Text

Exam Rept 50-400/OL-85-02 on 851104-07 & 12-15.Exam Results: 33 Candidates Passed Oral Exams & 34 Candidates Passed Written Exams.Summary of Exam Results Withheld (Ref 10CFR2.790)
	ML20140C694
Person / Time
Site:	Harris
Issue date:	01/13/1986
From:	Rogers T, Wilson B; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	;
Shared Package
ML20140C681	List: ML20140C676; ML20140C694;
References
	50-400-OL-85-02, 50-400-OL-85-2, NUDOCS 8601280386
	Download: ML20140C694 (139)
	v • d • e

_ _ _ _ _

UNITED STATES

/pm RirgDo NUCLEAR REGULATORY COMMisslON

[ n REGION ll g j 101 M ARIETTA STREET, N.W.

2 ATLANTA, GEORGI A 30323

\,...../

ENCLOSURE 1 EXAMINATION REPORT 400/0L-85-02 Facility Licensee: Carolina Power and Light Company P. O. Box 1551 e Raleigh, NC 27602 Facility Name: Shearon Harris Facility Docket No.: 50-400 Written and oral examinations were administered at the Shearon Harris Nuclear Power Plant near New Hill, Nort Carolina.

Chief Examiner: -

am / f!#(o Thomas Rogers / Date Signed Approved by: a . .

l[IS/E BrfceA. Wilson,SectionChief Date' Signed Summary:

Examinations on November 4-7, and 12-15,1985 Oral examinations were administered to 34 candidates; 33 of whom passed. Written examinations were administered to 34 candidates; 34 of whom passed. No simulator examinations were administered.

30 Senior Reactor Operator licenses were issued.

3 Reactor Operator licenses were issued.

+,

8601280394 860115

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ADOCK 05000400 PDR L._

2 REPORT DETAILS

1. Facility Employees Contacted:

J. L. Harness, Assistant Plant General Manager

J. Hudson, Project Specialist - Licensed Training

W. Powell, Director of Training - Harris

J.. Thompson, Operations Supervisor

D. Tibbits, Project Specialist - Regulatory Compliance

A. C. Tollison, Manager - Nuclear Training J. L. Willis, Plant Manager

Attended Exit Meeting

2. Examiners:

L. Defferding, PNL W. Henning, EG&G P. Isaksen, EG&G F. Jaggar, EG&G

T. Rogers, USNRC T. Vinnola, EG&G

Chief Examiner

3. Examination Review At the conclusion of the written examinations, the exams were released to the facility staff to review the written examinations and answer keys. The following comments were made by the facility reviewers:

a. R0 Exam (1) Question 1.04 Facility Comment: Recommend accepting choice a, b or c as answers. The answers could vary depending on the assumptions made by the candidates.

Reference attached.

NRC Resolution: Not accepted. With indications and conditions given in the question stem and the reference provided by the facility, the best answer works out to be approximately 10% shutdown which is answer d. Therefore, answer key has been changed to d. Any other assumptions made by the candidates would not be answering question as written but would be changing the question conditions.

3 (2) Question 1.15 (AnswerKey)

Facility Comment: Typographical error on answer key. Should be

a. 3 instead of a c

a. 1 b. a NRC Resolution: Accepted. Key has been revised.

(3) Question 2.01 Facility Comment: Recommend accepting choice c or d as answers.

Both statements are correct. Reference attached.

NRC Resolution: Accepted. Answer c or d is correct. Answer key has been revised.

(4) Question 2.14 Facility Comment: Part b - Recommend accepting either 2% or 0.5%

as answers. Reference attached.

NRC Resolution: Partially accepted. The answer key has been changed to accept 2% per reference provided, but will not accept both answers.

(5) Question 2.16 Facility Comment: Recommend accepting either 240,000 GALLONS or 254,000 GALLONS as answers for the first fill-in-the-blank selection.

NRC Resolution: Not accepted as stated. The answer key has been changed to accept 254,000 gallons per the Technical Specification reference provided by facility.

(6) Question 2.17.c Facility Comment: Part c - Recommend accepting POWER or NONE as answers. Power Range could be selected due to the small amount of gamma flux compared to the neutron flux and the question references .

"EXCORE NUCLEAR INSTRUMENTATION RANGES".

Reference attached.

-4 NRC Resolution: Not accepted. All nuclear instrument detectors are affected by gamma radiation whether the instrument compensates for the affect or not. As for the comment about the question referencing the " Ranges", b and part c ask about a detector. The detector is an integral part of the instrument be it

, Source, Intermediate or Power Range.

(7) Question 2.17.e Facility Comment: Part e - Recommend accepting ALL or NONE.

None could have been selected because the question could have been interpreted as to which one covered 12 decades.

NRC Resolution: Not accepted. The stem of the question clearly stated that "More than one may apply to each."

(8) Question 3.04.b Facility Comment: Part b - Explanation for question is SHNPP uses the technology of Hi-1, Hi-2 and Hi-3.

Hi-1 and Hi-2 are 2 out of 3; Hi-3 is 2 out of

4. Recommend accepting 2 out of 3 or 2 out of 4 if written in. Reference attached.

NRC Resolution: Accepted. Will accept 2 of 4 if explained as Hi-3 actuation point.

(9) Question 3.04.d Facility Comment: Part d - Recommend changing answer from false to true. Reference attached.

NRC Resolution: Accepted. Answer has been revised.

(10) Question 3.08 Facility Comment: Recommend not requiring selection f as part of the answer. Turbine impulse pressure goes to the S/G water level control system but is not used (constant level). Reference attached.

NRC Resolution: Not accepted. The facility reference supports the answer key.

5 (11) Question 3.10 Facility Comment: The question could have correctly been answered (that there is no correct answer).

Part d is incorrect because the PZR PORV's will automatically operate below 1970 psig when used in the cold overpressure protection mode.

NRC Resolution: Not accepted. The Question stem and distrac-tor indicates the PZR pressure control system, not the overpressurization subsystem.

(12) Question 3.12.c Facility Comment: Part c - Recommend accepting 4 and 5 as possible answers since the selector switches do not have trip open features.

NRC Resolution: Not accepted. The reference of answer key supports answer given and structure of the question (items in column A) indicates when a controller answer is required vs. a switch or control item.

(13) Question 3.15 Facility Comment: Recommend deleting the question because there is no correct answer. Reference attached.

NRC Resolution: Accepted. Question deleted due to a late change in training material which the candidates were exposed to as a result of a plant audit.

(14) Question 3.18.a Facility Comment: Part a - Recommend accepting either Generator Bus Fault or Generator Bus Differential. The terms are synonymous. Delete "Hi Lube Oil Temp" as a trip.

NRC Resolution: Accepted as follows. Deleted the "Hi lube oil temperature" as a trip. Due to reference provided answer key was modified to " Generator Differential" trip and Bus differential are not synonymous terms, but are protection for different parts of the Llectrical system.

6 (15) Question 3.18.b Facility Comment: Part b " Change Lo Jacket Water Temp." to "Lo Jacket Water Pressure." Also accept for engine trips Hi Lube Oil Temp. References attached.

NRCResolutih Accepted. The answer key has been revised as requested.

(16) Question 4.04 Facility Comment: Recommend deleting question since the responses are not listed in E0P-PATH-1.

NRC Resolution: Not accepted. Items c and d are directly supported by E0P-Path-1 while item b is an indirect method of doing the same as c.

Therefore, a is the correct answer.

C .

(17) Question 4.05.d Facility Coment: Part d - Recommend changing answer from 5 to 4.

NRC Resolution: Accepted. The answer key has been revised as recommended.

(18) Question 4.05.e Facility Coment: Part e - Recommend accepting either 3 or 5.

NRC Resolution: Not accepted. Step 112 referenced in support of the facility comment is a continuation of steps taken at 10% power, step 95 of G0P-005.

(19) Question 4.07 Facility Coment: Recommend accepting that adequate shutdown margin is equivalent to " safe conditions".

The candidates may have also calculated an amount of boron for adequate shutdown margin since the question asked "now much".

Reference attached.

NRC Resolution: Accepted. The answer key has been modified to accept a defining of safe by shutdown margin, etc.

7 (20) Question 4.15 Facility Comment Recommend deleting the question. Part b is incorrect according to A0P-16. The procedure states "If leakage exceeds RCS makeup

! capability, then initiate safety injection.

Reference attached.

NRC Resolution: Not accepted. Per referenced material A0P-16, Step 3.13, states to verify makeup operates to maintain VCT level. Then 3.1.4 says "if leakage exceeds RCS makeup capability".

Step 3.1.4 implies that to exceed makeup capability is to have a decreasing VCT level

. with makeup operating and letdown isolated.

(21) Question 4.23 1

l Facility Comment: Recommend changing answer from a to b.

NRC Resolution: Accepted. The answer key has been revised due to typographical error.

b. SR0 Exam (1) Question 5.19 Facility Comment: Recommend accepting either Part c or d.

Reference attached.

NRC Resolution: Comment accepted.

(2) Question 6.05 Facility Comment: Part b - Recommend changing the answer from REMAIN THE SAME to INCREASE. Reference attached.

NRC Resolution: Comment accepted. Answer key has been modified for part b to " increase".

(3) Question 6.08 Facility Comment: Part a, number 2 - Recommend also accepting false as an answer, since, during normal shutdown the normal start /stop buttons work.

Reference attached, a

NRC Resolution: Question has been deleted.

i

8 (4) Question 6.11 Facility Comment: Part c - Recommend also accepting no (false).

Part d - Recommend changing answer to no.

Reference attached.

NRC Resolution: Part c, not accepted. Facility provided references do not support changing the answer to false and the stated reference clearly supports a "true" answer.

Part d, accepted. The additional reference material furnished supports a "no" answer.

The answer key has been revised.

(5) Question 7.06 Facility Comment: Part b - Recommend accepting " BREAKER RACKED OUT" as being synonomous with "8REAKERS SECURED IN THE OPEN POSITION".

NRC Resolution: Comment accepted. Full credit will be given for the additional correct answer.

(6) Question 8.02 Facility Comment: Recommend accepting selection b or c.

Selection c may be selected since it is so close to being true. To determine that it is false you would have to know the procedure verbatim. Reference attached.

NRC Resolution: Comment accepted since c is a requirement for both cases.

(7) Question 8.04 Facility Comment: Part a - The correct answer is " Plant General Manager". Reference attached.

NRC Resolution: Comment accepted. The answer key has been v changed.

(8) Question 8.06 Facility Comment: Recommend accepting either rod misalignment or rod ejection accident (synonomous). Reference attached.

NRC Resolution: Comment accepted. The answer key has been revised to accept either answer for full credit.

9

4. Exit Meeting At the conclusion of the site visit, the Chief Examiner met with representatives of the plant staff to discuss the results of the examination. Those individuals who clearly passed the oral examination were 4 identified.

l There was no generic weaknesses (greater than 75 percent of candidates j giving incorrect answers to one examination topic) noted during the oral

examination.

4.

There were some apparent procedure problems noted during the oral

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examinations that were identified. They include:

a. The Steam Generator Tube Rupture procedure - It directs the operator to dump steam from a faulted steam generator, possibly to atmosphere.

b. The Heat Balance procedure used for setting the power range nuclear power detectors. The steam generator blowdown input for this procedure directs the operators to subtract steam flow indication from feed flow indication. Since these indicators are read in units of millions pounds mass per hour, it is doubtful that a calculation done in this manner will accurately provide a steam generator blowdown rate for the calorimetric.

c. Graphs used as operator aids for determining various tank volumes and for determining the cold overpressure protection system setpoint were not available. <

l The cooperation given to the examiners and the effort to ensure an atmosphere 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.

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

Y U. S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION rACILITY: _20EAE9U_UABEIS_1________

REACTOR TYPE: _EWR-WEC1________ -

DATE ADMINISTERED:_EiL11Lai_ - _ - - _ _ _

EXAMINER: _ELCEER._R.____- _ --____

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l T [

LNuTRUCILON2_IQ AEELLCAMIL Use separate paper for the answers. Write answers on one side only.

Staple question sheet on top of the answer sheets. Points for each question are indicated in parentheses 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 stx (6) hours after the eramination starts.

% OF CATECORY % or APPLICANT'S CATEGORY

__2ALUE_ _IRIAL ___200EE___ YALME__ ______________CAIECQEX-____________

32_S!L_ _$1_00 .._______ 1 PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, THCRMODYNAMICS, HEAT TRANSFER AND FLUID FLOW

.11.Q2__ 41.Q1 ___.________ ________ 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS

_12.24-_ 45.24 ___________ _______..J INSTRUMCNTS AND CONTROLS

_10 qu___ _10.02 __._._______ ________ 4. PROCEDURES NORMAL. ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL lad.da__ laa.QQ ___________ ________ TOTALS flNAL GRADE _________________%

All work done on th s examination is my own. I have neither qtven nnr received and APPLICANT'S SIGNATURE ,

l 11__ER1NCIELE3_QE_ NUCLEAR _EQWER_ELANT_QEERAILON. PAGE 2 INERMQQ1NAMLC3 _dEAI_IRANSECR_ANQ_EAULQ_ELQW QUESTION 1.01 (1.50)

TRUE or FALSC?

a. One of the pump laws for centrifugal pumps states that the volume flow rate is proporttonal to the speed of the pump. (0.5)

b. As VCT temperature decreases, volume flow rate from the centrifugal charging pump increases. (0.5)

c. Pump runout is the t e r ra used to deseribe the condition of a centrifugal pump running wtth no v o l urr.e flow rate. (O.5)

OUESTION 1.02 (1 00)

The margin to DNB:

a. Increases with decreasing flowrate

b. Decreases wtth decreastnq toactor power

c. Decreases wtth decreasing p r e s s u r i :: e r pressur-d increases with increasing Tavq (1.0)

OUCSTION 1.03 (1 00)

T, u r i r. g a 3 t ( a t: ;eak irsm !he main steam header t. the atmosphere, a thrott1inq process is created. Which pro.:ess t'elow wt i1 occur?

4 Cri t h a ! py or the s t . a ra wi!I d-croase t, . Entropy of the steam will increase.

c .; p e c . f i .- volime of the : team witI d e c r e a s e-

d. Steam temperature will remain the came. ( 1 . 0 'J

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QUESTION 1.04 -(1.00) -

l The reactor has been started up on a new core and has achieved 100%

power with equilibrium Xenon. Boron concentration is at 900 ppm.

i A reactor trip occurs. Assuming ALL rods trip, what is the approxi-mote shutdown margin immediately after the trip?

i f a. 7.0%-

i b. 8.0%

c; 9.0%

d. 10.0% (1.0)

-QUESTION 1.05 -(1.00)

Match each term in column A to its proper definition in column B.

Col.UMN A COLUMN D

a. Ileat flux 1 The process of heat transfer involving movement or circulation of fluid.

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b. DNDR i O. This takes place when heat flux is high c, Nucleate boiling and steam is formed in a relatively flat-ani l a r .J e bubble. !

l d Conduction 3 Th- ratto of the heat flux at a heated custace t ha t - wi l l cause DNB to the actual !

neat : lax present ;

4. The process of heat t r a n .s t e r trom one sub-t a r. : e to another due to tempeiature d6fter-nce

5. Tb s eccurs when small steant bubbles 1: e being formed on a heated surface a: i are taleased into the flow stream.

6. STU/ht per Square toot'of heating surface.

10.25 eachl (1.0)

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-OUCSTION 1.06- (1.00)

TRUE or FALSE 7 l- a. During 100% power operation. Departure from Nucleate Botting Ratio (DNBR) is greater than the DNDR for 00% reactor power

b. As the temperature difference between the fuel rod surface and thE saturation temperatute of the coolant (Twa l l -T s a t ) increases at a constant innear rate. (0-10E4), the heat flux across the fuel surface I -(BTU /hr sq. ft) increases at a constant linear rate.

l l OUESTION 't.07 (1.50)

! TRUE or FALSE?

i 's . When the system characteristic curve is considered with pumps-s n- pa ra lle l curve, the operattnq potnt represents a htgher volumettic flow rate than one pump and a greater system head l o s s'.

, b. In order to increase the volumetric flow rate in a system centrifugal pumps are often used in parallel

c. Volumettsc_ flow rate ftom a positive displacement pump increases in the same proportson as the speed increases i

r t

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1 -__ EE L NC L E L E3_Q E_ N UC L E &E_ EQW EE _ E L & NI _Q E E R&I1Q N . PAGE S IutRMQQ1 NAM 1 Cam _HEAI_IR&HEEER_AHQ_ELu1D_ELQW QUESTION 1.08 (2.00) ,

c. If the reactor ts operating in the power range. how long will at take to raise power from 20% to 40% with a +0.5 DPM Start-up rate?

1. 12 sec.

2. 21 sec.

4 3 36 sec.

4. 54 sec. (1.0) b . _ llow long will it take to raise power from 40% to 60% with the same +0.5 DPM Startup rate?

1 12 sec.

2 21 sec.

3. 36 sec.

4 S4 sec. (1 0)

QUE3 TION 1.09 (1.00)

Which of the following.best describes the eflect o MTC if the RCS temperature is LOWERED?

s It becomes less negattv6 hecause boron and water (no t e c u l e s are swept into the core as a result of the outsurge from the pressurszer, tbarefore, neutrons spend more time in the resonance region.

b It becomes less negative because the r3te of change in the danssty .

ot wat*r per degree temperaturs change is less at lower temperature .

which causes a lesser change in rate in resonance escape probablitty. !

c. It becomes more negative because thermal utlltzation increases r and rer.onance escape probability decreases.

! d. It becomes more negative because as temperature is lowered the moderator becomos.more dense, this increases the amount of water molecules in the core therefore neutrons have a greater ;

[ I j probahnlity of colliding wath a water saolecule and this is an j increased negative reactivity effect l

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-QUESTION 1.10 (4.00)

Using the attached Xenon worth curve. Fig. 1 1. answer the following.

a. Power at TO was at 70%. What was the power level between T1 and T27

1. 90%

2. 50% !

3. 20%

4. 10% (1.0)

b. What was the length of time between T2 and T37 1 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ,

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2. 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months

3. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 4 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months (1.0)

c. What happened at T2?

I Reactor tripped.

2. Rods were placed in AUTO, and turbine power was raised to 100%.

3. Reactor power was reduced to 10%.

4. Turbine power remained constant, rods were in manual and inserted 50 steps and the steam dump valves fatted open (10% of rated power) (1.0) d- At time T4 .

1 All Xenon productton has stopped.

2. todine decay to Xenon has stopped.

1 All Xenon production remann: constant, but the burnout increases.

4. Xenon production directly from fission has stopped, but Xenon production from decay ot t oda ne continues. (1,0) l t

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i _..Eg1NQ1 r ELE 1_QE_NUQLEa&_EQWER_ELANI_QEERAI1QNu PAGE 7 IuERWQQ1NAMICE._UEAI_IRANEECR_ANQ_CLu1Q_ELQW QUESTION 1.11 (1.00)

Delayed neutrons play a major role in the operatton of the core bocause they ...

a. are born at (thermal) slow energy levels (less than I ev) and therefore are more apt to cause a fission as compared to being absorbed by a poison.

b. are considered as eptthermal neutrons and therefore they will not travel far enough to leak out of the core.

c. are born so much later than the prompt neutrons and provide controlabellty during steady state operations and power transients.

d. provide 70% of the ftssion neutron inventory and have higher importance factors associated with them as compared to prompt neutrons.

QUESTION 1.10 (0.00)

If the Gource Range (SR) instruments indicate 50 eps with Keff i

equal to 0.9. what would the SR instrument Indicate if rods were withdrawn to bring Ketf equal to 0.95? Assume DOL condittons.

a. I S0 cps 0 75 eps 3 100 cps 4 000 cps (1.0) l b, ilow much reacttvat'y was added?

I 0.0347 l 0. 0.0500 i

l 1 0.0526

4. 0,05u5 (1.0) l I

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OUESTION 1.13 (1.50)

Conpare the calculated Estimated Crattcal Posatton (ECP) for a startup 15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months after a trip to the Actual-Critical Rod Position

! -(ACP) if the following events / conditions occurred. Constder each independently. Limit your answer to:

a. ACP higher than ECP.

b, ACP lower than ECP.

c. ACP would not be signsficantly different than ECP.

1. One' Reactor Coolant Pump is stopped one minute prior to criticality.

2. The. steam dump pressure setpoint is increased to a value Just below the code saftnes setpoints.

3. The startup is delayed 2 more hours OUE3 TION 1.14 (1.00) I TRUE or FALSE?

a. During a RCG hoatup, at t-mperature qvts higher, at wil! ;

take a smaller letdown 'i.w rate to mnintain a constant ,

pressurtser level ,

f

b. Increasing condensate deptecston (sub:ooling) will cause [

00Til a decrease in plar.t +ttt:nency AND an increase in }

condensate (hotwell) pump available N P Gil .

[

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

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QUCGTION 1.15 (2.00) l

! a. Steam extting the HP turbine is at 785 ps19, 90% qualaty. Steam

- . entering the LP turbine is superheated to 100 F. What is the enthalpy change of the steam? ,

t. 85 BTU /lbm

2. 140 BTU /lbm

3. 156 BTU /lbm 4, 705 DTU/lbm i

i b. During the process in part "a", how much energy is added to the i steam by mechanical motsture seperation in the MGR assuming that the steam quality after separation is 100%.

1 1 7i HTU/ Ibm

2. 85 DTU/lbm s ,

3 140 DTU/lbm 1

4 156 BTU /lbm i

4 i QUC3 TION 1 16 (1.00)

, in order to maintain a 200 f subcoolang margin in the RCG when reducing RCG pressure to 1600 psig, steam generator pressure must ;

be reluced to approximatcly:

a. 045 pstg I

t- 445 psig

.c. 645 psig l

d. 345 psag 1 l

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l QUESTION 1.17 (1.00)

During a reactor startup from an inattal Keff of .90, the first rooctivity addition caused count rate to increase from to cps to 16 cps, The second reacttvity addition caused count rate to increase fron 16 cps to 32 cps. Which of the following statements BEST describes the relationship between the first and second reactivity additions.

a. The first reactivity addition was the larger of the two.

l I b. The second reactivtty addition was the larger of the two.

1

c. The first and second reactivity addittuns were equal

d. There is not enough data given to determine relationship.

QUESTION 1.18 (1.00)

During a Xenon-free reactor startup, critical data was inadvertently taken two decades below the required intermediate Range (IR) level (txE-10 amps).

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

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

a. The erstical rod positton taken at the proper IR level is LESS THAN the erstical 1od posatton taken two decades below the proper IR level.

b. The eritscal rod posttion taken at the proper IR level is THE SAME AS the cittteal rod posation taken two decades below the proper IR leve!

l

c. The eritteal rod position taken at the proper IR level is OREATER TilAN the eritteal rod posation taken two decades below the proper !R level d, There is not enough information given to determine the relattonship between the eritscal rod posttion taken at the proper IR level and the erstical rod position taken two decades below the proper IR level l

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OUESTION 1.19 (2.00)

If steam goes through a throttling process, indtcate whether the following parameters will INCREASE, DECREASE. or REMAIN THE SAME.

a, Enthalpy

b. Pressure

'c. Entropy

d. Temperature OUESTION 1.20 (1.00)

Which parameter below will have the MOST effect on the shape of a Differential Rod Worth curve?

a. Core radial flux proftie.

b. Core axial flux profile.

c. Core axial t empe r a t ta r e profile.

d. Time of core cycle.

OUESTION 1.21 ( .50)

PRUE or FALSE?

The etfeet of tbe bank overlap ps igram on the Differential Rod Worth zurve is to make the s h'a p e of the curve more linear OUECTION 1.22 (1.00)

'TRUE OR FALGE?

L a. The change in Samatsum concentration following.a reactor trsp will 4tman: Sh the shutdown m.stqtn.

b. Samattum is produced as a resuit of the beta decay of Promethtum.

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L. 2___EL,ANI_QE21GN_1NCLERLNG_2AEET1_ANQ_EMERGENC1_S1ETEMS PAGE 12 l

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QUESTION -2.01 (1.00) i.

The flow from the RHRS to the RCS is designed to be:

a. Controlled by heat exchanger outlet valve.

b. Varied as the cooldown or heatup requires.

c. Controlled by the heat exchanger flow bypass.

'd. Constant around 3750 gpm.

QUESTION' 2.02 (1.00)

Which of the tollowing.ts correct for the Component Cooling Water System?

a Complete train separatton is maintained at all times.

I

b. The surge. tank is protected from a vacuum, when tsolated, by a rupture disk,

c. Both essenttal headers receive flow during normal operation with only one CCW pump running

d. The relief valve downstream of the excess letdown heat exchanger relieves at 150 pstg to protect against a tube rupture.

t QUEUTION 2.03 (1.50)

List i functtons of the Stc1m flow Restrtctor built into the Steam Generators.

i

(***** CATECORY 02 CONTINUED ON NEXT PACE *****)

T1;__ E L,ANI_ Q E 21G N _1NC LVQ1NG _ S A E EI1_ A NQ _ EM E RG E NC1_111IEM E PAGE 13

'OUESTION 2.04 (1.00)

When the pressurizer (PZR) is in a solid condition (liquid full). How is the pressurizer pressure, with pressure control on the PRT N2 and Weste gas controllers, equalized to the PRT?

a. Two PORVs are manually opened to the PRT.

b. A Jumper is installed from the PRT vent to the PZR PORV line.

I ic , .' N 2 is ported directly to the PZR through the sample line.

i-

d. PZR is manually equalized by cycling open one PORV as needed.

QUESTION 2.05 (1.00)

What method is used to attach the Rod Drive pressure housing to the Reactor Vessel Head?

a. Welded directly to the head.

b. -Bolted to the head and. tack welded.

c Threaded to the head and seat welded.

I d. Planged to head and seal +d with metalite O-ring seal.

OUESTION 2,06 (2.00) ,

TRIIC or FALSE

a. The Main Turbine turning g -t a : motor-will automattely start any-ttme when the turbane ? pr ed reaches zero and the power supply oreaker is shut -> . ,

b. The basis for the intercapt and reheat stop valves closing on a turbine trtp is to p r e v e r. t turbtne damage due to overspeed.

c, The turbine water detectton system purpose is to detect metal erosion problems befor- tney reach a eritteal condition.

d; The e'x h a u s t hood spray system is used to cool the last stages of the LP turbine during startop or low load condttions.

I

(***** CATEGORY 02 CONTINUED ON NEXT PAGE **ars) 9 s

. _ . .i______ m___

- 1___EL4NI_DE11GN_1NCLUQ1NG_2&EEI1_ANQ_EMERGENC1_11SIEMS PAGE 14 l - QUESTION 2.07 (3.00) l Using Figure 2-1, on the back of the exam as your guide, place the

'onscer to the 15 blanks on your answer sheet. Use the NOTE on the figure as a guide as to the spectfic answers desired.

-QUESTION 2.08 (1.00)

F: .The Emergency Trip System. of the main. turbine, consists of the

_____(name) emergency trip header and the _ _(name)_

controller trip header QUESTIOl! 2.09 (1.00).

The CVCS normal letdown comes from the RCS toop and returns to

the RCS loop .

. QUESTION 2.10 ( .50)

L TRUE.OR'FALSC?

The piping elbow installed in the RCS to create a delta-P for flow measurement has J low pressure taps and 1 htqh pressure tap.

t QUESTION 2.11 (2.00)

Any combination of the following equipment will assure adequate heat removal to keep containment pressure belcw the design pressure during fftil in t h e- blanks plactng answers on your answer page.)

inte: tion phase

______ out of two CSS pumps.

l ______ out of tour Containment Cooling Untts

______ CSS pump (s) and ______ Containment Cooling Unit (s).

1 1

(***** CATEGORY 02 CONTINUCD ON NEXT PAGE *****) ;

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( . . .- . .-.

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~a;__ELAMI_ DESIGN _1NCLUQ1NG_1AEEII_ANQ_EMERGENC1_E1SIEME PAGE 15 t.

. QUESTION 2.12 (2.00) 1 Complete the following statements concerning the Boron Thermal Rogoneratton System (BTRS) by filling in the blanks. Place your answers on your answer page.

The BTRS capacity is limited to approximately a __ _ ppm change at DOL and a ppm change at EOL.

At BOL, a boron concentration dilution of 100 ppm using BTRS takes approximately . _ hour (s) and at EOL, the same dilution takes

_ hour (s).

QUESTION 2.13 ( .S0)

TRUE OR FALSE?

A flow ~ restractor is inserted into the RCS hot leg bypass manifold so that hot leg bypass flow will be equal to cold leg bypass flow.

B QUESTION 2.14 (1.50) for each reactor core bypass ft.wpath. .stato the approximate amount of the bypass flow..(!n percent of total core flow.)

a. Nozzle Bypass Flow.

b. Ilead Cooling Bypas: Ftow.

c Control Rod and Instrument Thimble Bypas: Flow.

-QUESTION 2 IS (1.00; What is the r egis t r ed flowrate that auxtl:ary feedwater must supply to

.the S/C's on a loss of normal feedwater with site power available a 300 gpm.

.c

b. S00 gpm.

1. 800 gpm.

d. 030 gpm.

3

(***** CATECORY 02 CONTINUED ON NEXT PACE *****)

\

k. .____-_______________A_._______.

i 17__EL,ANI_QEElGN_1NCLUQLNG_2AEEII_ANQ_EMERGENC1_SIEIEMS PAGE 16 l

1 QUESTION 2.16 (2.00)

The Condensate Storage Tank minimum water volume of gallons, balow all other suctions from the tank, is suffacient to maintain the plant.In hot standby for ____ hours fo!! owed by a ___ hour cooldown to degrees T.

QUESTION 2.17 (3.00)

Indicate which of the Excore' Nuclear instrumentatton Ranges (SOURCE.

INTERMEDIATE, POWER or NONE), will correctly match with the following statements. More than one may apply to each.

a. Uses an opposing current technique to compensate for gamma radiation,

b. Operates in the Proportional region of the Gas-ftiled Detector curve.

c. Detector operation is unaffected by gamma radiation.

d. Covers etqht fRJ decades of neutron flux.

e. Covers twelve (12) decades of neutron flux.

f Chates a common instrument thimble but only covet 3 the lower core area.

OUEGTION 2.-10 (1.00)

The aux itary r setvctr prc vides the prsmary source of water to the _____(name)__________ system and the ______ (name)____ .___

systen.

QUEGTION 2.19 (1.00) ,

The accumulator injection line design *d such tha+ the e- enters I

the RCC:

a. wtthan one toot of the vessel outlets.

b. at the'RCP suctions to and in injection af the pumps'are running.

c. cold leg downstream of the RCP at a 45 degree angle.

d. cold leg.below the piping midplane upstream of the RCPs.

(***** CATECORY 02 CONTINUED ON NEXT PACE *****)

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

l __ELAUI_DC21CH_1 e HCL'ltlHC_212;II_1U2_CM22CCECI_21220L'1 FtCE !?

. QUESTION 2.20 (1 00)

Which condition below would meet the safety injection design criteria, assuming all other conditions are normal?

a. RHR pump #1 fails to start and #2 RHR pump mechanical seat fails,

b. One of Accumulator #2's discharge check valve fails to open.

c. Charging pump #2 trips and RHR pump #2 seals fait

d. 'Two charging pumps fail, one due to a' breaker, other due to bearings.

QUESTION 2.21 (1.00)

Regarding the Chemical and Volume Control System, af an unsaturated bed of H-OH resin is placed in service, what will be the results?

a. Oxygen in the primary will increace.

b. No non exchange will occur for the first 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

c Posstave reactivity wt!! be adled to the reactor.

d. Doron wt!! be released.

OU CST I Oil Z.22 (l.00)

Which of the following is NOT correct for the Essenttal Service Challed Water System (CSCWS)?

a The wat+r ts cooled by R 12 compressors powered from 1A24 and 1824 b- Automatic flow control ts governed by pressure in the R-!Z side and is efependent on Service Wat+: temperature.

e. Makeup to ESCWS train A and train B is ftom the fire Protection via-tne systems expansion tank An **

d. Sesvice to the closed expanston tank is isolated on an SI signal.

(***** END OF CATECORY 02 *****)

1,__1N,SIREMEMI1_AMQ_CQRIRQL1 PAGE 18 QUESTION 3.01 (2.50)

Indicate which of the Excore Nuclear Instrumentation Ranges (SOURCE.

INTERMEDIATE.-POWER or NONE), will correctly match with the following statements. More than'one may apply to each.

a. Provides a direct input to the Rod Control System.

b. Has a reactor 1 trip function t'at a is blocked at some time between startup and full power operation.

c. Detector output current is adjusted by a front panel potentometer.

d. Utiltzes a Boron-10 coattng in it's detectors.

e. Operates in the "lon Chamber" regton of the " Gas Tilled Detector Characternstic Curve" (0,5)

OUESTION 3.00 (1.00)

Which of the.following 13 correct for the Component Cooling Water System-(CCWS) following an ac:tdent condttlun?

a. The Reactor Coolant Drain rank and Excess Letdown !!e a t Exchanger flow Is matntained during a Si

b. If one pump fatts to stast , the C pump will automattelly start and s ta p p l y those loads

c. The two CCWS pumps' and ir. mary sample isolatton valves 547 end 548

eceive SI stonals.

d. Upon receipt of a SI sig: al the operating CCWS pumps are trapped and th+n restatted QUESTION 3.03 (2.00)

1. t s t 4 r egtt i r eme n t s need+d t- r opening the orifice isotation valves to the CVCS.

l

)

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(***** CATECORY 03 CONTINUED ON NEXT PAGE *****)

lh__lMSIE!1MEMI1_&MQ CQtlIROld PAGE -20 OUESTION 3.07 (1.00)

Whtch condition below'is correct concerning Rod insertson Limits?

a. The delta T constant K2 in the RIL calculation is set to zero at our p l a n t'.

b. ~ The fulI power rod insertion Iamtt is controf bank D at 99 steps.

c. The rod insertton I t ro t t computer uses auct. high NI power to calculate-the power-dependent RlL.

d. TheEzero power rod' insertion limit is control bank C at 64 steps.

-QUESTION 3.08 (1.00)

Which of the following indications are used in the Steam Generator Water Level Control System. More than one indication may be correct.

a. Auct. high r. u c l e a r power

b. Steam flow rate

c. Feed header pressure

d. . Wide range SG .evel e F*ed flow rate A

f. - Turbane.impule.pressuse

/I

(***** CATEGORY 03 CONTINUED ON NEXT PAGE *****)

m_.- _ _ _ . _ _ _ _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ . _ . _ _ _ _ _ _ _

1;__1MEIRTJENI1_ANQ_CQEIRQLa PAGE 18 OUESTION 3.01 C2.50)

Indicate which of the Excore Nuclear Instrumentation Ranges (SOURCE. _

INTERMEDIATE. POWER or NONE), wt1i correct-ly ' match wtth the foflowing statements. More than one may apply to each.

a. Provides a direct anput to the Rod-Control System.

b. Has a reactor trap function that is blocked at some time between startup and full power operation.

c. Detector output current as adjusted by a front panel potentometer.

w

d. Utilizes a Boron-10 coating in it's detectors.

e. Operates'an the "lon Chamber" regton of the " Gas I' l l i e d Detector Characteristte Curve" (0,5)

OUESTION 3.00 (1.00)

Whtch of the following i2 correct tot the Component Cooling Water System (CCWS) following an ac:Ident condition?

a, the Reactor Coolant Dra;n rank and Execss Letdown llea t Exchanger flow '

is maintained during a- C i *

-b. If one pump fasts to staa'. the C pump will automattelly start and supply those loads

c. The two CCWS pumps and ; r .. ma r y sample isolation valves 547 and 548 receive 31 stqnals.

d. .Upon reeeipt of a SI : i g t.a 1 the operating CCWS pumps are tripped and Ih+n Ieitatt.d QUESTION -3.03 (0.00)

' t. n s t I requiraments need*d t r epenino the orifice isolation valves to the CVCS.

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(***** CATEGORY 03 CONTINUED ON NEXT PAGE *****)

1.,_1EEIRUMERI2_ANQ_CQMIRQL2 PAGE 19 OUESTION 3.04 (2.00)

TRUE or FALSE

s. When resetting ESF actuations, all valves and components must be manually realtoned including the containment spray system.

.b. lii gh containment pressure is actuated by 2.of 3 channels reaching the setpoint.

c. Feedwater isolation occurs automatically af Tave drops to 566 degrees F.

d. When an Auxiliary feedwater isolation occurs the flow control and motor operated valves from the motor and turbine aux. feedwater pumps are shut.

QUESTION 3.05 (1.00) ,

Which of the following rod control componants supplies speeds and

-direction to the logic cabinent?

a Rate comparator

b. Summer.

e Vartable gain unit

d. Reactor control unat.

OUCGTION 3.06 (1 00)

-Mann Steam 1.t o l a t l a n wo tt i d occur during wht b c o rn.i t in (l e s e r a b e d below?

a Gudden drop in steaminne pressure from 300 pssa to o80 psla from a steam leak at 75% power

b. Reactor operator inadvertantly depresses one ma n tia l M'i l pis s hbu t t o n .

while explaining the system operatton to a student

c. til 11 containment pressure signals on channel A due to tailure of an instrument Tech. to place channel A in test prtot to testing. ;

d. Low steam pressure actuatton on 2/3 channels during normal plant cooldown to place R ilR on- I n ne .

(***** CATCCORY 03 CONTINUCD ON NEXT PAOC *****)

17__iMEIREMENI2_auQ_CQUIROLE PAGE 20

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OUESTION 3.07 (1.00) '

Which. condition below is correct concerning Rod Insertion Limits?

a. The delta-T constant K2 in the RIL calculation is set to zero at our plant

b. .The-full power rod insertion limat is control bank D at 99 steps.

c. The rod insertnon limst c o m p it t e r uses auct, high Ni power to calculate the power-dependent RIL.

d. The zero power rod insertion limit is control bank C at 64 steps.

QUESTION 3.08 (1.00)

. Which of the following indications are used in the Steam Generator Water Level Control System. More than one indication may be correct.

I

a. Auct high nuclear power

b. Steam flow rate

'c, Feed header pressure

~

d. Wide range SG level e t'e e d flow rate A

f. Turbine impute pressure '

A i

i I

l.

(***** CATECORY 03 CONTINUED ON NEXT PAGE *****)

1 3__1NgIREMCMI1_ANQ_CQMIRQL1 PAGE 21 QUESTION 3.09 (1.00)

The OP delta T.setpoint is a calculated value determined by which of the following methods?

a, 109% full power delta T minus correction proporttonal to rate of increase of Tavg, minus correction proportional to variation of delta T above full load value,

b. 109% full power delta T minus correction proportional to rate of increase of Thot, minus correction proporttonal to varation of Thot above full load Thot

.c. 109% full power delta T manus correctton proportional to rate of increase of Tavg. minus correction proportional to varatton of Tavg above full load Tavg.

d. 109% full power delta T. minus correction proportional to rate of increase of delta T. minus correction proporttonal to variation of delta T above full load.

QUESTION 3.10 (1.00)

Which of the below is a cortect statem(nt about tha Pressurtser Pressure Control System?

Ra,:kup heatars and spray valves are controlled from PT-455 and PT-456.

b. The " Master Controller" controls the PZR heaters. PZR spray valves,-

n n .1 PORV-44SB,

c. PZR PORV block valves are air operated and fait closed on loss of air.

d PZR PORVs will not open when pressure is below 1970 psig, except when operated from MCD or ACP.

QUESTION 3.11 (1.00)

The goal of the Pressurtzer Level Control Gystem is to maintain a nearly

________ ____ (3 words) thus minimisinq charging and letdown along with

. minimising _______________________

(***** CATECORY 03 CONTINUED ON NEXT PAGE *****)

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-1___1M,1IEuMEMI1_AMQ COMIRQLE PAGE 22

(

OUESTION 3.12 (3.00) h Match the proper Steam Dump Control (s) or Controller (s) in Column B j to each statement in Column A. More than one in Column B may apply.

(i.e.- a. 6.8,10: b. 3,7 )

COLUMN A COLUMN B

c. Operates Steam Dumps based on a 1 Turbine trip controller

{ temperature deviation (Tavg-Tref)

2. Steam pressure controller

b. Used to reset the C-7 arming signal

3. Load rejection controller.

c. Contains no trap open features.

4. Steam Dump Control Mode

d. Uses auctioneered high Tavg. Selector,

e. Compares the actual parameter to 5. Steam Dump Interlock that of a pre-set value for operation. Selector, f, Used to allow cooldown valves to open l 'below P-12 l

g. Used to turn the system off

'h. U s e s . q ta l c k open bastables for rapid transients.

I OUESTION 3.13 (1.00) l l Trouble in DOTH trains of Reactor Protectton Gystem would cause which of the following?

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4. Mill t s pl ex i ng of signals to $ top.

l b. Urgent laiture alarm.

c Reactor trip to occur.

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d. Input error inhibit alarm.

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1,__14EIREMENI1_ANQ_CQRIRQL1 PAGE 23 l

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i OUESTION 3.14 (1.00) ,

Which of the following conditions / Interlocks must be sattsited, in order to allow for manual reset of a SIS?

a. 20 seconds have elapsed since Si actuation.

l l b. Reactor Trip breakers are open.

l

.c. PZR pressure above P-ll ,

d. Si signal ts cleared.

-QU TION 3,15 (1.00)

When c loads shed by an UV or a GI signal be restarted?

a, When the a nals are manually reset.

b. When sequencer gt e4 ermtsstve signal.

j c. At anytime provided the power source is not overloaded.

c. After the problem caustnq the UV'cr GI clears N N, i l

OUEGTION 3.16 (1.00) l L If tha containment Gpray Ac'uition Gignal (CGAS) occurs within isve seconds of LOCA sequencer initiation the sequencer l

a, starts the contsinment srray pumps at the auto load block at 5 seconds.

b. stops loading sequence and starts the containment spray pumps then continues the load cycle c, continues the loading s e q u e ric e and loads the containment pumps at the next auto load bloci at 15 seconds.

d. interupts the load cycle at 10 seconds, loads the spray pumps and then restarts.the lond cycle

(***as CATECORY 03 CONTINUED ON NEXT PAGE *****)

1

1;__1M,21&MEMIS.&MQ_CQMIRQL1 PACE 24 QUESTION 3.17 (1.00)

At what pressure will the Ri!R valves 8700A and 8701A close automatically? .

c. 350 psig b ,. 425 pstg !

c. 500 psig

d. 700 psag i i

OUESTION 3.18 (3.00)

a. List all trips on the Diesel Engine which remain active during during an emergency start (St or UV). (1.0)

b. List 8 additional Diesel Engine trtps. (2.0) l OUC3 TION 3.19 ( .50) i TRUC or FAL3C Pre-actton sprinkler systems are systems that actuate to dampen the fire prior to it growing beyond the inttal state, thus limiting damage

l. from the itre.

l L

l l CUC3 TION 3.20 (1.00) l The lla l o n l' s r

suppress 6on system t c, activat*d to discharge by I

! a. Flame detectors.

b lonisation detectors "

c. Thermal detectors I d. Air duct detectors i

(***** CATECORY 03 CONTIN 2CD ON NEXT PACC *****)

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1;-_15,SIguMEEI2_ANQ_CQMIRQL1 PAGE 25 QUESTION 3.21 (1.00)

Which of the following used by the Auxiliary feedwater Turbine Governor to sense turbine speed?

a. Ghaft oil pump pressure.

b. Magnetic pickup coni.

c. Centrifugal Flywieghts.

d. Governor oil pump system.

OUCSTION 3.22 (1.00)

The Boron Recycle System normally receives water from the ___ ___

__.._____ _______ ________ (4 wordsJ. ________ __________ _______ _______

(4 words) and _______ _______ _______ (3 words) The system stores the unter for processing in the BRS ________ ________ ________ (3 words)

OUEGTION .3.23 (1.00)

Which of the following is NOT a reasor. for the G/G level program?

a. Minimize cooldown of RCG following a steam break.

b. Maintain constant mass in G/O at all power levels to facilitate chemistry control

c. Minimize containment pressure following a steam break.

d. Minimigo inadvertent low low G/O level reactor trips following a load reduction-(***** CND Or CATECORY 03 *****)

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i.__EEQCEDURE3_

_MQEWAL._ ARM 2&M&L._EMERCCMC1_AMQ PAGE 26 l RAQLQLQG LCAL _CQMIEQL ,

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l QUESTION 4.01 (1.00) i Which of the following is NOT a requirement prior to withdrawing control f rods for a " Recovery from a Reactor Trip (GP-004)?

l o. The cause of the trip has been identified and corrected. !

l l b. Permission is obtained from the Operating Supervisor. .

! I L c. An estimated eritscal posttion has been calculated.

i <

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d. Three RCP's, two condensate pumps, and one main feed pump are operable and in operation. ,

i l QUESTION 4.02 (1.00) l Procedure EOP-EPP-001. Loss of AC Power to tA-SA and ID-SB Busses, j l cautions the operator not to depressurtre the S/O's below 165 pstg. i Why as the limst imposed? j I l

a. To prevent nitrogen from being injected into the primary. '

d f

b. TO prevent voiding in the vessel head region. .

c. To ensure the nuclear instruments continue to lead properly.

J To *nsure the S/O's continue as retsable heat sinks.

t OUESTION 4.03 (1.00) -

The Control Room Ia declared inaccessable and an evacuation is declared.

The teactot is trapped from the main control board a rid an operator !

-6tstianed at the Aux:liary Control Panct What procedure is to be used? ,

a Evr Path I. entry at " reactor trip or 31 block"

. b. E0P Path 1. entry point A.

c. AOP-004. Control Room inaccessabtitty, and the EOP Network {

procedures'as they apply

d. AOP 004. Control Room Inaccessability.

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l fa**** CATECORY 04 CONTINUED ON NEXT PAGE *****)

l l 1.__ERQCEDURES : NQRMAL._&BNQRWAL._CMERQENCI_&MQ PAGE 27 R&QLQLQGLCAL_CQNIRQL l

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l OUESTION 4.04 (1.00) l Pollowing a reactor trip, the turbine did not automatically trip and tho manual control room trtp was unsuccessful. According to EOP-PATH-1 "Roactor Trsp/ Safety . Injectlon". which of the following statements j is the LEAST acceptable method of securing the turbine, i

l c. Close main steam trip valves.

b. Stop EHC pumps. ;

l

c. Manually runback turbine. !

d. Locally trtp turbine.

1

! OUESTION 4.05 (3.00) l Match the evolutnons in Column A to the power. at which they are normslly performed during a power increase, in Column.B. More than one power level may apply, i COLUMN A COLUMN B

~

j a. Perform heat balance 1. 0%

2, 3%

b. Verify proper G/O chemistry 3. 10%

l 4. 15%

c. Start second main teed pump 5. 35%

6. 50% .

l d. Place steam dumps in "Tavg" 7. 60%

8. 70%

0. Place reneat system in operation 9. 90% i t

r I

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h 1,__ERpCCQURC2_.:._MQEMAL _&ENQEM&L._CMCRQCNCY. &NQ PAGE 28 R&QLQLQQlCAL_CQNIEQL QUESTION 4.06 (1.00)

An excessive turbine eccentricity /vibratton alarm ts received while oporating the main turbine on the grtd. The turbine is tripped and stoam is cutoff. Upon engagement of the turning gear, eccentricity roads .003 in. What action is to be taken per AOP-006. Turbine Vibration?

'c. Continue operatton on the turning gear and continue with procedure.

b. Stop the turning gear operation and proceed with follow-up Actions,

c. Inform the Supervison-Operations and continue investigation.

d. Continue operations on the turning gear and advise the Manager-Operations of the reading.

QUESTION 4.07 (1.00) l If two or mora control rods are not fully inserted following a i reactor trip, how much boration is required.

OUCSTION -4.08 (1.00)

Which of the following is the Nrrect actson if. following a reactor trsp. only one AC emergency bus is energtsed?

a Try to restore power to de anergtzed AC emargency bus j wbsie continuing COP PATil : " Reactor Trip / Safety injection"

(

b. Go to COP-CPP-001, L o s s et Ati AC Power to IA-SA and IA-SB" l

j c Rastore power to de energized AC emargency bus beforv continuing COP - P ATil- 1 l

d. Go to COP-UPP-002. "Losa vi All AC Power Recovery without St Required" I

t I

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i ,__ERQCEQUEE1___NQRMAL _ABMQEMAL _CMERQEMQ1_AUQ PAGE 29 RAQ10LQQ1 CAL _OQUIROL QUC3 TION 4.09 (1.00)

During a natural circulatton cooldown following a reactor trtp, Chich of the following criteria determine the amount of RCS subcooling r e q it t r e d ?

o. RCS cooldown rate.

b. Reactor power hastery (decay heat rate)

c. Pressurtser level

d. Number of CRDM fans runntng.

QUESTION 4.10 (1.00)

An inadvertant reactor trtp has occurred. During performance of procedure COP-CPP-004. Reactor Trip Response, a safety inlection occurs Whera ate you to prceeod?

a. Path 2, entry point J.

L Path 1, entry point C.

c. COP CPP 004, stop i

d. Path 1. entry point A OUCSTION 4.11 (1.00)

Which o t' the fallowing statements concerning the :3 ") Tube Rupture, per COP PATil 2. is eosteet?

a Cooldown may be commenced prtor to isolating the ruptured G/0.

b. Cooldown rate is limited to 100 degrees / hour

c. Using one pst PORV is a method of depressuri:ation-I d. The RC3 should be borated to the cold shutdown require-menta prior to commencing cooldown.

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i.__EEQCEQUEE2_ _MQEMAL._&aMQEMAL._ CMC &QCMC1_AMQ PAGE 30 RiQ1QLQQ1 CAL _CQEIRQL l

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OUESTION 4.12 (1.00) l Which of the following statements concerning the procedure for a

dropped RCCA (AOP-001) is correct?

l

o. Upon starting recovery of the dropped RCCA, an UROENT FAILURE alarm will occur because the 11ft cotts for the other rods in the group have been disconnected.

b. The detta flux target band is not applicable during a dropped RCCA malfunction and recovery. ,

l c. If two or more RCCA's have dropped, manually trip the reactor and proceed in accordance with EOP - P ATil- l . ;

d. Recovery from a dropped RCCA will be factittated if Tavg la higher than Trei prnor to commenetnq wnthdrawal of the dropped RCCA.

-QUESTION 4.13 (1.00) l Which of the following statements concerning a loss of one RCP at less than 40% power is correct? :

l

a. Atter meeting the precautions and limitations associated with starting a RCP, testart the affected RCP.

b. Defeat affected loops detta T and Tavg signals and commence unat shutdown,

c. Immediately trtp the reactor and proceed in accordance wttn PATil-l. " Reactor Trsp/Galety Infection" ,

d. Power operattons may continue for up tu faus houts while attempting repair and restart of the aflected RCP.

i i

l i

l

(***** CATEGORY 04 CONTINUED ON NEXT PAGE *****)

l 1 i

i 1,__ELQCEQUEE2_ _NCEMAL._AREQEMAL&_EMEEGENC1_ANQ PAGE 31 i l EAQLQLQQlCAL CQNIEQL ,

l l

t '

I i

l QUESTION 4.14 (1.00) l Whon control is shifted to the Auxtlary Control Panel, what automatte l functions are removed?

I a. All functions associated wtth P-7.

b. All functions of P-10 and P-6.

c. All automatic $1 actuation signals.

l d. All automatic Si actuation signals and functions of P-7.

QUESTION 4.15 (1.00) i When using AOP-16. Excessive Primary Plant Leakage, when should safety injection be inattated?

a If leakage exceeds the capacity of one charging pump.

I h. If VCT level cannot be maintained with letdown isolated.

I

c. If pressurtser level cannot be mainthined greator than 15%.

I

d. If the leakage equals RCG makeup capabillty.

OUESTION 4 16 (1.00)

In a 11tesaving situation, what is the emergency exposure limit?

a, 25 rems wholebody, 100 rams to hands and forearms.

b. 100 r*ms wholebody. 200 rems to hands and forearms,

c. 75 rems wholebody, 200 rems hands and forearms.

d. 75 rams wholebody, 100 r en s hands and forearms.

(****a CATE00RY 04 CONTINUED ON NEXT PAGE *****) [

i

i___EROCCQURCE_:_NQEMAL._AENQEMALu CMCEQCNCE_ANQ - PACE 32 R&b LQLQQLC&L_CQNIRQL OUCSTION 4.17 (1.00)

Which of the following statements concerning the immediate actions for a complete loss of component cooling water is correct?

c. Stop charging flow by closing ICS-231 and letdown flow by closing ICS-7, 8. and 9.

b. The RCP's are trtpped two minutes after eIther the upper or lower motor bearing temperature reaches 190 degrees,

c. Line up NSW to the standby CSW header and verify adequate cooling flow to the CCW lleat Exchanger

d. Secure the boron recovery system.

OUCSTION . 18 (4.00)

A n s wer t ach of the following according to the precautions in procedure GP 02. Normal Plant lleatup from Cold Solid to llot Suberatical,

a. Reactivity can be added to a subcrstical reactit by more than one method at a ttme providing that oca ct the methods is from _____.____________. (two words)

b. llentup and cooldown sates for the RCS shall not exceed ______F/hr

c. The maximum spray water to pressuriter temperature differential shall be _______f.

d. The shutdown marytn shall be greater than or e q tia l to ________ pen tot 3 loop operation e Mad *ratur Tampirature Coefficient (MTC) shall ba maintained less acqative than ________ pem/f.

i ro allow the shutdown banks to be left inserted while the reactor is suhcritscal with posit 6ve reacttvity being inserted requires the approval of the ______________________. ttwo words) 4 With the RC3 temperature les: than 70 T, S/O pressure must be determtncd to be ' ass than 200 pstg at least once every ______.

h. When the RilR loops are in servtee, the reactor coolant pressure must not exceed _______ pstg as determined by PI 403.

l l

(***** CATCCORY 04 CONTINUCD ON NEXT PAGC *****)

i___ERQCEDURE1_

NQEM&Lu_&aNQEM&L _EMERGENC1_&MQ PAOC 33 RAQLQLQQlCAL_CONIRQL QUESTION 4.19 (1.00)

Whon frisking out of a contaminated area, what constitutes skin or clothing contamination using an Eberline RM-14 and what is the maximum bockground that may be present at the final extt point?

a. 100 cpm > background with a maximum 100 cpm final exit background.

b. 75 cpm > background with a maximum 200 cpm final exit background,

c. 100 cpm > background with a maximum 200 cpm final exit background,

d. 200 cpm > background with a maximum 100 cpm final exit background.

OUCGTION 4.20 (1.00)

According to 10 CPR 00.100b. before permitting any individual in a restricted area to reconve exposure in excess of the limits of 10 CPR 20.10ta (l.05 rem /qtt 1, what must be done?

a. relo only form NRC 4

b. File form NRC 4 and :alculate the additional t o s er allowed.

c. File form NRC 4 and dint t .s v an approved General Employee Training course on r a d i a t t o r. axp..uta

d. File form NRC-4 and f o r n. N h c 3 9 6 i

(***** CATCOORY 04 CONTINUCD ON NEXT PAGC *****)

1 1

l l

L i.__EEQCEQUEE1_;_EQtMAL._A&MQEMAL._tMEEGENCI_ANR PACE 34 R&DLQLQGLCAL_CQHIRQL l

l l

QUESTION 4.21 (1.00) e Which of the following defines a RESTRICTED AREA per 10 CFR 207 l

j

a. The area surrounding the reactor in which the licensee has the authority to determine all activities including the removal of personnel or property from the area,

b. An area where an individual located at any point on it's boundary

, for two hotar s following a postulated accident will not receive in

! excess of 25 rems whole body or 300 fems to the thyrond.

1

c. An area in which access is controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive matettals. ,

d. An area where an individual located at any point on it's boundary following a postulated accident will not recetve in excess of 25 rems whole body or 300 rems to the thytold.

OUCGTION 4.22 (1.00)

According to 10 CTR 20. what ts the maximum dose any individual may receive with form NRC-4 on file?

a. I t/4 rems / quarter not to exceed 5(n-18).

b. 3 rems / quarter not to exceed 5(n-10)

c. 5 soms/ quarter not to exceed 5(n-18),

d. 5(n 10)

OUCGTION 4.23 (1.00)

If actual erstical rod position is >250 pcm below the Csttmated Critical Position. OP-004 states that you shalt

a. rihis t down the reactor, evaluate conditnons, recalculate CCC,

b. Continue with startup. do not recalculate CCC.

c. Shutdown the reactor, recalculate CCC, d, Trip the reactor, evaluate conditions, recalculate CCC.

(***** CATECORY 04 CONTINUED ON NEXT PACE nessa)

i.c_ERQCCQURE1_ _NQLWAL._&RNQLKAL CWERGEMC1_&MQ PAGE 35 R&QLQLQGLC&L_CQMIRQL

(

QUESTION 4.24 (1.00)

I i What are THREE indications used to monitor plant cooldown during Natural Circulation according to COP-EPP-0077

c. RCS Thot. Tavg and Core exit TC's.

b. Reactor Vessel Level. Core exit TC's, Subcooling.

c. RCS Teold, Reactor Vessel Level. Subcooling.

d. Subcooling. Core exit TC's, RCS Thot, QUESTION 4.25 (1.00)

After initiation of EO P - P ATit - 1 due to a LOCA, at what decreasing pressure must the Reactor Coolant Pumps be stopped if adverse containment l conditions exist?

f

o. 1360 pang

b. 1450 pstg

c. 1550 psig d, 1600 psig l

(assan CND OF CATEGORY 04 *****)

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l CURVE B-3 POWER DEFECT vs BORON CONCENTRATION g

A 1900 1800-REV:O 31 OCT 78 APPROVED : i 1700 1600

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l

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EQUATION SHEET f = ma v = s/t Cycle efficiency = (Net work cut)/(Energy in) 2 w = mg s = V3 : + 1/2 ac 2 -

E = mc A = IN A=Ae" g

.<E = 1/2 mv a = (Vf - V3 )/t PE = mgn Vf=V + at * = e/t 1= In2/t372 = 0.693/tl/2 y,y p nD 2 t

1/2 8 "

M A= 4 [(ty/2) + (tb}3 c.E = 931 sn -Ex

, m=V avAo ,

Q = mCpat 6 = UA A T I=Iec Pwr = Wfah I = I, 10~*/IYL TVt. = 1.3/u sur(t) HVL = -0.593/u P = P*10t P = Poe / *'

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

CR x = 5/(1 - K,ffx)

SUR = 25a/t* + (a - o)T CR3 (1 - K,ff3) = CR2 (I ~ "eff2)

T = ( t*/o ) + ((a - o V Io] M = 1/(1 - K,ff) = CR)/G 3 T = 1/(o - a) M = (1 - K,ffg)/(1 - K,7f 3)

T = (a - o)/(Io) SCM = ( - K ,ff)/K,ff a = (K,ff-1)/K,ff = M,ff/K,ff t' = 10 seconds I = 0.1 seconds ~I o = ((t*/(T K,ff)] + [a,ff /(1 + IT)]

=Id I jd) 2 ,2 gd 2 P = (t4V)/(3 x 1010) I 3d; 22 2 t=N R/hr = (0.5 CE)/d (meters)

R/hr = 6 CE/d2 (f,,g) .

Water Partneters Miscellaneous Conversions 1 gal. = 8.345 lem. 1 curie = 3.7 x 1010dps 1 ga 1 kg = 2.21 lem 1f.].=3.78

= 7.48 gal. liters 1 no = 2.54 x 10 3 Stu/hr Density = 62.4 lbrg/ft3 1 m = 3.41 x 100 5tu/hr Density = 1 gm/cd lin = 2.54 cm Heat of vaporization = 970 Stu/lem *F = 9/5'C + 32 Heat of fusion = 144 Stu/lem 'C = 5/9 (*F-32) 1 Atm = 14.7 psi = 29.9 in. Hg. 1 BTU = 778 ft-lbf I ft. H O 2

= 0.4335 lbf/in. . .

L

1 _._ER1HC1ELES_QE_ NUCLEAR _EQWER_ELANI_QEERAI1QNm PAGE 36 j

IudRMQQ1NAMICE._HEAI_IRANGEER_ANQ_ELu1R_ELQti ANSWERS -- SHEARON HARRIS 1 -85/11/04-PICKER, B.

MSIERCOPY ANSWER 1.01 (1.50)

c. True

b. Faise

c. False (0.5 each) (1.5).

REFERENCE IP-3 Thermodynamics. Chapter 6, Pages 27 and 29 SHNP TF-LP-1.1, p. 22.

ANSWER 1.02 (1.00) answer: c. (1.0)

' REFERENCE V. C. Summer Heat Transfer. Thermodynamics and fluid flow, pp 226, 243 SIINP !!T- L P - 1. 2. pp 10-16 ANSWER 1.03 (1.00) answer b. (1.0)

REFERENCE V. C Summer flT T F pp 94-96 Steam Tables ANSWER 1.04 C1.00)

(1.0) answer-

\d RETERENCE VCS Curve Book. !!-9. II 12 GHNP Curve Book, curves A-D. A- 1. B-2 i

1 __EEfMC1

ELE 1_QE_ NUCLE &&_EQWER_ELANI_QEER&I1QNm PACE 37

, IUERMQQINAMLC3 _HE&I_IRANSEER_&SQ_ELULQ_ELOW '

ANSWERS -- SHEARON IfARRIS 1 -85/11/04-PICKER, B.

ANSWER 1.05 (1.00)

c. 6 4

b. 3

c. S

d. 4 [0.25 eachl ~(1.0)

REFERENCE

, S VCS HTrr pp 99. 105, 123, 124, 228.

SHNP HT-LP-1.0, pp'4-20 ANSWER 1.06 (1.00) a; false b.'ralse (0.5 ea.1 REFERENCE-Westinghouse Thermal Science. Chapter 13. Pp. 17 - c 3 . KA002/000,KS.01,3.1, GilN P . lit - L P - 1. L . Pp 10-11 and IIT TP- S 6 .

AN St!ER 1.07 (1.50) a: TRUC

b. TRUE

c. TRUC (0.5 each)

REFERENCE Westanghouse Thermal Science. Chapter 10 Pp. 41 49 SilN P . F T- L P - 1.1, p. 26 ANGY1ER 1.08 (2.00)

a. 3

.b. 2 (1.0 ca.1 ;

e

=. ._- . _ _ _

PAGE 38 1 3__ERANCLELEE_QE_NECLEAR_EQWER_ELANI_QEERAIl0N.

, IHERMQQ1NAMLCE._uEAI_IRANSECR_ANQ_ELULQ_ELQW

.. ANSWERS --

SHEARON HARRIS 1 - 8 5 /_11/ 0 4 - P I CK ER , B.

REFERENCE

' Cook Theory, Pp. 13.15-16. KA001/010,KS.37,3.2.

SHNP, RT-HO-1.6, Pp 10-12.

ANSWER 1.09 (1.00) b.

REFERENCE SONP, 6 Factor formula lesson, pp. 3 - S KA061/000,KS.26.3.3.

Cook Theory, Pp 1-5.2-15.

SHNP, RT IIO-1 10 Pp. S-6.

ANSWER 1.10' 'C4.00)

a. 1

b. 3

c. 3-

d. 4 [1.0 each]

REFERENCE SONP, Review of core poisons lesson, p. 6 KA004/000,KS.20,3.6.

. Cook Theory Pp. I S.S7-77.

SilN P , RT !!O 1.11 ANSWER 1.11 (1.00) c.

RETERENCE SONP, Review of Neutron Kinettes, p. S KA001/000,KS.49,2.9.

Cook Theory, Pp. 1-3.3-10.

SHNP, RT -if 0 - 1. 6 Pp. 18 23.

1 v_ER4NC1ELES_QE_ NUCLEAR _EQWER_ELAMI_QEER&I1QM& PAGE 39

. INERMQQ1NAMLCS._EEAI_IRANSECR_ANQ_EkulR_ELQW

-ANSWERS -- SHEARON HARRIS 1 -85/11/04-PICKER, B.

ANSWER 1.12 (2.00) a 3

b. 4 (1.0 each)

REFERENCE SQNP. Suberatical Multipiteation lesson, p. 5: Review of Kinetics, p. 3 Cook Theory, Pp. 1-4.13-15. KA001/000.KS.49,2.9.

SHNP, RT-HO-1.6.

ANSWER 1.13 (1.50)

1. c (same)

2. a (ACP higher)

3. b (ACP lower) (0.5 ea.]

REFERENCE SONP, Review of Core Poisons, pp. 4 - 7 KA001/000,KS.18,4.2.

Cook Theory, Pp. 1-36-45.

SilNP , RT-HO-1 14.

ANSWER 1 14 (1.00) a F A L.S E

b. TRUE (0.5 ea.)

REFERENCE (SONP) General Phystes, HT&TF, pp. ISS and 320 and KAOS6/000,KS.02,1.5 Subcooled Liquid Density Tables KS.0S.I.7 (Cook) Westinghouse Thermal Science, Chapter 10, Pp 9-24 KA004/020,KS.06.2.4 Chapter 00, Pp 21-23.

Sl!NP , The rmo -LP- 1. 5, p.12 (example excercise)

F F - 1. P - 1 1, Pp.6-12, i

PAGE 40 1 r_EE{NCLELES_QE_NECLEAE_EQWER_ELAMI_QEEE&ILQN.

. IHERMQQINEWLCE _EEAI_IRANSEER_ANQ_ELula_ELQW ANSWERS -- SHEARON HARRIS 1 '85/11/04-PICKER, B.

ANSWER 1.15 (2.00) a,>l'3

b. p# l (1.0 each)

RETERENCE SONP, llTT T text, pp. 23 - 24 Cook, Westinghouse Thermal Science, Chapter 7. Pp 32-46.

SHNP, Thermo-LP-1.4, Pp. 38-43.

ANSWER 1.16 (1.00) a.

REFERENCE Shearon llarris-Thermo-LP-1 1 and steam tables KA002/000,KS.01,3.1 Cook-Westinghouse Thermal Science. Chapter 2.Pp 63-70,79. /020,KS.06,3.4 SHNP,-Thermo-LP-1.2 and-steam tables

' ANSWER 1 17 (1.00) a REFERENCE HUR, Reactor Theory, Sesssons 41 and 42 DCC, WNTC_ Theory text. pp. 1-4.26 27.

SHNP,.RT-HO-1 IS, Pp. 8 10.

ANSWER .1 18 (1.00) b REFERENCE.

HUS. Nuclear Energy Training, Module 3. Unat 6 Westinghouse Reactor Physics. Sect 3, Neutron Kinettes and Sect 5, Core Physics

!!BR, Reactor Theory, Sessions 20 and 24 - 31 SHNP, RT-HO-1.14.

1 __ER1HCLELEE_QE_NECLE&E_EQWER_ELAMI_QEER&I1QNm PAGE 41

, *IHEkMQQ1NAMLCE._EEAI_IRANEEER_ANQ_ ELE 1Q_ELQW ANSWERS -- SHEARON liARRIS 1 -85/11/04-PICKER, B.

ANSWER 1.19 (2.00)

a. REMAIN THE SAME

b. DECREASE

c. INCREASE

d. DECREASE [0.S each)

REFERENCE Steam Tables ANSWER 1.20 (1.00) b REFERENCE IP-3 ECl Rx Theory: Chapter 7. Pages 21. 22, and 27 DCC Rx Theory Revtew Text, pp. 1-5.42 .50 SilNP , ; RT - L P - 1 13, Pp. 11-18.

ANSWER I.21 ( S0)

TRUE RETERENCE .

SHNP..RT LP 1 13, Pp. 11-18.

ANSWER 1.22 (1.00)

a. TALSE

b. TRUE REFERENCE 5.H. RT 110 - 1.11. Pages 22-25

1 3-_E4ANI_QE11GN_1ECEURLNG_1AT.EI1_ANQ_EMERGENC1_113IEMS PAGE 42 ANSWERS --

SHEARON HARRIS 1 -85/11/04-PICKEi, B.

ANSWER 2.01 (1.00) d .or c REFERENCE SHNP RHRS-HO-1.0, p. 11 ANSWER 2.02 (1.00) c.

REFERENCE SHNP CCWS-HO-1.0, pp 5, 8, 10, 16 1

ANSWER 2.03 (1.50) 3 of 5 required. (0.5 each) 1 Provida plant protection in event of steamitne break downstream of rostrictor

2. Provide minimum pressure loss during normal operations.

3 Reduce the potential thrust force in event of a pipe fatture.

4 '. Reduce the mass flow rate of steam that the MSIVs must close against during a steamline break downstream of the MSIVs.

5. Provide a venturn to permit measurement of steam flow.

REPERENCE SIINP SG - l!O - 1. 0 , p- 4 ANSWER 2.04 (1.00) b.

REPERENCE

' SilNP PZR-HO-1.0, p. 24 ANSWER 2.05 (1.00) c.

1.__ELAMI_QC11GN_1NCLMQLNG_EAEEII_ANQ_EMERGENC1_211IEMS PAGE 43 ANSWERS <- SilEARON HARRIS 1 -8S/11/04-PICKER. B.

REFERENCE SHNP.RODCS-HO-1.0, p. 9 ANSWER 2.06 (2.00)

c. False

b. True

c. False d false REFERENCE SilNP MT-llO-1.0, pp S-12 ANSWER 2.07 (3.00) 1 'CCW 6 Containment Sump 11. Pump Radial Brg.

2. AIR 7. 3 GPH 12. 3 GPM

3. 800 cc/hr 8. RCDT 13. 8 GPM

4. 400 cc/hr 9. 3 GPM 14. CCW S. 400 cc/hr 10. VCT IS. 5 GPM

[0.2 each)

REFERENCE SIINP R C P - 110 - 1. O RCP-TP 2.0 (Blanks numbered top to bottom)

ANSWER 0.00 (1.00J Auto stop. emergency. Overspeed protection controller [0.5 each)

REFERENCE S!!NP CllC - HO- 1. 0 . p. 5 ANSWER 2.09 (1.00) 1 2 [0.S'each)

REFERENCE SHNP CVCS-TP-1 0 1

u..

1___ELAMI_QEELGE_1MChuQLEG_E&EEll_&MQ_EMERGENC1_111IEMS PAGE 44

-ANSWERS --

SHEARON !!ARRIS 1 -85/11/04-PICKER, B.

ANSWER 2.10 ( .50)

TRUE REFERENCE RCS-HO-1.0, p-18'.

ANSWER 2.11 (2.00)

Two (2)

'Fou r - ( 4 ) .

One (1), two (2). [0.5 each)

REFERENCE SHNP CSS- HO- 1. 0, p-5.

ANSWER. 2.12 (2.00) 200, 100, 3-4, 14-18. [0 5 each)

REFERENCE.

SHNP DTRS-HO-1.0, p-8.

ANSUER 2'.13 ( .50)

FALSE RETERENCC SIINP RCS HO-! O, p-17 ANSWER 2.14 (1.50) 1%, 2%. (&/ 0.1%> (0.5 eachl REFERENCE SHNP - RV ! -llO- 1. 0 . p-15

- L.__ELANI_QE21GN lMChualMQ_EAEEIl_&MQ_EMERGENC1_ELEIEMS PAGE '4 S ANSWERS --

S!!EARON ll ARR I S 1 -85/11/04-PICKER, B.

ANSWER 2.15 (1.00) b.

RETERENCE SHNP AFS-HO-1.0,.p-7.

ANSWER 2.16 (2.00)

' 9) ^

> 2M ,000 12 3

350 [0.5 each)

RETERENCE S!!NP ATS-IlO- 1. 0, p. 8

.VCS Plant System Descriptions, IB-4, p. 6

' ANSWER 2.'17 (3.00) i 3 Intermediate

b. Source c- None

d. Intermediate

e. Source, Intermediate. Power

f. Source (0.5 each letter 1 ,

t RETERENCE Sl!NP M I S - 110 - 1. 0 , pp 10-15 ANSWER 2.18 (1.00)

Emergency Service Water fire Protection (0 Seachl REFERENCE S!!NP ' UllS 110- 1. 0, p. 3

. , , . , , . , -, ..-----.v.a._,,. - - ,- , , - ,, , - -

~..

1.__ELAMI_QEELGE_LEGLuQLNG_SAECIl_AMa_OWERGENC1_EISTEME PAGE 46 ANSWERS?-- SHEARON HARRIS 1 -85/11/04-PICKER, B.

ANSWER 2.19' (1.00) c.

REFERENCE-SHNP CI.A-HO-1.0,.p. 7 ANSWER 2.20 (1.00) b.

REFERENCE.

SHNP SIS-HO-1.0. p. 5 ANSWER 2.-21 (1.00)

C.

REFERENCE SIINP CVCS -110-- 1. 0 , p-13.

LANSWER 2.22 (1.00) a

~ REFERENCE GilNP1 ESCWS-IIO- I . 0, ' pp .? , 9, !!, 19 t

1.m_1NSIauMEMIS_AUQ_CQEIRQL1 PAGE 47 ANSWERS -- SHEARON HARRIS 1 -85/11/04-PICKER, B. -

i.

i ANSWER 3.01 (2.50)

c. INTERMEDIATE and POWER

b. SOURCE, 1NTERMEDIATE and POWER

c. NONE

d. INTERMEDIATE and POWER O. INTERMEDIATE and POWER (0.5 eachl C2.5)

REFERENCE

> Zion SD, 6a,6b,and 6c.

SHNP NIS-LP-1.0, pp 8-19 ANSWER 3.02 (1.00) c.

REFERENCE SilNP CCWS -IIO- t . 0 . . p . 18 ANSWER 3 03 (2.00) f 1 Ptr l e, v e l > 17%.

^2. Both letdown isolation valves 459 and 460 open.

3. P r o r,e r air pressure.

4. Voltage available. [0.5 each)

RF.TERENCE 311MP CVCS !!O- 1. 0 , p. 0 l

1

.. ANSWER 3.04 (2.00)

a. Tru*

b. True cv- l *S4 $c e NM aduha%

c. false

d. % Wuc IO.S each)

REFERENCE SHNP CIS-LP 1.0, TP-1.0 S!!N P ESrAS LP 1.0, pp 7-10 l

l e.-,- + - - . , . . , - , - - . . , - - . . , , . - .

- - ,. a.---- - ., .

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

l.,_LNQIREMENTS_ANQ_CONIROLE PAGE 48 ANSWERS -- SilEARON HARRIS 1 -8S/11/04-PICKER, B.

ANSWER 3.05 (1.00) d REFERENCE SIINP RODCS-LP-1.0, TP-5.0 ANSWER 3.06 (1.00) b REFERENCE SilN P EST AS - HO - 1. 0, p. 10 ANSWER 3.07 (1.00) d REFERENCE SHNP RODCS 11 0 - 1 1. T P - 16 . 0 . sect 3.5.2 ANSWER 3.08 (1.00)

b. e. f [0.33 eachl REFERENCE SHNP SGWLC-llO 1 0, sect 3.4.0 ANSWER 3.09 C1.00)

C REFERENCE VCS Plant System Desertptions. IC 6 p 05 S!!NP RPS-LP-1.0, p. 12

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

I i

1 y_1NGIREMENIE_ANQ_CQNIRQL2 PAGE 49 s - ANSWERS -- SHEARON HARRIS 1 -85/11/04-PICKER. D.

i i-

. ANSWER 3.10 (1.00) d

-REFERENCE SHNP PZRPC-LP-1.0. p. 14 i-ANSWER 3.11 (1.00) con'stant mass [0.51.

' liquid waste processing or waste discharge or rad waste or (will accept other answers if same meaning is conveyed) (0.51.

< REFERENCE SHNP PZRLC-IlO-1.0 p. 18 1 .ANGWER- 3.12 (3.00)

a. 1,3 J b. 4' c.

d. 1.3 .

e. 1,3

't. S- ,

- g. S .

h. 1,3 I.CS each responsel (3.0)

R EIT.R ENC E VCS Plant System Desertptsons, le 1. pp 13 23 i Zion 3 D 21e SitN P GDCG-LP-1.0, pp S 13frw+'IP 1. 0 an/ 7P- 4 0 ;

ANSWER 3.13 (1.00) c REFERENCE GilNP RPG-LP-1.0, p. e 4

5 t

b A

P

1.__1NQIRUMENIE_ANQ_CQNIRQL1 PAGE 50 ANSWERS -- StiEARON HARRIS 1 85/11/04- PICKER. B.

ANSWER 3.14 (1.00) b REFERENCE CHNP ESTAS-HO-1.0, p. 7 "WER 3.15 (1.00) b REFERENCE SHNP SEO HO-1.0, p. 4 ANSWER 3.16 (1.00)

G REFERENCE SilNP SEO-LP- .0, p. 8 ANOWER 3.17 (1.00) a REFERENCE GHNP R ii P,3 f. P 1 0. p 13

1.,__1NjlIRUMENI1_ANQ_CONIRQLE PAGE S1 ANSWERS -- SHEARON llARRIS 1 -85/11/04- PICKER. B.

ANGWER 3.18 (3.00)

a. 1. Overspeed

2. Gen. Differential 3.,

% Bus I a . : h. O.f4 .d

4. ::; : L. v. : ;srp:--+"r= ^ _. I S each) (1.0)

g. W d^

b. 1. Lo turbo oil press. 6. Lo Lube oil press, 10. Lo Jacket

. 2. 11 1 Eng. bearing temp. 7. Hi Cen. Dear temp water 4.e a n Vibration !!! crankcase press. 38" N 3.

DO Neg. phase seg.

8.

g, g. .

NV-

4. 9. Ht Jacket water

5. DC volt inbalance with temp g Reg Overvoit or Loss of Excitation or Reverse Pwr (8 required 9 0.25 each) (2.0)

REFERENCE GilNP DE-LP-1.0 pp 2 4 '. 25. 35, 36 , 5 4nc.P - TP - 2 0 ANSWER 3.19 ( .50) f a i s --

REFERENCC GHNP fr LP-1.0. pp 12.13 ANSWER 3.20 (1.00's C

RETCRENCE GilflP FP !!O 1.0. p. I7 ANSWER 3.21 (1.00) b .

RErCRENCE SHNP ATS LP-1 0, p. 13 l

l

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

!- PACE L.__1N,2IRUMCEIE_&NQ_CONIRQLE S2 I* -8 S /11/ 0 4 -P ICKER , B.

-. ANSWERS -- S!!EARON llARR I S 1 I

r.

l ANSWER 3.22 (1.00)

Chemical Volume Control System (CVCS) >

Reactor Coolant Drain Tank (RCDT)

Gaseous radwaste drains Recycle Holdup Tanks (RHT) (0.25 each)

{ REFERENCE i SilNP BRS-LP-1.0, p. 4 l

l.

ANSWER 3.23 (1.00) b t REFERENCE SHNPP SGWLC 110.1.0, p 9-13.15.

i 3

l- s s

(

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

9 L.__ERpCEQuRE1_ _NQRMAL _&REQRMAL _EMERQ[NC1_&NQ PAGE S3

, R&.21QLQQ1 CAL _CONIRQL ANSWERS -- SHEARON HARRIS 1 -8S/11/04-PICKER. B.

ANSWER 4.01 (1.00) d~

REFERENCE SHNP GP-004-GP-LP-1.4. .pp 25, 26 ANSWER 4.02 (1.00)

G.

REFERENCE S.H. EOP-EPP-001, p. 12

ANSWER. 4.03 (1.00) d.

REFERENCE S !! AOP 004 p 3 ANSWER 4.04 (1 00)

' REFERENCE G11NP COr - P ATt! !. i' R ; 0 1 i

ANSWER 4.05 (3.00)

(0.5 pts cach)

a. 6,-9

b. I

c. 6 d.

e.

\4 a

i

L.__ERQCEQuRES_

._NQRMAL._AaRQRMAL._EMERGEMCY._ANQ PAGE S4

,- RahlOLOGICAL_COMIRQL

, ANSWERS -- SilEARON liARRIS 1 -85/11/04-PICKER, B.

REFERENCE SHNP GP-005

' ANSWER 4.06 (1.00) b.

REFERENCE S . 11 . AOP-006, p 4.

. ANSWER 4.07 (1.00)

Borat unti1 s fe reactor condtttons

at estabtished.OP S b M8a b3 CdeMe, md8 W sah e tmadth (t.e. so n m u m*.h c.4 c . )

REFERENCE Sil N P AOP 002, p. 5 ANSWER 4.08 (1.00) a REFERENCE SURRY, EP-1.00, p. 3 SilNP EOP - P ATii- 1 AN3WER 4.09 (1.00) d REFERENCE Surry. EP 1.02A. p. 6 S!!NP . COP-EP P-OOS , p. 9

, ANSWER 4.10 (1.00) d.

REFERENCE S . }I . COP-EPP-004, p 3.

i___ERQCEQMRE1_ _NQEM&L._&RNQEM&L&_EMERQEHQ1_ANQ' PAGE SS

, ' E'AOLQLOGLCAL_CQNIRQL-ANSWERS -- SHEARON HARRIS 1 - 85/11/04-PICKER. B.

=,

ANSWER 4.11 (1.00)

C REFERENCE Surry, EP -4. 00, pp. 9, it, and 12 SHNP EOP-PATH-2 ANSWER. 4.12 (1.00)

'a REFERENCE Su r r y 1 - AP - 1. 4. pp. 3 - 5 SHNP AOP-001, pp 16 20 ANSWER '4.13 (1.00) b RETERL*NCE Surry, AP-43, p. 2 SiiNP AOP.-018..p. 15 ANSWER 4.14 (1.00) c.

REFERENCE S.H. AOP 004, p 4.

ANSWER 4.15 (1.00) b REFERENCE S.H. AOP-16, p 6.

4

. 'i.__E4QpCQHRE1_;_NQEM&Lu_&aMQRM&L _EMERQCMC1_&NQ PAGE 56

. . R&QLQLQQLCAL_CQRIRQL ANSWERS --

SHEARON HARRIS 1 -85/11/04-PICKER. B.

)

ANSWER 4.16 (1.00)

C.

REFERENCE S.H. RC and PM,'p 4-3 and preceeding change i nsert.

< ANSWER 4.17 (1.00)

C REFERENCE 4 SHNP AOP-014, p. 4 ANSWER 4.18 (4.00)

a. Xenon decay.

b. .100. (6/- S)

c. 320 C+/- SJ (or 625)

d. 1770.

e, 0 (*/ ii )

f. Operations Manager.

g. hgur 4

h. 400. '(*/- 10) 1.S each letter)

REFERENCE S.H. GP-02, Pp 14-17.

d ANSWER 4.19. (1.00)

C.

REFERENCE S.H. RC and PM, p 4-11

.. , . _ - , _ . , -- , ,~r. ..,_ . - . . - . . . . - . . , .s.,._, , . . . - . . - - . . . . _ _ , y.

i.__ERQCEQUREE_:._NQEMAL _ARNQEMAC2_EMERGENCL_ANQ PAGE S7

, _'.E'A11QLQQLCAL_CONIEQL

-ANSWERS --

SHEARON t!ARRIS 1 -85/11/04-PICKER. B.

i- ,

! 1 ,

+

1 ANSWER. 4.20 (1.00)

b. '"

RETERENCE '

IO CFR 20, 20.102 '

+

2 ANSWER 4 . 2 1' s (1.00) i

<? r? c . i ,

3 REFERENCE .t 3

1 s 0CFR'20.3 (

t ANSWER 4.22 (1.00) b.

.[.

- \.

RETERENCE (4 '

10 CPR 20.101

&. s.

\.i -f AN'SWER 4.23 (1.00$ .

~\

iY-

\. b.

~

RETERENCE I

S!!NP GP 004. pp.8 9

' ?

- ,, 'i ,

i! ',

ANSWER 4.24 (1.00) 4

.;_ ,4

,. 41- '

2 REFERENCE i Surry CP+1.02a. p '. S~

SilNP EDP'-E P P,- 0 0 7 .

k &

i.

't

'q ' ;

\

s

% b s

~

_________-__-c_____

PACE 58

.: L.__EBSCEQMRE1_.:._MQRMAL._A ENQRMAL._EMERQENCY._ANQ :

, '"ICARLQLQGLCAL_COMIRQL ANSWERS -- SHEARON HARRIS 1 -85/11/04-PICKER. B.

ANSWER 4.25 (1.00) d.

REFERENCE SHNP-EOP-PATH-1, foIdout A

a *

'U. S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION

. PACILITY: _SUEAE9H_MABE13_1 REACTOR TYPE: _EWR-WEC1___ _ _

DATE ADMINISTERED:_ ail 11Lai__ _ __

E X AM I N ER': _1SAKSEN _E -- _ -

APPLICANT: _ (_T M N'"*/ _

-1NSIRECILONE_IQ AEELLCAMIl M] JIEn LL' '-

Use separate paper for the answers. Write answers on one side only.

Staple question sheet on top of the answer sheets. Potnts 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 six (6) hours after the examination starts.

% OF CATEOORY % Of APPLICANT'S CATEGORY

__MALUE_ _I.lIAL ___ECREE___ _YALUE__ ___ ________CAIE99EI lo 00 21.20 ________ S. TilEOR Y Of NUCLEAR POWER PLANT OPERATION, FLUIDS. AND T!!ERMODYNAMICS

_a2.20__ _ai.ta ___.._______ ________.u PLANT GYSTEMG DESION, CONTROL, AND INSTRUMENTATION

.10.Ed._ li.lu . _ _ _ _ _ _ _ . - -_____ _

7. PROCEDUREG NORMAL, ADNORMAL, EMERGENCY AND RADIOLOGICAL CONTRvL

_lk_Q 0__ _al..Q Q _ _ _ _ _ _ _ . _ _ _ _ ________ 8. ADMINISTRATIVE PROCEDURES, CONDITIONS. AND LIMITATIONS Laa.aa__ 120.QQ ___________ ________ TOTALG f!NAL ORADE _________________%

.All work done on this examination 1 my onn. I have neather given nor recetved ato.

b APPLICANT *S SIGNATURE

)

Sc__IWEQEI_QE_ NUCLEAR _EQWER_ELAMI_QEERAI1QN _ ELM 1 rem _ANQ PAGE 2 THCEMQQINAMLC1 4 .

QUESTION S.01 (1.50)

a. With the plant operating at 85% power and all systems in a normal / automatic configuratton, the operator borates 100 PCM.

Shutdown Margin (1.0)

1. Increases. '

2. Increases until rods move.

3. Decreases.

4 Decreases until rods move.

S. Remains unchanged, whether or not rods move.

b. The Shutdown Margin required by Technical Spectfications for the operating condition described in a.. above, ts_ _ ___ _ P C M . (0.S) 1 1

1 OUESTION S.02 (2.00) ilo t channel factors are measurable and their Technical Spectfication

survet!!ance frequency requirements are elatively' low, provided FOUR

, items are monitored and vertfled to be within their limits. What are

.hese FOUR items?

.OllESTION- S 03 (2.50)

, Comp,re tne CALCllLATED Estimated Crattcal Pos tron (ECP) for a startup.

to be performed 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after a trip from 100% power, to the ACTUAL contro l tad posntton (ACP). 1f the following events /condit' tons occurred.

Constder each andependently. Lim t your answer to ACP s H I GIIER than, ,

LEWER than, or SAME as the ECP.

a. vne reactor coolant pump ts stcpped two minutes prior to crittaality. (0.5)

b. The startup is delayed until 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months after the itip. (0.5)

, c. The steam dump pressure f. e t p o t n t is increased to a value Just below the Steam Generator PORV setpoint (0.5) d, Condenser vacuum is reduced by 4 inches of Mercury. (0.5) e All Steam Generator levels are being raised Ly 5% as the ACP is reached. (0.5) i i

(***** CATECORY 05 CONTINUED ON NEXT PAGE *****)

4 .__I11EQR1_Q E_NUC LE AR_EQWEB _E L &NI _QEERAILQN._ELQ1QSm_ ANQ PACE 3 IHERMQQ1NAMLCS

-QUESTION S.04' (2.00)

A. Does Beta bar effective Increase, Decrease, or Remain the Same, from BOL to EOL? (Briefly explain your choice.) (1.0)

B. For equivalent positive reactivity additions to a critical reactor, will the SUR be the Same, Larger, or Smaller at EOL compared to BOL? (no explanation necessary) (1.0)

QUESTION S.05 (1.50)

Two identical reactors are taken erstical usang continous rod withdrawal Reactor.A has a rod speed of 48 steps per minute and reactor B has a rod speed of.24 steps per minute.

a. Which reactor will obtain erattcality first? (0,5)

b. Which reactor will have the highest source range counts at criticality? (0.5)

c. How will 10-8 crstical rod heights compare in the two reactors? (0.5)

OUESTION 5.06 (1.00)

TRtit or FALSE?

a. At EOL, the Doppler Temperature Coefficient is more negative due to an increase in the quanttty of Pu 240 in the fuel

b. Wtth all rods out, and a constant baron concentratton (ppm), the MTC becomes mor- negative as RCS temperature (Tavg) increases

(***** CATECORY 05 CONTINUED ON NEXT PAGE *****)

4.__IMEQRY_QE_ NUCLEAR _EQWER_EL&W7__QEERAI1QN _ ELM 1QS _ANQ PAGE 4 THERMQQINAMICE QUESTION- S.07 (1.00)

Which of the following. nuclear related factors or rattos has a normal value of less than one?

t'

.e. Reproduction factor (Cta)

b. Importance factor (1)

c. Fast itsston factor-(Epstion)

d. Departure from Nucleate Botling ratto (DNBR) t QUESTION S.08 (2.00)

a. Provide TWO-reasons for Xenon contributing more negative reactivity at full power than Samartum. (1.0)

b. Explat'n why you agree or disagree wtth the following statement:

"Equilibrtum Samartum concentration at S0% power is approximately half 1ts concentration at 100% power." (1.0)

QUESTION 5 . 0 'J ( 1 . 0 0 .'

At B o l. , the components ot *h- power doteet in an INCREASING order of

-signsftcance (reactivity valueJ are.

4 V o s .1, Doppler, MTC

b. Votd. MTC. Doppler e MTC. Vold. Dapple

d. MTC. Doppler, Void 1

I

(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)

I

E 1.__IH EO R1_Q E_ NuC L E A R _ EQ'd E R_ E L ANI_Q E E R ail 0 N._ E Eu 1R S._ AN Q PAGE 5 IHERMODINAMICE QUESTION S.10 (1.00)

Which of the following statements concerning the power defect is correct?

a. The power defect is the difference between the measured power coeffnetent and-the predteted power coefftetent

b. The power defect increases the rod worth requirements necessary

t. o maintain the desired shutdown margin following a reactor trtp.

c. Because of the higher boron concentratton, the power defect is more negative at beginning of core infe.

d. The power defect necessttates the use of a ramped Tavg program to maintain an adequate Reactor Coolant System subcooling margin.

QUESTION 5.11 (1.00)

During fuel loading, which of the following will have NO effect on the shape of a 1/M plot?

I f.o c a t t o n of the neutron source in the core

b. Strength of the neutron source in tne ccre.

c !.ocation of the neutron detectors around the core

d. Order of placement of fuel assemblies in the core.

QUESTION S,12 (1.00)

The cactor is :ritteal at 10,000 eps.when a '3 / C EORV fasIs open.

Assuming BOL conditions, no rod motion, and no reactor trsp, choose the answer below that best describes the values o: Tavq and nuclear power for the resulting new steacy state. ( POAll : point of adding heati

a. Final Tavg greater than inttaal Tavg, Final power above POAH.

b Final Tavg greator than intttal Tavg. Final power at POAll .

c. Final Tavg less than intttal Tavg, Final power at POAH.

l

d. Final Tavg less than intttal Tavg. Final power above PO All . j

(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)

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

ic__IHEOR1_QE_ NUCLEAR _EQWER_ELANI_QEERAILQN _ELu1QE _ANQ PACE 6 IHERMQQ1NAMIC3 QUESTION 5.13 (1.00)

The Moderator Temperature Coefftetent (MTC) varles with certain plant conditions. Concerning these vartations, which of the following is correct?

a. The MTC becomes more negative as boron concentration is increased,

b. The MTC causes axial flux distributton to be tilted towards the top of the core at BOL.

c. The MTC varles as temperature changes because of the non-!!near density changes of water as temperature changes.

d. The MTC is not permitted by Technical Spectfacations to be positive for any of the plant operating modes.

QUESTION S.14 (1.50)

a. At what axial location in a PWR core is the erttical heat flux (CHF) at the MAXIMUM? (Limit your answer to top, middle, or bottom.) (0.S)

b. Il o w does the MINIMUM critical heat flux change (increase, decrease not change) as the following parameters are INCREASED? Consider each separately. (1.0) 1 Tave

2. RCS pressure 3 RCS flow QUEGT!dN 5.15 (2.50)

a. If steam goes through a throttling ptocecs. spectiteally as in a leak from the high pressure main steam header, Indicate whether the follow-Ing parameters will INCREASE, DECREASE, or REMAIN TIIE SAME. (2.0) 1- Enthalpy

2. Pressure .

3. Entropy 4 Temperature J l

b. Wtil the steam become subcooled, saturated or superheated as it leaks out? C0,5) t

'l

(***** CATECORY 05 CONTINUED ON NEXT PACE *****)

1.__It6EQR1_QE_NuQLEAE_EQWER_ELANI_QEERAIl0N _ ELE 1Q1._ANQ PAGE 7 IHERMQQ1NAMICE QUESTION S.16 (1.00) from the choices below, select the one which best completes the sentence.

When the flow rate through a centrifugal pump is increased by opening the discharge valve, the r e q u i r e d N P Sil _______ , and the available NPSH (a) increases increases (b) increases decreases (c) decreases increases (d) decreases decreases QUESTION S.17 (1.S0)

'TRUE or FALSE?

s. The faster a centrafugal pump rotates, the greater the NPSH required to prevent cavitation. (0.S)

-b. One of the pump laws for centrifugal pumps states that the volumetrte flow rate is inversely proportional to the speed of the pump. (0.S)

c. P urnp runout is the term used to descrtbe the conditton of a centtifugal pump running wtth no volumetric flow rate. (0.5)

- - OUESTION 5.18 (1.00) 4 In o r d .t r to maintain a 200 F subcooling margin in the RCS when reducing RCS pressure to 1600 psig, steam generator pressure must be reduced to apptoxtmately:

a. 24S pstg

b. 445 pcig

c. 64S psig ,

-d. 845 pstg

)

(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)

im__IHEQR1_QC_NMCLEAR_EQWER_ELANI_QEER&I1ON _ELMLQE _&NQ PAGE 8 IHERMQQZNAMICE QUESTION S.19 (1.00)

The reactor is operattng at 30% power when one RCP trips. Assuming NO roactor trtp or turbine load changes occur, which one of the following parameters will DECREASE?

a. Ficw in operating reactor coolant loops

b. Core delta.T

, c. Reactor vessel detta P

d. Steam generator pressure in affected loop QUESTION 5.20 (1.00)

The reactor is operating at 90% of rated thermal power with Tavg on program and equilibrium Xenon. The secondary instruments indicate i_ steam pressure at 835 ps1g. The computer shows feedwater temperature l at'440 F. Neglect any energy added by the RCP's and assume all liquids at saturation. Calculate the mass flowrate in the secondary system.

6

a. 3.2*10 lbm/hr 6

1 b. 10.9*10 lbm/hr 6

j

c. 10.2*10 lbm/hr G

d. 3.6*10 lbm/hr

! OUESTION S.J1 (t.00)

Assuming at1 Other tactors are identscal, the mass flow rato of fluid

through a 10 inch diameter pipe will be approximately ____ times as great as rne mas, flow rate thraugh a J inch diameter pipe.

a

a. J.S b S.0

c. 10.5

d. 25.0 i

i

(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)

it__IUCOEl_Q E_UUCL EAR _EQWER_EL AUI_Q EER&ILQM m_ELU LRS _ANQ PACC 9 IUCRMQQ1NAMLCS OUCSTION 5.22 (1.00)

The main condenser must remove more heat energy to condense

c. One pound of steam at 0 psta.

b. One pound of steam at 300 psta.

c. Two pounds of steam at 600 psta.

d Two pounds of steam at 1200 p.ta.

(***** END Of CATCCORY OS *****)

E L Et__ERAMI_213IEMS_QCSIGN _CQNIRQL _AUQ_LNSIREMENI&I1QM PAGE 10 i

1

-QUESTION 6.01 (1.00) g Which of the-following-conditions / interlocks must be sattsfned, in order to j . allow for a manual reset of a SIS?

i

a. 20-seconds have elapsed since Si tnitiation.

b. Reactor trip breakers open.

I l- c. PZR pressure.above P-!!-

I f d. St signal cleared.

~

j' QUESTION 6.02 (1.00) l l l Indicate WHET!!Ed or NOT cach of the following signals / conditions would i r e s :11 t in a main steam !!ne isolation signal

-a. I. u w steaminne pressure, l

b. ' ll i g h steam pressure rato above'P-!! setpoint.

c. III -1 containment pressure,

d. 111 -! !1 con t a i nmen t pressitre OUCSTION 6.03' (2.00)

a. What condstion, IN ADDITICN To a teodwater isolatson signal, will automatically close the main feedwater control valves? (1.0)

( b. Which.cf the following is NOT a bases / reason for main feedwater j t s o t a t t <; n actuation? (t.0) l 1 Prevents motsture carryover resulting in damage to the main i turbine bladtng.

2. Prevents / mitigates a loss of secondary coolant accident.

i J. Prevents /mittgates excesstve plant cooldown fotlowing a turbtne trtp.

4. Prevents / mitigates the consequences of the event which caused a-Sin.

(***** CATCGORY 06 CONT!!1UED ON NEXT PAGE *****)

I L __ _ _ _ _ _ - _ _ - -

L __EhANI_SISIEM2_QE2LGM._CONIRQL._AND_LN1IREMENIAILQM PAGE 11 QUESTION 6.04 (1.00)

Which of the following is correct concerning the Source Range channel high voltage cutoff?

a. During a reactor startup either IR channel increasing above P-6 will turn off the high voltage.

b. If one IR channel fails low while at power, the Source Range high voltage will be re onergized.

c. Two out of four PR channels above 10% power will turn off the high voltage.

d. During a reactor shutdown either IR channel decreasing below P-6 will turn on the high voltago.

QUESTION 6.05 (1.00)

Indicate whether the Over Temperature Delta Temperature (OT-DeltaT) trip setpoint will INCREASE. DECREASE. or REMAIN THE SAME for the following parameter changes. Consider each separately.

a. Increasing Tavg.

b W"

Tavg less p than[f$ted,p*ower Tavg.

c. DeIta I becoming more negattve.

d. Pressurtrer Precure'!ncreasing.

1 i

1 t

n

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

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

hi__ELANT_SISIEM2_QE11GN. CQNIRQL _ANQ_1NSIEllMENIAIlQM PAGE 12 i

QUESTION 6.06 (2.00)

TRUE or FALSE?

a. If a containment spray actuation signal (CSAS) occurs within 5 seconds of the LOCA sequencer initiation the containment spray pumps start at five seconds and the sequencer proceeds in a normal sequence. -(0.5)

b. If CSAS is received after,five seconds of LOCA sequencer operation the sequencer stops loading and starts the spray pumps then proceeds with the remaining sequence cycle. (0.S)

c. The reactor trtp-bypass breakers are electronically interlocked such that if an attempt to close both breakers is made both bypass breakers trip open. (0.S)

d. The low PZR pressure trip as automatically bypassed below 10% pow 3h to permit the shutdown banks to be withdrawn during a cooldown. (0.S) i i

QUESTION 6.07 (2.00)

Match the interlock descriptions in Column A with the appropttate control identifscation in Column D. (te. e. 7) l COLUMN A COLUMN 8

a. Prevents auto rod withdrawal of Bank D only. I C1

2. C2

b. Turbine loading inhtbtt on excesstve Trei Tavg. 3. C3.

4. C4

c. I'revents auto / manual rod withdrawal when >OP-DT setpoint. S. Cil

6. C16

d. Prevents auto / manual rod wtthdrawal when IRM indicates

,2 0 % power.

I 1

i

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

L___EiANI_3X1IEM1_QEELGN _CQMIRQLs_ANR_181IRUMENIAILQM PAGE 13 OUESTION 6.08 (3.00)

a. Indicate whether the following statements concerning dtesel generator CDG) operation are TRUE or FALGE?

1. ' ALL engine shutdown signals are blocked for 60 seconds to allow the diesel to reach operating condttions except for high bearing temperature and lube oil temperature. (0.5)

[ghb-4F- To stop the DG from the DECP the master control switch must be local and the " emergency stop" and " emergency stop think" buttons must be depressed simultaneously. (0.5)

3. The overspeed trip is the ONLY trip that is operative in all modes of DG operation. (0.5)

b. For each of the following, i nd i ca t e WHETilER or NOT the condition must be met in order to permtt the DG to be manually stopped from the MCB.

( u_ = 'y M m- ; r - -- A) (g,5)

1. No SIG signal present.

2. DC output breaker closed

3. No undervoltage signal present 4 " Operational / Maintenance" selector switch in " Operational" position.

l S. DG lockout relay reset

! QUEGTION 6 09 (l.00)

Whtch of the following flowpaths correctly descrtbe how power is no rma A y supplied to Uninterruptable Instrument panet IDP-1A Gl?

a. 480 VAC from vttal bus 1A3-GA, recttited to 120 VDC. inverted to 120 VAC, and supplied to bus IDP-1A-Gl.

b 400 VAC f.om vital bus IDP 1A-G1, transformed to 120 VAC, and

upplied to bus 1DP 1A G1.

c. 120 VOC from battery, inverted to 120 VAC, and supplied to bus IDP- I A - G1

d. 100 VAC from bus IA211 is supplied to bus IDP 1A-31

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

S.__ELANI_HISIEM2_QEELGN CQNIRQL _ANE_LNSIEMMENI&ILQN PAGE 14 QUESTION 6.10 (t.00)

Which of the following statements concerning the effects of controlling PZR pressure channel PT-444 fatinng high during mode 1 operation is correct? Assume NO operator action.

c. The master control.ler will cause control heaters to deenergtze and both PORV's to fall open.

b. Both spray valves will remain open and RCS pressure reduction results in reactor trtp and 31

c. The reactor will trip on high pressure signal

d. The reactor will not trip on high pressure due to plant safety valve actuation reducing RCS pressure. +

QUESTION 6.!!- (2.00)

Indicate WiiETi!ER or NOT the following statements concerning the PZR Overpressure Protection Subsystem (OPS) are correct.

a, Wide range pressure and nu:tionected low narrow range temperature are inputs to the control circuitry.

b. If the OPS requires the PORV's to open and the isolation valves are shut, the tsoliti n 'atee, a u t oraa t t c a l l y open.

c. The purpose of the OPG is to protect the RCS from pressurized thermal shock

d. In mode 1, a temperatal- inpat faals low and the PORV control swatch is in AUTO, the FohV's wtll ta11 open uuttI shut by the P 11 interlock

(***** CATCCORY 06 CONTINUCD ON NCXT PAGE *****)

m-

=

Et__Ek&NI_SISTEM3-QESLGMm_COMIRQL AMQ_LMSIEUMEMIAIlQM PACE 15 p

L QUESTION 6.12 (1.00)

! Indicate WHETHER or NOT each of the following is a result (DIRECT OR

( INDIRECT) when the PZR level channel 459 (controlling channel) falls high l

with NO operator actton. Assume Mode 1 operation.

a. Charging flow decreases.

b. High pressure reactor trip and St.

l c. Letdown isolates. -

d. High level reactor trsp.

-QUESTION 6.13 (1.00)

Which of the following failures of an "RTD" in the circutt would result in a fatted 111 011 temperature indication?

l Short~

3. Open l

l OUCSTION 6.14 (1,50) l List TilREE o f the four pro'ection circuits that Tavg ptovides an input

[ signal to, according to RCTEMP 110- 1. 0.

l i

L e

i t

l l

l (***** CATECORY 06 CONTINUCD ON NEXT PACE *****)

F L- .

im__EbaNI_SISIEMa_QEalGN _CQMIRQL&_&MQ_1NEIEMMENIAIlQM PAGE 16 l

l l

l . QUESTION 6.15 (2.00)

.For each case below select the method of RCS temperature control that most l

correctly describes the final plant condition. Consider each case separately and assume initial normal system lineup for each case. Cror

-example, S. e)

CASE:

1. Steam pressure nety.. . is reduced by 92 psa while at stable plant condittons avatting reactor startup.

2. The Steam Dump selector swttch is placed in "off" while at 5% reactor power awatting turbine startup.

! 3. Train B reactor trip breaker fails to open upon a trip from 78%

power NOTE: Train A breaker opens.

l l

l 4. Reactor power ~20% and main turbine trips.

METil0D:

a. Secondary pressure rises to atmospheric rettef valve setpoint, main-tatning Tavg ~560 F.

b. Tavg decreases to approximately P-12 setpoint

c. S t e am dismp controlling by load rejection cont cIler

d. Steam dump controlling by trip controller l

(***** CATECORY 06 CONTINUED ON NEXT PAOC *****)

F 1__ELANI_21SIEME_EC2LGN. CQMIRQL _AME_1NSIR'lMENIAILON PAGE 17 QUESTION 6.16 (2.00)

I a. Whtch of the following ts NOT a reason for the 3/C level program?

1 Mtntmize cooldown of RCS following a steam break.

2 Maintatn constant mass in S/C at all power levels to facilitate chemistry control

3. Minimize containment pressure following a steam break.

4. Minimise inadvertent low low S/G level reactor trips following a load reduction.

b. Which of the following is NOT a protection feature derived from the same inputs that feed GCWLCS?

1. Low steamline pressure S! and steamline tsolation.

O. Turbine trip and feedwater isolation.

3. Reactor trtp and ATW actuation.

4. li n g h steamline D/P reactor trtp and AfW tsolation.

3 OUESTION 6.17 (1.00)

The adic MTW punip starts automatically at the other MrW pump is operating and an automatic start signal Is received. What are the TilREE conditions which will generate an automatic start stqnal' 00EGTION 6 la Cl S0) a_ "tito the condation(s) which will autataattcally open contatnment rectreulatton sump suctton valves to R i! R G 7 (0,5)

b. Otate the bases / reasons tor the RCS hot leg to RilRG suction valve OPENING interlocks. (valvos 8701A.8702A) (1.0) .

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

-Ow__EiANI_312 TEM 2_QE11 Gum _CONIRQL _ANQ 1NSTRUMENIAI1QN PAGE 18 OUESTION 6.19 (1.50)

I a. For which of the following turbine trip.stgnals will the power circutt breaker from the generator immediately open (no 30 sec.

time delay)? (0.5)

l. Manual Trip l

[ 2. !!!gh ..%ratton Turbine Trip i

3. Overspeed Trip

4. T h r ts s t Bearang Trip

~b. What'are the TWO " safety-related" requirements / reasons for the 30-sec.ttmo delay? (1.0)

QUESTION 6.20 (1.00)

What is the. required flowrate that auxiliary feedwater-must supply to the G/G's on-a loss of normal feedwater with site power available?

a. 380 ypm l

l l 'b. 500 gpm

.c 300 gpm

d. 030 gpm l

t l

s l

I

{

l

(***** END OF CATECORY 06 *****)

4.__EEQCEQUEE2_;_MQEMAL _ARNCRMAL _EMCEGCMC1_ANQ PAGE 19 R&QLQLQGLCAL CQNIRQL QUESTION 7.01 (1.00)

Whon RCS temperature is >350-F. before increasing pressure above 400 psag, verification that the Low Temperature Overpressure System is not armed is required. Ilow is this verification performed, according to Normal Plant Hostup tMode S to Mode 3) procedure GP-002?

OUESTION 7.02 (1.50)

Complete the following statements by ftiling in the approptlate numbers. Place answers on your answer paper.

d. If crsticality occurt at less than _______ pcm below the ECP or has not occurred by _______ pcm above the ECP. the control rods must be inserted,

b. A reactor coolant pump shall not be started wtth cold les tempera-tit r e s < ____ degrees T unless th4 S/O secondary temperatple is less than ____ degrees above each of the RCS cold log temperatures.

-c. If the source tange count rate 'ncreases by a factor of -_

i _.

.dutIng boron dilution. .t_p t h .: driution.

d During boron concentrat - c h a n tl e s of ,______ ppm or greater, the presaut :: e r sptay 2: vu:j te inittated to equa11ze the concentrations in the (+ actor coolant loops and pressurtzer 00ESTION ?.03 (1.00 rurbine.pnerator tuad e n a .. , 2: e ! . m t t c ci to a ma x t raum o f ____%/ min.

3 i b,

c. 5

d. 10 l

l

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

r 2 __E20CCD!.lRES_ _ NORMAL _ARNQEMAL _CMCRGENCL AUQ PACE 20 RADLQLQGLCAL_QQUIRQL O'J E ST I ON 7.n4 (1.S0)

Complete the following statements from the selections below concerntng GP-005. Power Operation procedure. Place answers on your answer paper.

c. During plant startup tMode 2 to Mode 1) operations, the wide range and narrow range S/G levels tend to disagree. Use the range level indication to observe which direction level is moving.

b. During startup and loading of the turbine, the 3/G water level is very unstable and has a tendency to _____. maintain G/G level I

at 66% on _____ tange level indication for better control I Narrow

0. Wide 3 Ghrink 4 Gwe11 i

QUESTION 7.05 (2.00)

a. Why is rractor power t ra t * + d ta 10*6 whra n.a o turbtne throttle vaives are not ful'y open? ft 0) b in what docament can the opetator obtain turbine resonant r a n g e s ( U . S }

c. At about ____% turbtne 13ad transfer '. h e :. team .t ump to the Tavg contro! sao d e . (0.S) vUESTICN 7 O t, (l 50) a What is the Technical Spe: ftea!tur. .TC) ba:es/ sea;on for allowing only one Charging 3afety injection P ura p (CGlP) to be operable when RCS temperature is less than 250 F (1.0)

b. Ilow is the inoperable CSIP "verifled" inoperable according to TS?(0.S)

(***** CATCCORY 07 CONTINUED ON !! EXT PAGE *****) )

l

1 __EEQCCQUREE_.:_NQEM&L._ARNQEMAL._;MERQCNC1_&NQ PAGE 21 RAQLQLQQ1 CAL _CQUIRQL OUESTION 7.07 (2,50)

a. Which of the following ts NOT a condition requtring Emergency Doration

-according to AOP-002? (1.0)

1. Excessive control rod motion indicated by bank step counter indicat'ng the control bank is below its insertion limit.

2. Uncontrolled cooldown following a reactor trip indicated by decreasing PZR level and/or pressure.

3. Unexplained or uncontrolled reactivity increase indicated by abnormal control rod insertion.

4. One or more rod position indicators failing to indicate rod (s)

Inserted after a reactor trtp.

b. Which of the following flow paths is the one required by AOP-002 if the low-low insertion limit ts reached? (1.0) 1 Dorte acid pump to blender to CGIP suctton.

2 Boric acid pump to emergency boration valve.

3. Doric acid pump to bbinder to VCT.

4. RWOT suction to 00!P

c. According to AOP-002. Cmergency Doration may be stopped when____.(0.5)

OUESTIvN 7 06 (l 00J Mat:h the t e s p .-n : . b t ilty in column D to the i: ?tited position th column A for a contrui ' r c oni tnacces: tbtlity. ,iceerding to AOP - 0 0 4 . (ie. S-e)

CC I,UMM A COLUMN B

1. GCO a Operate key-actuated security transfer s#ttches in CWGR toom A

2. RO

b. Vcrify reactor trip at ACP.

3. DOP '

c Asstst the Ghtit Foreman in required

4. Turbine Bldg. AO Emergency Plan actions.

I

d. Perform local start of diesels if required. l l

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

i i L___EEQCEQUEE3_2_UQRMAL._AREQRMAL _EMERQENQ1_ANQ PAGE 22 EAQ10LQQ1CEL_COMIRQL i

l

, OUESTION 7.09 (1.00)

! Which.of the following statements is most correct for the automatic actions associated with Inadequate Feedwater Flow procedure AOP-0107

c. Loss of a condensate booster pump will trip the associated matn l feedwater pump if both are running.

b. If a heater drain pump is lost above 70% power a turbine runback will occur.

l

c. If both MFP breakers are open, the motor driven AFW pumps will start and a turbine runback will occur bve 50% power

d. The condensate demineralizer bypass valve wtll close on high delta-P across the domineralizers.

I OUESTION 7.10 (2.00)

Provide ALL the immediate operator actions required if level is lost in the CCW Surge Tank, according to AOP-014. ASSUME Mode 1 operation. (2.0)

QU C GT I Off '7.11 (1.00)

According to A O P -- 0 1 0 . Excessive Plant Leakaq3 procedure, what is the most correct opetator action required it leakage exceeds RCS makeup capacity?

a, ' tart addstional ;harging pumps and take manual control to maintain VCT level D. Isolate letdown.

c f n i t 1 .t t e SI

d. De in hot standby wtthin 6 nours and co14 shutdown within the following 30 hoars.

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

2 __EEQCEQUEE2_:._MQEM&L._&BMQEM&L _EMERGENC1_&MQ PACE 23 R&Q10LQQ1 CAL _CQMIRQL QUESTION 7.12 (2.00)

Durang Mode 1-operation and a loss of instrument att indicate whether the

.following. valves will fail OPEN, CLOSED, or are NOT AFFECTED.

a. MS!V's

b. PZR PORV's

c. MFWRV's

d. Charging Flow Control (1CS-231)

e. Letdown Orifice Isolation valves QUESTION 7.13 (1.00)

The following concern Reactor Coolant Pump Abnormal Conditions procedure.

AOP-018. Place answers on your answer paper

a. At ____ gpm total flow through the RCP thermal bartter coolers, valve ICC-2S2 will automatically close. (0.5)

b. Reactor power must be less than ____ % to restart a RCP. (0.S)

QUESTION 7 14 (1.00)

The (olIownng concern Seismic DLsturbances procedure. AOP-021

a. If plant condittons remain normal, operation can continue upon approval of tha __ _ or designated alternate until seismic recorder ttim and plates are evaluated. t0.S)

b. Why should the tape NOT ne removed it a yellow " Event Alarm" is on? (0 S)

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

Im__ESOCERURE3_:_UQRMAL _aHNORMAL _EMERGENC1_ANQ PAGE 24 RaulCLQQLCAL_COUIRQL QUESTION 7.15 (1.50)

o. What immediate operator action is required for high RCS activity, other than to verify an alarm is valtd, according to AOP-032? (0.5)

b. What is the TS bases for reducing Tavg to less than 500-F (within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ) if RCS activtty is greater than 100/E bar microcuries per gram? C1.0)

QUESTION 7,16 (1.001 Whtch of the following statements, concerning TS actions required for Nuclear Instrument malfunctions, is correct?

a. if a source range channel fatts while a startup is in progress and reactor power is below P 6, insert all control banks to to zero steps

b. If an intermediate range channel falls while a startup is an progress and reactor power is above P6 but below P-10, the power increase may continue using the operable intermediate range channel

c. Fatture of one power rang.. hannel durinq shutdown precludes reactor startup untt! t r. e r11 led channel is returned to operable status,

d. Failuto of both source r a r le channels while shutdowri requires shutdown margin requiten. a't to be votitted wtthin I hour QUESTION 7 17 t! 00)

Tc wb t ;! of the following p,cred ateas 1.s entry c r. 6 CRWP pelmt(ted?

a. No ti t r o n radiatton areas

b. Airborne radacactivity ar-a; e Deta hazard areas

d. iftgh radiatton are2s.

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

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

i -Im__E1QCEQMREE_ _MQRMAL._AEMQRMAL _EMERGEMC1_ANQ PAGE 2S

[ RAQ10 LOGICAL _CQRIRQL l'

l QUEbTION 7,18 (1,S0) t A 25 year old radiation worker's total 11fetime dose is 10 Rem and his NRC

! Torm-4 is up to date, li t s personnel monitoring devices are read for the I first week of the quarter with the following results: 500 mrem-whole bodyt S00 mrem-skint 3000 mrem-extremttres. What are his dose limits for the remainder of the quarter for:

i

s. Whole body 1 25 Rem

b. Skin 2. 15,75 Rem

c. Extremittes 3. ? Rem

4. 2.5 Rem OUESTION 7.19 (1.00)

Which of the'following descrabes tha RCP Trtp C iterta (foldout-A),

following a valid safety sniectton tnattatton?

a. Less than 2S degreet subevoling and pressurtzer leve! < 10%.

b. Less than 50 degrees subcooling and one C3lP is running.

c RCS pressure less than i160 psig and one CGIP is running,

d. .RCS pressure less than 1600 psig and pressurizer leve! < 10%.

QUESTION 7.20 (1.00)

A.'catJtng to Io I d 0 tt t C. which 2[ the tos1 win; .: o n d s t i u n a meet the 01 Rennstnation Criterta?

a RCG pressure less tPan 2000 ps19 RCO tubcooling less than S0 degrees, or pressurizer level less than 20%.

b. RCS pressure less than 1360 ps19, RCG subcooling less than than 50 degrecs, or pressur1:er level tess than 50%.

c. RCC pressure less than 1600 psag, RCS subcooling less than 45 degrees, or pressurtzer level less than 10%.

d. RCS pressure less than 1600 psig, RCS subcooling less than 30 degrees, or pressurtrer leve n less than 50%.

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

12__ER'QCEDURES_ _ NORMAL._AENQRMAL _EMERGENC1_&MQ PAGE 26

!. RAQ10LOGLCAL_CQNIROL i

QUESTION 7.21 (1.00)

Following a reactor trip the main turbine did not automatically trip.

According to EOP-FRP-S.1, Response to Nuclear Power Gemeration/ATWS procedure, which ONE of the following is NOT an acceptable / preferred method'to secure the turbine?

a. Manual control room'trsp.

b. Runback turbine and stop EHC pumps-

c. Shut MSIV's and bypasses,

d. Locally trip the turbine, QUESTION .7.22 (1.00) j

!ndicate which of the following is the preferred, order for depressurizing the RCS to satisfy the TS pressure-temperature cooldown curve, according to COP TRP P 2.- Response to Anticipated Pressurt:ed Thermal Shock procedure, A5 Normal spray 3: PZR PORV C Aux spray 1 A.C.D.

2 C.A.C.

3. A.3,C.

'4. C.A.D.

i i

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

L, .

?

2.4._ ElbQCEQURE3_i._NQEMAL _AREQEMAL LMCEQCNCY._ANQ PAGE 27

. R&QLQLQQLCAL_CQNIRQL

.3' .!

.i t s ,

,ss .

f' K

. QUESTION 7.23 (1.00)

Which-of .he 'fo11owing is the' method of RCS cooidown to be utiiined in

.tho-event ot a SGTR and thetisptured S/G MSIV fails to close, according to SOTR i s o l a t t o n p r o c edu r eEOP'- EP P - 16 ?

~

c. Steam dump, c o t.J e n s e r avn Iabl.e.

b. Prtmary teed ~and bleed.

' ~

c. Intact'S/G PORV's, assoct'ated MSIV's shut

~

~d . Mann steam header drains.

s c,

1 E '1-k O>, s. 7 ,

yq 1

,t i

, s i ,'

s '\

N

+

i

\ N, 1,

1 s

p- ,

s t

(

y s, t

. (, -

i

-4 g ,

5 J- &

9 : i

!ry 'i

',. A 3 ,,

(***** END OF CATEGORY 07 *****)

fff ,.

14

(

@> l[.

.- i. - - . _ , _

. _ . u , L._ _ . , _ . . . _ , _ _ . _ _ . _ . , _ _ . . , , . _ _ . , _ . _ , . _ . .

'b.__&LMINLSIRAI1VC_ERQQEDERES _CONQLILQNS _ANQ_LLMLIAllQN1 PAGE 08 OUESTION 8.01 (2.00)

List'the FOUR Technical Spectitcation bases /rcasons for the Mantmum Tomperature for Criticality.

QUESTION 8.03 (1.00)

Which of the following statements concerning " Guidance for Voluntary LCO's" procedure AP-019, is correct. '

a. The approval of the Opetating Supervisor is required for a group 1 LCO.

b. Work will proceed on a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months a day basis for a group 1 LCO condition.

c. The length of time required to complete the work for a group I or !!

LCO condition should be less than 75% of the LCO to allow sufficient ttme tor testing.

d. Voluntary-initiatson of an LCO is a routine evolution for performance of preventative maintenance QUEST!CN 8.03 (2 00)

Indicate WilCTitCR or NOT a clearance would be required for the folicwing according to Clearance Procedure. AP 00.

a Radioactive flu;d system.

b. 'jyst>m at 100 degrees-P.

c. S y s t e.n g r e a t e than 100 ps

c. Ground straps involving electr-ical equipment. ,

i y

e.

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

1.__ AEWlNLSIRSI1'IC_ERQCCQU.RE2 _QQMQLILQUE._ANQ_LLM1TallQN1 PACE 29 OUESTION 8.04 (2.00)

c. Who, as a MINIMUM. may give the required permasston to take the reactor critical for a normal startup from hot standby / recovery from a reactor trtp with the cause for the trip known and corrected? (1.0)

J Op:r-etiusia Me n egirr-fCp e r ; i t-ng-supe tv t-eo r ,- A 2 opa uta ng-Supe-r v-t-ewn-/-64w-I-t-Techtt w a i Adviser "--

3_ GhIft T orgmanJOp+r+t-t ng--Gu pa g.y Lao g _

i Ope r a t-a r,g O nperns e f 464H-f-t-FmHmta rA

b. What TWO people must always be nottited of a reactor trip by the Shift Foreman, as stated in AI 1. "Operat1ons-Conduct of Operations? (1.0)

OUESTION 8.05 (2.00) indicate whether the f o l I o w i ri g statements are TRUC or TALSE concernang Clearances, procedure 1-AP-20

a. Eq tt i pme n t in the Machtna Shop is exempt from the clearance procedure.

b. Red tags are uttitzed where special authorsty is required to operate equtpment c Clearances may be t r a n s f ee r r e d from one clearance holder to another.

with :ih I f t foreman c o n ; <- 1. t d Work may be pertormed under a "Ghift foreman" Clearance, QUESTION 3.06 C1 S0)

1. 3 a t fil R E E r e a s o n s / b a .t e s why sntrc: rods must be ma:ntaaned above the Tech. Spec. mantmum insertion amtt during pawer operatson.

i l

l t***** CATECORY 08 CONTINUED ON NEXT PAGE *****)

as__AEMINLSIRAILYE_ERQQEQMREE _CONQLILQNS _ANk_LIMLIalloNE PAGE 30 QUESTION 8.07 (1.00)

Whtch one of the following always requires a Temporary Bypass, Jumper or Ware Removal, according to AP-24?

a. Electrical equipment such as motor leads transmitter leads, or relays which can be de-energized.

b. A Temporary bypass, jumper, or wtre removal for an operable safety system.

c. Power cables from receptacles to temporary or portable equipment.

d. Pipe caps installed to stop remote manual drain valve leakage.

QUESTION 8.08 (1.00)

Which of the following is NOT a requirement for electrreal work on equipment ~that must remain energized for trouble-shooting and repairing of. control circutts? (1.0)

a. Permission obtained from cognizent supervisor

b. Permisston obtained from the Shift foreman.

c. Two persons are assigned to perform the task.

d. Gafety precauttons/inctruction; given to worker (sJ QUESTION 3.09 (3.00)

The concentratton of the boric acid solutton in the Retueling Water Storage Tank (RWST) shall be verifled once per 7 days in accordance wtth Technical 3pectfteation 3.S.4. The chemist sampled the RWGT on the folicwing schedule. (All samples taken at 1200 hour0.0139 days 0.333 hours 0.00198 weeks 4.566e-4 months sJ Oct i Oct 3 Oct 16 Oct 24 - Oct 31

a. EXPLAIN why survettlance time interval requtrements were or ,

were not exceeded on Oct 16. -(1.S)

b. EXPLAIN why surveillance time inte: val requirements were or were not exceeded on Oct 24 (1.5)

(***=* CATECORY 08 CONTINUED ON NEXT PAGE *****)

i a.__ADMLN13IR&ILVE_EROCCQuREa._CONQlIlQHam_&MQ_LLMLIAIlQUE PAGE 31

-OUESTION 8.10 (2.00)

What are'the TilREE provisions that must be met before a temporary change can be made to an approved operating procedure, according to Technical

- Spectftcations?

QUESTION 8.11 (2.50)

The following concern the Plant Emergency Procedures

a. State the title of the person who is responsable for the inittation of the INITIAL emergency action. Who ts responsible tf this person is unavailable or incapacitated? (1,0)

b. Once implemented, when may the inattal emergency action procedure be terminated? (TVO conditions required) (0.5)

c. List the TOUR types of emergencies AND state which of the four require activatton of the Techntcal Support Center. (0.S)

d. TRUE or FALSE?

If an action level for a higher classifteation was exceeded but currently has been resolved, the higher class 1fteation should be reportod and declared to the state, county and NRC. (0.5)

QUESTION 0.12 (1.00)

-According to Technical SpectLtcations, if a safety Itmtt is exceeded the NRC Operations Center shall be nottfted within _____.

a-. 1S minutos

b. I hour

c. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months

d. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

s l'=*** CATEGORY 03 CONTINUED ON NEXT PAGE *****)

am__AEMINISIRAI1YE_ERQQEQuRES _CQURLIlOHam_ANQ_ LIM 11&ILQM1 PAGE 32 QUESTION 8.13 (1,50)

O. The indicated AfD shall be considered outside of its target band when or more operable excore channels are indicating the AFD outside the target band. (0.S)

b. Which of the following statements concerning the AFD requirements is correct? (1.0)

a. Above 90%, within 30 minutes of going outside the target band: either restore indicated AfD to within the target band or reduce power to less than 90%.

b. If the axial flux difference a l a r m .* are out of service, the axial flux difference shall be logged every hour for the first 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and half-hourly thereafter until the alarms are returned to operable.

l c. Delow 15% power, penalty points are accumulated at one

, half point for every minute outstde the target band.

l

d. Power level shall not be increased above 15% unless the AfD is within the target band.

l

, OUEGTION 0.14 (2.00) l-Indicate Wii ETi!ER or NOT the tollowing conditions ItEOUIRC that the plant be

(

in flo t Gtandby within one hour ASSUME Mode 1 operatton.

I

a. W:th one cold leg injection valve fatled in the closed posttion.

b. W1th an accumulator isolation valve closec.

c. W tb RCG pressure having exceeded 2775 psig.

d. Without p r i nia r y containment integttty i

l

(***** CATECORY 03 CONTINUED ON NEXT PAGE *****)

i

Lo__ ADM LN L SIR &I LV E _REOC EQ'lRE E s_CONQLI LON S ._aNQ_ L AM LI&ILQN 2 PAGE 33 QUEJTION 8.1S (1.00)

Which of the following statements concerning Shutdown Margin (SDM) considerations is correct?

a. With Tavg less than 200 degrees, the SDM requirements are increased because of the possibility of a positive MTC.

b. The most restrtotive condttion for GDM requirements occur at EOL, with Tavg at no load temperature, and is associated with a rod ejection accident

c. When in Mode 2 with ketf less than 1.0, adequate SDM is ensured by vertfying the predicted eratacal rod posatton is above the rod insertion limits.

d. If one rod is known to be parttally inserted and untrtppable dn increased aIloWance for the entire rod worth shall be made to the SDM requirements.

QUESTION 8.16 ( .50)

TRUE or PALSE?

An operator may never deviate from a procedure in the Plant Operating Manual without a Temporary or Permanent procedure change.

QUESTION 8.17 (1.00)

Golect from column B the color of the badge which correctly identsftes the personnel positions listed in column A. (for example 6. f)

COL'IMN A COLUMN D 1 Operating Supervisor a. Red C. Ghtft't'oreman b. Orange l

3. Senior Control Operator c. Yellow

4. Control Operator. d. Green S. Shtft Technical-Advisor e. Blue ,

(*****'CATECORY 08 CONTINUED ON NEXT PAGE *****)

+

IL._ _ AQMIN1EIR AI1Y C _ ERQC EQu R E E m_ CON Q1I1CN E._ ANQ _ LIM LI AI1CN E PAGE 34 QUESTION 8.18 (l.50)

The following concern informatton found in OMM-001. Operations - Conduct of Operations procedure. Place answers on your answer paper.

a. When performing valva lineups on MANUAL valves their position will be verified b y __ __ ____ O R _ _ __ _ _ _ _ . (A a h) (0.S)

b. To check a MANUAL valve OPEN the operator should (0.S)

e. VaIves whach are Ti!ROTTLCD and NOT 1ocked sha11 have their position checked by_____. (0,5)

QUESTION 8.19 ( .50)

TRUC or FALSC?

! Procedures. Operations Work Permits, Operations Survestlance Tests, etc.,

on vital and/or sonsttive plant equipment require double vertftcation of the. equipment status. Double verifteation will consist of two indepen-dont veritications by quaitfted individuals.

QUESTION 8.20 (l.00)

During the performance of a ;urvet!!ance test it becomes necessary to delete seve al steps in the p r te c e d u r e . The Shitt foreman wti1 N/A the appiopttate 3teps 1n the anit a1 b1ock then he wti1 ______ AND ______.

Please be spectfac. (NOTE: btanxs don't necessarily mean one word answers)

~

h the<.% e m m - r' ' 1 ogg4 % g g ,,

-=, ,- M gz=1 . ,u , -

i

(***** CND Or CATCCORY 08 *****)

(************* CND OF EXAMINATION ***************)

EQUATIOil 5HEET f = .na v = s/t Cycle efficiency = (. 1et'nork cut)/(Energy in) 2 w = mg s = V ,t

1/2 at E = me- - v' 2 A = U1 A = A,a XE = 1/2 mv 3 = (Vf - V3 )/t PE = mgn Vf = V, + at 4 = a/t t= m2/t1/2 = 0.693/t1/2 5 e H

W ,1, M g9 2 37z y , , ,p A= 4 ((t 1/2I

l*b)3 d = 931 sn -

m=V avAo -m

[=Ieo Q = mCpat 6 = UA A T I = I ae"#

Pwr = Wyah I = I,10~*/ M TYL = 1.3/u P = Po lo sur(t) HVL = -0.593/u P = Po e*/

SUR = 25.06/T SCR = 5/(1 - X,g)

C?x = 5/(1 - X,ffx) suR 2sa/t* + (s - ajr CR3 (1 - X,g3) = CR2 Cl -

w 2)

T = ( t*/o ) + ((s - o '/ Ia ] M = 1/(1 - X,g) = CR /CR 3 3 7 = t/(o - 3) M = (1 - Xeffo)/II ~ #effl)

T = (3 - 2)/(Ia) SOM = (1 - K,g)/K,f,-

t- = 10 g seconos a = (X ,ff-1)/Xg = .X ,g/K ,g -I I = 0.1 seconds a = ((t*/(T K,g)] + (I,g/(1 + IT)]

Ij d3 = !,d2 P = (uV)/(3 x 1010) I d) 2 =~Id. ., 2 ,

N R/hr = (0.5 CE)/d'(metars)

R/hr = 6 CE/d2 (feet) ,

Water Parameters Miscellaneour Conversions 1 gal. = 8.345 lem. 1 curia = 3.7 x 1010eas 1 ga]. = 3.78 litars 1 kg = 2.21 lem 1 ftd = 7.48 gal. 1no=2.54x103Stu/hr Oensity = 62.4 lbqi/ft 3 1 = = 3.41 x 100 Stu/hr Density = 1 gm/c:9 lin = 2.54 cm Heat of vacorization = 970 Stu/lem *F = 9/5'C + 32 Heat of fusion = 144 Stu/lem *C = 5/9 (*F-32) 1 Atm = 14.7 psi = 29.9 in. Hg. 1 BTU = 778 ft-lbf I ft. H O = 0.4335 lbf/in, 2

l

r, f'

5 __IHEQR1_QE_MECLEAR_EQWER_ELAMI_QEEEAI1QM._ ELE 1QE._ANQ PAGE 35 IHERMQQ1NEMICE

! ANSWERS -- S!!EARON ll ARR I S 1 -8S/11/04-ISAKSEN, P.

k Mk ANSWER 5.01 (1.50)~

j a. 1 (Increase) (1.0)

b. 1770 pcm. 10,5)

-REFERENCE l SilNPP Technical Spectftcattons 3.1.1.1; RT-LP-3.13, p 7-9.

l ANSWER 5.02 (2.00)

-Rod to group alignment.C+/-12 steps)

I -Oroups. sequenced and overlapped.

-Rod Insertion Ltmlts maintained.

-Axtal flux Diflerence limits maintained. 10.S. eachl REFERENCE SilNPP Te chni ca l Specifications. D 3/4 p 2 -2 to 2-4.

l ANSWER S.03 (2.50)

2. GAME

b. fil GilER

c. FilCllER

d. SAME e'. LOWER (0.5 tachl (2.5)

REFERENCE Sli N P P RT-LP-3.13, p 10-15 and RT TP-262.

l .

. . = _ . . -

. im__IMEQR1_QE_NMCLEAE_EQWER_EEANI_QEERAI1QNu_EkMlEE&_&MQ PA'GE 36 IHERMQQ1NAMICE ANSWERS --

SHEARON HARRIS'l -85/11/04-ISAKSEN, P.

ANSWER' S.04 (2.00)

O. Decreases (0.2S] Pu 239 concentration increases (while U 235

. concentration decreases) [0.751. (1.0)

b. Larger SUR. (1.0)

REFERENCE SHNPP RT-LP-1.6, p 23,24.

ANSWER S.05 (1.50)

a. A i b. D

c. Same rod height (0.5 each)

REFERENCE

SHNPP RT-LP-1.6, p39-46.

ANSWER 5.06 (1.00)

a. True'

b. True to 5 eachl

' REFERENCE S!!NP P RT-LP I'.9. p 19 RT L F' : 10. p 11 16,00-22.

4

- ANSWER S,.07 ( 1 . 0 0-)

b REFERENCE SHNPP RT-LP-1.4. RT-LP-1 G p 0; 24 1

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

ii__INEQR1_QE_ NUCLEAR _EQWER_ELaMI_QEEEAILQM _ELulRS&_ANQ' PAGE 37 ItiERMQQ1NAMLC3.

ANSWERS -- SHEARON HARRIS 1 -85/11/04- ISAKSEN, P.

1 ANSWER 5.08 (2.00)

.a. ~1. lii g he r fission yield.

2.

Larger-(thermal) absorbiton cross section (1.0)

b. Disagree [0.41 Equilibrium Gm concentration is not power dependent.(0.61 (1.0)

. -REFERENCE SHNPP-RT-LP-1 11, p 9-21.

- ANSWER 5.09 (1.00) b ,

RETERENCE Westinghouse. Reactor Physics, pp. 1-S.12 25 and 27

.SilNPP RT-LP-1.10, p 14,15. +

ANSWER 5.10 . (1.00) b RETERENCE.

Westingnouse Reactor Phy: tes, pp. 1-5.26 s 07 SilN P P RT-LP-1 10. p 13 15.

4 ANSWER S.11 (1,00) b

. REFERENCE Mestinghouse Reactor Phystes, pp. 1-4.19 24. ,

SilNPP RT-LP-1.7. l 1

l

. im__INEQR1_QE_NECLEAR_EQWER_ELAMI_QEERAI1QN._ELu1Q1 _ANQ PAGE 38 IliERMQQ1NAMICE ANSWERS -- SHEARON llARRIS 1 -85/11/04- ISAKSEN, P.

ANSWER 5.12 (1.00) d REFERENCE Westinghouse Reactor Physics. Section I-5. MTC and Power Defect SilNPP.RT-LP-1.6. p 36-41.

ANSWER 5.13 (1.00) c REFERENCE

-Wastinghouse Reactor Phystes, pp. !-S.2 - 16 SilNPP;fT-LP-1.10, p 9~12.

' ANSWER S.14 (1.S0)

. a. Bottom of the core. (0.5)

b. 1. Decrease

2. Increase

, 3. Increase (0.33 each) (1.0)

-REFERENCE GPNT Vol Ill, Ch. 2. Sect E, p. 2-164 thru 167.

SilNPP !!T- LP - 1 2, p 10 14.

2 ANSWER. S 15 (2.50)

s. t. REMAIN Tile SAME

- 2. DECREASE

1. INCREASE

4. DECREASE

b. 'Superheated. (0.S eachl

. REFERENCE Steam Tables S ilN P P FT-LP-1.1. p 32-34.

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

Lir__IUCQEl_QE_NECLE6d_EQWER_ELAMI_QEER&ILQN._ELELQS _ANQ PAGE 39 THERMQQ1NAMLCE-ANSWERS -- SHEARON HARRIS 1 -8S/11/04-ISAKSEN, P.

l

~ ANSWER 5.16 (1.00) b REFERENCE SilNP P TF-LP-1.1, p 27-30.

ANSWER 5.17 (1.50)

a. True

b. False

'c .ralse (0.5 each]

' REFERENCE Westinghouse Thermal Sctence. Chapter 10. Pp. 41-49 S!!N P P rr-LP-1 1, p 21-23, 27-30.

-ANSWER 5.18 (1.00) a.

REFERENCE ,

SHNPP Thermo-LP-1 1 and steam tables KA002/000,KS,01,3.1 Cook

Westinghouse Thermal Science. Chapter-2.Pp 63-70,79. /020.KS.06.3.4 ANSWER 5.19 11:00) t C p r C(

REFERENCE Ceneral Physics, !!Trr -~rlund riow Applications for Systems and Components.

-SHNPP T&AA-LP-1 19.

1

,s ~.

i l

I l

l- )

.1.__ISEQR1_QE_ NUCLEAR _EQWER_ELAMI_QEERAIlQNm_ELVlRS _ANQ PAGE 40 IHERMQQ1NAMICE ANSWERS - SHEARON !!ARR I S 1 -85/11/04- ISAKSEN. P.

ANSWER 5.20- (1.00) b ( 10.% W '*b REFERENCE V C S . IIT T T , p. 179 GHNPP Thermo-LP-1.3, p 11-16.

ANSWER 5.21 (1.00) d

^ REFERENCE SHNPP TF-LP-1 1 Section 2.2. p 6-10.

4 ANSWER 5 22 (1 00)

C REFERENCE

'Gream Tables I

I

E._ EEANI_2121EME_REclGN _CONIRQLs_bEQ_LNEIREMENIAllON PACE 41 ANSWERS -- S!!EARON li ARR I S 1 -85/11/04- ISAKSEN. P.

ANSWER 6.01 (1.00) b REFERENCE SHNPP E S P A S -II O - 1 . 0 , p 7.

ANSWER 6.02 (1.00)

a. Yes

b. No

c. No

d. Yes [0.25 each)

RCfERENCE SilNP P ESTAS-HO-1.0. p 10.

ANSWER 6.03 (2.00) '

a. P 4 (reactor trip brester: pen > and Low Tavg .564-f) (1.0)

L " wuM A**s *( . ;- += . . >. x. ? . mg -

L. 3 (1.0)

REFERENCE S!!N P P CS T A S - !!O 1.0, p 4,10..!

AMSUCR 6.04 (1.00';

,: +

REFERENCE ENP. Excore Nuclear I n s t r un.e t. f a t ton S y ; t e:n UDN. LP Excore Instrumentatier, pp. 10, 10, & 14 S!!M P P RPS !!O 1 9 p 1.

E2__EkANT_S13IEMS_QE1LQN._CQMIRQL _ANQ_1HEIREMENIAI1QM PAGE 42 ANSWERS.-- SilEARON li ARR I S 1 -85/11/04- ISAKSEN. P.

' ANSWER 6.05 (1.00)

4. DECREASE

b. Z;.;a ;;v i n t. s am t."- LWC EMSG

c. DECREASE

d. INCREASE [0.25 each)

REFERENCE THP, Tavg, Delta T, and Pimp, pp. 16 & 17 Surry, instrumentation Manual. Sect 9, p. IV-5.5

'WBN. LP - Reactor Coolant Temperature Instrumentation, p. 8 SHNPP RPS-Ilo-1.0, p.14,15.

ANSWER 6.06 (2.00)

a. True

b. False

c. True

d. True (0.5 each)

REFERENCE Gl!NPP SCO -HO 1.0, p 10; RPS !!O - 1. 0, p 9,18 ANSWER 6.07 (2.001

1. S (Cll)

b. 6 (C16)

c. ~ 4 (C4)

d. 1 (Cl) (0.5 each)

REFCRENCE SilN P P R P G - ilO - 1. 0 , p 2-3 . 2 4 .

l

Jit__Eh&MIi21SIEME_QE2LGN._CONIRQL._ANQ LNEIREMENIAILON PAGE 43 ANSWERS > S!!EARON llARRIS 1 -05/11/04- lSAKSEN. P.

~ ANSWER 6.08 (3.00)

a. 1. True

2. T.v. TN

3. raise [0.5 each) b, 1. Yes-2 No

3. Yes 4 Yes S. No~ [0.3 each)

REFERENCE SliN P P S ACP- L P - 1. 0 . p 11.13.

ANSWER 6.09 (1.00) a

. REFERENCE

SliN P P 120V'UPS-HO-1,0. f19 UPS-TP-1.0.

ANSWER 6.10 ( 1 .-0 0 )

b REFERENCE

' S HN P P ' P Z R PC 110- 1. 0 . p 25.

ANSWER 6.11 (0.00)

J .' l o

b. No

c. Yes

'd; ; ; ' C.' " -> 60 (0.5 each)

REFERENCE SilNPP PZRPC-HO-1.0. p 22. f19 PZRPC-TP-5.0.

Eu__Ek&MI_SISTEME_QCELGM _CQMIRQL._ANQ_1NSIREMENIAILQN PAGE 44 ANSWERS -- S!!EARON H ARR I S 1 -85/11/04- ISAKSEN, P.

ANSWER 6.12 . (1.00)

a. Yes

b. No

c. Yes d Yes (0.2S each]

REFERENCE' SHNPP P Z R L C -I! O - 1 . 0 , p 19.

ANSWER 6.13 (1.00) 2 (OPEN)

REFERENCE SHNPP RCT EMP - IlO - 1. 0 . p 21.

-ANSWER 6.14 (1.50)

1. OT -De l t aT

2. OP-DeltaT

3. Low Tavg-trWI with reactor trip)

4. Low-Low Tavg-(Steam dump block) [3 required. 0.5 eachl REFERENCE

.SHNPP RCTEMP-liO-t.0, p 10.

4 A N S t! E R 6.15 (2.00)

'l b 2 a

3. d

4. d to.S each)

REFERENCE O SHNPP SDCS-HO-1.0, p S-11, fig. RPS-TP-21.

- ft,"_ _ E L A MI_11 EIEM E _ Q E E LGM._CQUIRQL ._ A NQ_1N EIREM EMI AI LQN PACE 45

. ANSWERS -- GHEARON HARRIS 1 -85/11/04-13AKSEN, P.

1

' ANSWER 6.16 (2.00) ;

a. 2

-b. ~4 (1.0 each)

REFERENCE SilNPP SCWLC -I!O- t . 0. p 9-13,1S 4

ANSWER 6.17 (1.50) 4 1 Phase overcurrent tr p/er c' # '=# M

2. Low suction pressure trip

, J. Low tube oil-pressure 10.S each)

REFERENCE S!!N P P CFW-!!O - ! . 0, p 38.

ANGWER 6.18 (1.50)

a. RWGT Low-Low level and GIS present. (0.S) b Prevent inadvertant c o .'.n e c t i o n of RCS to RWST'AND CVCS.C## (1.0) tprevent overpre:sure of Rl!R system)(c.s.w ,y g y 3%)

1.

REFERCNCE 311N P P RilR G - 110 ~ 1. 0 . p-13.16.

1 ANSWER 6 J 19- >: 1.50) 3 4 (0.S) i b. 1 Prevent loss of RCS forced flow.

. Prevent /1tmlt RCP overspeed.( # (1.0) 4 % ,e,. .

r)

RETERENCE SilNPP GEN-l!O- 1. 0, p 14.15.

E 2__ E L ANI_ S Y SIEM S _Q E S 1Q tL._CQ tlIRQ L._ a tit _.L M SIEEM ENI AI 1QN PAGE 46 ANSWERS -- SilE ARON li ARR I S 1 -85/11/04- ISAKSEN, P.

ANSWER 6.20 C1.00) b.

REFERENCE StiNP P AT S-IIO - 1. 0 , p 7.

'li__ESQCCQURC1_:_NQEMAL&_ARNQRM&L _EMERGENC1_ANQ PAGE 47 RAQLCLQGLC&L_CQHIRQL ANSWER'S -- 'S!!EARON llARR I S 1 -85/11/04-1 SAKSEN, P.

/

' ANSWER. 7,01 (1.00)

(.a.s,4{ d M W " \

-07 " ' a shut PORV isolation valves (1RC-117.113) one at a time and vertfy clarm (Low Temp & Pzr Relief isol Viv A,B) does'not alarm (and reopen velves). M* -T)

REFERENCE

-SIINPP CP-002, p 22.

ANSWER ?.02 (1.50)

a. '500 500

b. 250

-50

c. 2

d. 10 [0.25 each)

-RETERENCE

-SliNPP GP-002, p 7,8s and 0P 004 p 0.

' ANS*f!ER 7.03 (l.00)

C REFERENCE SHNPP CP-005,-p 6.

ANSWER 7.C4 C1.S0'>

a. 2 (wien cui

b. 4, . .1. C 9 44+ >'; [0.5 each1 REFERENCL S!!NPP CP 00 5, p 6.

i l

l l

l.

t I

li__ERQCCQUEE1_ _NQEM&k _&aNQEM&L&_EMERQENQ1_ANQ PACE 48 R&QLQLQQLCAL_CQNIRQL ANSWERS --

SHEARON HARRIS 1 -85/11/04- ISAKSEN, P.

ANSWER 7.05 (2.00)

a. To prevent inadvertant reactor trtps due to turbine trtp signal (1.0)

b. Curve book (turbine speed hold recommendations c h a r t ) ./ Tee.e m wve. ( 0. 5 )

c. 15 (0.5)

REFERENCE SilNPP GP-00 5, p 11,12.20.

ANSWER 7.06 (1.50)

a. Provides assurance'that the mass addttton pressure can be retteved by a SINGLE PORV. (1.0)

b. LThe motor circuit breakers are secured in the open posatton. (0.5)

L RA tt uo c~n')

-REFERENCE S!!NPP TS 3.1.2.4 and bases 3/4 1.* -

ANSt!ER 7.07 (2.50)

a. 4 (1.0)

b. 2- (1.0) .

I e, rafe reactor -or.ditIons a r +> e :; t a b l i s h e 1. ' i s ai 444, f* G *A*M CD 5)

RETERENCC SttNPP AOP 002, p 3-S.

ANSWER 7.08 (1.00) ,

1. b

2. a 3 d

4. c (0.25 eachl

1,__ERQCEQuREE___NQRMAL _ABNQRMAL. EMERGENC1_AND PAGE 49 RAQLQLOGICAL_CONIROL ANSWERS -- SHEARON liARRIS 1 -8S/11/04-ISAKSEN, P.

REFERENCE e SHNPP AOP-004, p 24-26.

ANSWER 7.09 C1.00)

G RETERENCE SHNPP AOP-010, p 5.

_ ANSWER 7.10 (2.00)

-secure _CCW pumps

-trip reactordand turbine)

-stop RCP's (within 10 mtn or bearing temp reaching 190-F)

-tsolate leaking component (s)

-open 1 DW - 1 5 (_ /#=-A. - A - q ')

.(msantain seal injection flow to RCP's) [0.4 each)

REFERENCE-SilN P P AOP-014. p 4.

ANSWER 7.11 (1.00) c REFERENCE SilNPP AOP-016, p 5.6.

ANSWER 7.10 (2.00J a Closed

b. Not affected

.c. ' Closed

d. Open

e. Closed (0.4 each)

REFERENCE SHNPP AOP-017. p4,7.

1s__EROCEQUEEE_ _ NORMAL _ARNQRMAL _EMERQENC1_ANQ PAGE S0 l RAQ10LQGLCAL_CQNIRQL ANSWERS --

SHEARON liARR I S 1 -85/11/04- ISAKSEN. P.

1 I.

i

! . ANSWER 7.13 (1.00) l

a. 188

b. 25 [0.S cachl l

REFERENCE j --

SilNPP AOP-018, p 4,12.

ANSWER 7.14 (1.00) l

a. Plant Manager l-

b. Indicates an event is being recorded. [0.5 each)

REFERENCE SilN P P AOP 001, p 4.

I L

i l

l ANSWER 7.15 -(1.50) r e.w .

! a. Reduce' reactor power by 2 5 1'y a t max r a t e'g,y ( 0 . S 1 (c.Q

b. Prevents the release of activity in the event of 9 SGTR, since saturatton pressure is less than the itft pressutb**El an atmosph-eric rettet valve. [1.01 (c. wi l REFERENCE SHtlPP AOP-030. p 3. TS bases 3/4.4.8 l

ANSWER- 7.16 (1.00) l d '

I RCTERENCE SliNPP TS table 3.3-1.

l ANSWER 7 17 (1.00) i d l

l t

l

li__ERQCEQUEEE_ _MQEMAL _ABMQEMAL._EMERGENCI_ANQ PAGE 51 R&Q10LQGLCAL_COMIRQL ANSWERS -- SHEARON' HARRIS 1 -85/11/04- ISAKSEN, P.

REFERENCE SHNPP AP-503, p 13.

ANSWER 7.18 (1.50)

a. 4 (2.5)

b. 3 (7)

c. 2'(15.75) 10.5 each]

RETERENCE.

SHNPP RP-LP-1.3, p 10.

ANSWER 7.19 (1.00)

C REFERENCE Surry, CP-1.00.. foldout Page S11NP P COP-EPP-Toldout'page A ANOWCR :7.20 (1.00)

C-REFERCflCE Surgy. EP 0.00. Toldout, p I ',

. SilN P P EOP-EPP-foldout C.

ANSWER 7.21 ( l.003 d'

REFERENCE S HilP P COP TRP-S 1, p 3 tt ANSWER 7.00 (1.00) 1

1.a__ESQCEQUREE_ _NQEMAL._&RNQRMAL _EMERGENC1_ANQ PACE S2 R&Q10LQQ1 CAL _ CONTROL ANSWERS -- SHEARON HARR!S'1 -85/11/04-1 SAKSEN. P.

R::TERENCE.

SilNPP EOP-FRP-P.2, p 4.

ANSWER -7 23 -( 1 .-0 0 )

-C REFERENCE

' SilNP P EOP -EP P - 16, p 4.

M M

i R __AEMLNLEIRAILVE_ERQCEQuREL._CONQLILONS._ANQ_1.1MLIAILQNE PAGE S3

. ANSWERS --

SilEARON. !! ARR I S 1 -8S/11/04-ISAKSEN. P.

f ANSWER 8.01 (2.00)

1. MTC within its analyzed range.

'2; Protective instrumentation-is within its normal operating range.

3. PZR is capable of betng operable (with a steam bubble).

~

4 Reactor. pressure vessel above RTNDT temperature. (0.5 each)

'~

REFERENCE SilNP P - TS .- 03/4 1 2.

ANSWER 8.02 (1.00) b - ~ 0ts t,s

'REPCRENCE S!!NPP AP -019. p S.

ANSWER 8.03 (2.00)

a. Yes

b. No

c. -Yes

d. No -(0.5 eaertl RtrLRENCE

- SilN P P 1 .AP-20, p 4 7. ,

ANSWER 8 04 (2.00) 3, p EM

b. STA and Sh;ft Operating rupervisor !1.0 eachl

'(se : _=* % =l m -.+.v ..- c.r;)

RCPERCNCE

'GilNPP GP-03, p 17; GP-004, p 154 CW!M 1. p 10.26.

. ,-j1: -1

,. g n

.. 11__ADM1H12IRAILVE_P.EQCCQMRES _CQNQ1TlQNE _ANQ_LLMLIAI1QN1 PACE 54

p ': ,, . ,) -

1(ANSWERS --~SHEARON IIARR1S 1. i

.1 ) -

-85'{11/04-1 SAKSEN. P.

^) .

\

w' -\ .\

.,j i

' ~\

y cy; e '=

} I -

1 ANGWER' 8.05l *

,(2.00)

~

i i i* 1

.o . True ., , ,s

'b . TaIse ~y.

c" ' ', T r u e '

d s. Falso LO.5 each)

.f.g

. REFERENCE s.

- Y'SHNPP'1-AP-20. p'540'.4l4 y -

, \c ANSWER ' '

8~06

. (1.50)- ,

^ '

%, 4

--s ' 1 ".

Maintat'n. acceptable power distribution limits.

, 2. Maintain adequate SDM.

[.j 3. Limit affects of rod mils, alignment (.A,e*4. .'p :* A.)

[0.S eachl REFERENCE SilNPP TS . B 3/4 1-J.

,'s,

' ANSWER. 8.07 ( 1. 0 0 ) N d

F ' REFERENCE ]*

SilNPP AP - 0 4. p'S-7.

3 3 A f1 S W E R U .9 8 ( 1:. 0 0 )

7 e

RCTURENCE q SIIMPP-AP-003, p 10.

a I

J' j, y

)

T

, 9 w_ . - - _ - - - - - - . - - _ _ _ - . - - - .

L__&IMdLNLSIE&ILVE_EEQCERURCE COMRLILQM1. AMD_LLMLIAIl0NS PAGE SS

-ANSWERS -- SIICARON llARR1S 1 8S/11/04-!SAKSEN. P

. ANSWER 8.09 (3.00) e, Interval requirement not exceeded (0.51. Etqht days does not exceed 1.2S times the spectfled interval (1.01 (1.5)

b. Interval requirement exceeded (0.51. The last 3 consecutive intervals exceed 3.25 times the specified interval (1.01. (1.S)

-REFERENCE SHNPP TS'. p. 3/4 0-2. 5-10.

-ANSWER 8.10 (2.00)

1. The intent of the procedure is not altered (0.S1.

2. The-change is approved by two members of the plant management staff.

at.least one holds a SRO license (1.01

3. The change is documented, reviewed, and approved within 14 days g of amplementation by the Plant General Manager (or the manager of W the functional area atfected) LO.Sl (2.0)

REFERENCE SilN P P TS. pt 17.

.ANSWCR .0.11 (O 50)

a. Shift l'o r ema n (O.51 Control Room Senior Control Operator (then roving SCO)- 10.Sl (1.0) b 1. The emergene/ te classitied and proper procedures implemented.

j Th+ off n c t r.u t c o nd i t a ts n is resulved.C O M .,A f d t0.5)

c. Unusual Event. Alert *, Site Emergercy*, General Emergency

t* indtcates TSC acttvsted7".c. q s w w a u.) (O.S}

d. False (0.5) 4 i REFERENCE SilNPP. PEP 101.p 4-S; 103 p 6. 0.3 2.5 p 1 i

i

a s_ _ AL-MIN L 2T R AILV C _ E ROC E R'lR C 2 _CO NQ1I1QH 2 m_ A N Q..L LM LI&ILQNS PAGE 56 ANGWERG - Gil E A RON !! AR R 10 1 -85/11/04- ISAKGEN. P.

ANGWER 8.12 (1.00) b REFERENCE SHNPP TG p 6-16.

ANSWER 8.13 (1.50)

a. 2 CO.S)

b. b (1.0)

REFERENCE Gl! N P P , TG 3/4 2.1 ANCWER 3.14 (2.00)

a. NO

b. F10

YCC

d. NO LO.S .i REEFRENCE S!!NPP. T:1, pp. 2-1, 2/4 S : - & 61 ANSWER 8.16 (1 00)

REFEPEtiCE GHNPP, TG. pp. 3/4 1 1 and ; , , 1 ANGWER 8.16 C SU) raise REFERENCE 01-IN P P AP 002, p 21

' l a_AEMLN 12IR AILV.C_ ERQC EQuar.1 _COMQ LI LQM2._ANQ_ L LM LI AI LQM E PACE S7' I

ANSWERS -- SilE ARON llARRIS 1 -8S/11/04-ISAKSEN. P.

ANSWER 8.17 (1.00) i e b[)

'2. a(O

3. b(s0

~4. e (N

5. d (f.) 10.2 eachl REFERENCE GilN P P CMM- 0 01, p 23.

. ANSWER 8.18 (1.50)

a. turning in the closed postiton or by stem position Indication.

(c.I f e.O

b. -turn the valve at least 1/4 turn shut then return to oraginal positionfo.1) L A. - . ')

c. -means' determined by Shift F o r ema n (cr eAA A *

[0.5 eachl I6 q : : *- + ; _ 6 4. h h as &

~

d M- %,so)

-REFERENCE SIINPP OMM-001, p 37.

ANSWER 8.19 ( SO>

I True RCFERENCE SHNPP OMM 001, p 33.

ANSWER 8.20 (1.00) intttal in the lett hand naa r g i n cn t;p of the proc + dure step number (0.51 s.zr; wr1te a brief statement in the comments section explaining ^

the reason for the deletto;N (0.51 Le* LC REFERENCE SHNPP OMM-007. p 8

- ___ <- _ _ _ _ _ _ _ . _ _ _ _ _ _ - _ _ _ _ . _ _ _ _ - . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . - _m__-__________________-___..______..__.-.___._.-__m . _ - _ . _ _ _ _ _ _ _ _ . - _

ML20140C694

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