- ROBINSON

-85/06/18-VINNOLA, A.

ANSWER 7.05 (1.50) a.

F.

b.

T.

c.

T.

REFERENCE HBR/GP-007s pp.

8-9.

ANSWER 7.06 (1.00) a.

350 b.

350 REFERENCE HBR/GP-001.

p.

9; H8R/T.S.,

3. 3.1. 3 J HBR/GP-002, p.

15, 41.

ANSWER 7.07 (1 50) a.

F.

b.

T.

c.

T.

REFERENCE HBR/0P-301, pp. 7-10.

ANSWER 7.08 (1.00) c.

REFERENCE H BR / G P-00 3, p.

25.

Ia__ERDCEQUEE3_=_bOR5&La_ABBQEBALA_EBEREENCI_AND PAGE 64 RADIDLDGICAL_CQHIRQL ANSWERS -- ROBINSON

-85/06/18-VINNOLAs A.

ANSWER 7.09 (1 00) d.

REFERENCE HBR/GP-005, p.

25.

H8R/T.S., Table 4.1-2.

ANSWER 7.10 (2.00) a.

2, 200, 225.

b.

325.

REFERENCE H8R/0P-101, pp. 9-10.

ANSWER 7.11 (2.00) a.

2 b.

4 REFERENCE HBR/0P-101, pp. 10-11.

ANSWER 7.12 (2.00)'

a.

4 b.

1 REFERENCE HBR/T.S.,

p.

3.1-5; HBR/GP-002,

p. 15.

ANSWER 7.13 (1.00) b.

Za__ERDCEDURE1_=_bORMAL4_AAHORBALA_EBERGENCX_AND PAGE 65 RAH DLD H CAL _CQHIROL ANSWERS -- ROBINSON

-85/06/18-VINNOLAs A.

REFERENCE SONP/GOI-2s p.

2.

H8R/GP-003, p.12.

ANSWER 7.14 (1.00) c.

REFERENCE H8R/GP-001, p.

19.

ANSWER 7.15 (1.00) d REFERENCE H8R/AOP-012, pp.

4-5.

ANSWER 7.16 (1.00) a 6r C REFERENCE HBR/AOP-001. pp. 15-18.

ANSWER 7 17 (1.00) b REFERENCE HBR FRP-S.1 pg. 3 s

ANSWER 7.18 (1 00) a REFERENCE HBR/FRP-S.1, pp. 3-4.

j

Za__EEQCEDURE1_ _NORMALa_ABEDERALa _ EMEREEHC1_ANQ PAGE 66 EAQ1DLDSICAL_CDEIRDL ANSWERS -- R08INSON

-85/06/18-VINNOLAs A.

ANSWER 7.19 (3.00) a.

100s 310 b.

1200 c.

25 d.

42 0.

5 REFERENCE H8R EPP-Foldouts, pg. 4 ANSWER 7 20 (1.00) b.

REFERENCE HBR EPP-5 pg. 7 ANSWER 7.21 (1.00)

C REFERENCE HBR EPP-5 pg 8 ANSWER 7.22 (1 00) a.

T b.

T REFERENCE H8R/EPP-5, pp. 9-10.

Ia__ EE QCEDU RE1_=_ dQR5&La_ A A MQRBALa_EBERGENCI_ A M Q PAGE 67 BARIDLOGICAL_CDMIRDL ANSWERS -- ROBINSON

-85/06/18-VINNOLAs A.

ANSWER 7.23 (1.00) a.

T.

b.

T.

REFERENCE HBR/EOP-HO-4 & -5.

ANSWER 7.24 (1.00) b.

REFERENCE HBR/CSFST Diagram.

ANSWER 7 25 (1.00) b REFERENCE HBR/FHP-035, p.

11.

ANSWER 7.26 (1 00) c REFERENCE HBR/FHP-035s p.

11.

AMittR 7 27 i. 5M-

%\\e Le N j

-g

-REFERE NC t j

i H6R-/f MF-0 3 4, p.

2.

24__EROCEDURE1_=_HORMALa_ARBORBALa_EBERGENCI_AND PAGE 68 RAQ1DLDEICAL_CDHIRDL ANSWERS -- ROBINSON

-85/06/18-VINNOLA, A.

1 ANSWER 7.28 (1.00) b.

REFERENCE HBR/AOP-005, p.

15.

i l

I i

l l

I

,.,,,, ~

Ac__ AQ51dISIR AIIME_EEDGEDUBE3a_CQHDIIIDH32_AN Q_LIHlI AIIQHS PAGE 69 ANSWERS -- ROBINSON

-85/06/18-VINNOLA, A.

ANSWER 8.01 (1.00) a REFERENCE Surry, TS 3.12-11 and 12 H8Rs TSs p.

3.10-10 ANSWER 8 02 (1.00) b REFERENCE VEGPs Emergency Plan, p.

3-3 Surry, EPIP-3.02, p.

I and E PIP-3.03, p.

1 WBN, IP-2, IP-3, IP-4s and IP-5 HBR, PEP-102 - 106 ANSWER 8.03 (1.00) d REFERENCE Surry, TS 2.3-7 USNs TSs p.

B 2-5 H8Rs TSs p.

2 3-5 ANSWER 8.04 (1.00)~

b REFERENCE HBRs AP-004, p.

29 ANSWER 8.05 (1.00) a REFERENCE H8Rs AP-004s p.

30 1

f n

l R a__ ADMINISIB AIIM E_ ERD CEDURE1a_CDHDIIIQMSA_AHQ_L1511AllDdi PAGE 70 i

ANSWERS -- RGBINSON

-85/06/18-VINNOLA, A.

ANSWER 8.06 (1.00) d REFERENCE H8Rs AP-027, p.

6 ANSWER 8.07 (1.00)

C REFERENCE HBR, OMM-006, pp. 5E6 ANSWER 8.08 (1.00) a REFERENCE HBR, OMM-1006, p.

2 ANSWER 8.09 (1.00) c REFERENCE McG, TS, p.

1-1 Surry, TS 1.0-3 Cats TSs p.

1-1 W8N, TS, p.

1-1 H8Rs TSs p.

1-3 ANSWER 8.10 (1.00) a REFERENCE HBR, TSs p.

3.1-11

Aa__AQ51N1111AIIME_ERQCEQMBEiz_CQHDIIIQMia_AHQ_LI51IAIIQMS PAGE 71 ANSWERS -- ROBINSON

-85/06/18-VINNOLAs A.

ANSWER 8.11 (1.00) a REFERENCE H8Rs TSs p.

3.1-18 ANSWER 8 12 (1.00) b REFERENCE HBRs TS, p.

1-4 ANSWER 8 13 (1.00) a REFERENCE H8Rs TSs p.

2.2-1 ANSWER 8 14 (1.00) d REFERENCE H8Rs TSs p.

3.1-2 ANSWER 8 15 (1.00) d REFERENCE H8Rs TSs p.

3.3-4 ANSWER 8 16 (1.00) c

~

ac__AQ518111RAIIME_ERDGEDilBilt CDHD1IIQuia_AHQ_L152IAIIDH1 PAGE 72 ANSWERS -- ROBINSON

-85/06/18-VIhMOLA, A.

REFERENCE HBR, TS, p.

3.8-4a ANSWER 8 17 (1.00) b REFERENCE HBRs TSs p.

4.1-1

(

ANSWER 8 18 (1.00) a REFERENCE HBRs TSs p.

6.2-1 ANSWER 8 19 (1.00) d REFERENCE HBRs TS, p.

6.2-2 ANSWER 8.20 (1.00) b REFERENCE H8Rs TSs p.

3.14-1 ANSWER 8.21 (2.00) a.

TRUE b.

TRUE c.

FALSE de FALSE REFERENCE H8Rs OMM-1009, pp. 5, 3s 4,

and 6

)

Ra__AD51BI118AIIME ERQCEDURElt_CONDIIIQNit ANQ_LI511AIIDMS PAGE 73 ANSWERS -- ROBINSON

-85/06/18-VIhNOLA, A.

I I

ANSWER 8.22 (1.50)

I a.

FALSE

b.

FALSE c.

FALSE REFERENCE f

HBRs OMM-005, pp. 6 & 8 ANSWER 8.23 (1.50) 1.

c 2.

f 3.

c

+

REFERGNCE HBR, TSs p.

3.1-16 ANSWER 8.24 (2.50) 1.

c 2.

e 3.

c 4.

a 5.

c

(

REFERENCE l

HBRs TSs pp. 2.3 6 I

ANSWER 8 25 (1 00) a.

1000 b.

RC Foreman REFERENCE I

HBRs AP-027, p.

21 l

l l

f l

Ra__AQ5INI11RAIIME_ERDCEDlJREst_CDHDII1Duit_AHQ_LI51IAIIDMS PAGE 74 ANSWERS -- ROBINSON

-85/06/18-VINNOLAs A.

)

ANSWER 8.26 (1 50) 1.

Misaligned

(> 15 inches) with its bank 2.

Can not be moved by its drive mechanism l

3.

Drop time is not met REFERENCE HBRs TSs p.

3 10-8 ANSWER 8.27 (1.00) (Ay b f4k Sb mgcop uJ) 1.

All (three) safety valves operable.

2.

At least 125 kW of heaters (0.25 pts) capable of being powered from an emergency power source (0.25 pts) operable.

3 Mt e. p n s s ew4 rot sy s% op wie,

o REFERENCE HBRs TSs p.

3.1-3a,*. W s b 4-c..

I~

ANSWER 8.28 (1.00) 1.

RCS temperature less than 350 degrees 2.

RCS not vented to containment REFERENCE l

HBRs TSs 3.1-4 1

ANSWER 8.29 (1.00) l 1.

Its emergency power source is operable 2.

Its redundant system is operable REFERENCE HBRs TS, p.

1-2 i

..o a i__ AD dIBISIE AIIY E_E E QC E D U111s._C DH DlI1D Hia._ AH Q _ L1HII A l10 H1 PAGE 75 ANSWERS -- ROBINSON

-85/06/18-VINNOLAs A.

ANSWER 8.30 (2.00)

(Any 5 at 0.4 pts each)

Or flant General Manager

@ @anager - Operations) 6 aintenance Q3 Manager - Technical Support Manager - E & RC Operating Supervisor l

Supervisor on calI a.Wec % :c.S % % ee

b. I & c. m ew % e,_

REFERENCE e.,

std _ Di% c, yA HBR, PE P-001, p.

5 c), g gy_.,%

0-A

- % vde e,q Ne'., _. s + 9~ _,

4 I