ML20196L522

Exam Rept 50-498/OL-88-01 on 880516-23.Exam results:16 of 17 Candidates Passed Exam & Issued Appropriate License

ML20196L522
Person / Time
Site:	South Texas
Issue date:	06/27/1988
From:	Mccrory S, Pellet J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20196L519	List: ML20196L517 ML20196L522
References
50-498-OL-88-01, 50-498-OL-88-1, NUDOCS 8807070560
Download: ML20196L522 (59)

Text

--

APPENDIX U.S. NUCLEAR REGULATORY COMMISSION REGION IV Operator Licensing Exam Report: 50-498/0L88-01 Operating License: NPF-76 Docket No: 50-498 f

Licensee: Houston Lighting & Power Company P.O. Box 1700 Houston, Texas 77001 Facility Name: South Texas Project Electric Generating Station Examination at: South Texas Project Electric Generating Station l

Chief Exami  : /o u 47V\ [ 2.7 d8 L.[Mc r Leaf Examiner, Da'te erator icensing Section Division of Reactor Safety Approved by: .

6 7 88

. L{. Pf let, Chief, Date Operatot Licensing Section Division of Reactor Safety Summary NRC Administered Examinations Conducted During the Week of May 16-23, 1988 (Report 50-498/0L88-01)

NRC administered examinations to seventeen (17) reactor operator applicants.

Sixteen (16) applicants passed all portions of the examination and have been issued the appropriate license.

[

2 OETAILS

1. Persons Examined SRO ft(1 Total License Examinations: Pass - 0 16 16 Fail - 0 1 1

2. Examiners S. L. McCrory, Chief Examiner R. Gruel T. Guilfoil F. Victor

3. Examination Report Performance results for individual examinees are not included in this report as it will be placed in the NRC Public Document Room and these results are not subject to public disclosure,

a. Examination Review Comment / Resolution In general, editorial comments or changes made during the examination, or subsequent grading reviews are not addressed by this resolution section. This section reflects resolution of substantive comments made by STP. The only comments addres:ed in this section are those which were not accepted for incorporation into the examination and/or answer key. Those connents accepted are incorporated into the master examination key which is included in this report. Comments may be paraphrased for brevity. The full text of the contents is attached.

(1.05) FTC is temperature dependent and et a constant temperature over core life it becomes more positive. Therefore, c is also correct.

Response: Reject. The observable FTC becomes more negative as the core ages. As the fuel ages the centerline temperature decreases due to changes in the heat transfer properties l in the fuel rod. Therefore, to operationally observe the effects of constant temperature would require increasing T-ave above operational limits.

(2.05b) The ventilation system normally requires that two trains of ECW be running while at power. Therefore, accept "2 trair,s running and one in standby at all times."

3 Response: Reject. This contradicts the requirements specified in the ECW reference and since both answers cannot be right the one referenced in the ECW lesson plan will be credited. This contradiction should be resolved by the facility licensee and appropriate changes made to training material and operating procedures.

(2.05c) The term "Train actuation" in the referenced lesson plan is vague. Therefore, accept "blowdown valve gets a close signal on safety train actuation."

Response: Reject. The references to ECW trains in parts a and b are sufficient to clarify the interpretation of "train actuation". It is the facility licensee responsibility to ensure that training material does not contain vague or ambiguous terminology.

(3.09c) Because of a typographical error in the question, the NRC should accept responses indicated.

(See facility licensee comments.)

Response: Reject. The typographical error was corrected during the time that the written examination was being taken. All applicants were made aware of the correction.

(4.15a) Since STP does not have approval of the submitted requalification program, these requirements were not covered in the licensed training. Therefore, it is requested that question be deleted or that credit be given for general discussion of requirements to stand shift watches and participate in the requalification program.

Response: The question was not deleted. However, partial credit was l given to the maximum appropriate extent. Regardless of the status of approval of programs directed at operator l proficiency, it is the responsibility of the individual l and the facility licensee to ensure that applicants for operating licenses are fully aware of the conditions for obtaining as well as maintaining a license in accordance l with 10 CFR 55.

(4.15b) Question implies that the nonlicensed individual is )

authorized in accordance with 10 CFR 55 to manipulate plant controls under instruction.

Response: This can neither be implied nor assumed by the licensed operator at any time. Recent violations of this requirement make it imperative that all operators fully understand the requirements of 10 CFR 55 in this area.

b. Site Visit Sumary l (1) At the end of the written examination administration, the facility licensee was provided a copy of the examination and answer key for the purpose of commenting on the examination

4 content validity. It was explained to the facility licensee that regional policy was to have examination results finalized within 30 days. Thus, a timely response was desired to attain this goal.

(2) At the conclusion of the site visit, the Chief Examiner met with facility licensee representatives to discuss aspects of the conduct of the examinations. The following personnel were present at the exit:

P. Appleby, STP G. Weldon, STP J. Constantin, STP S. McCrory, NRC (3) The following items were communicated to the facility licensee representatives as coments, observations, suggestions, or deficiencies:

i (a) Applicants appeared to be less confident when performing I routine system operations in the simulator than when f responding to abnormal or emergency conditions.

(b) The operational simulator malfunctions were barely adequate to administer simulator examinations to a large group of applicants. The reliability of the simulator was marginal. Facility licensee representatives responded by indicating that new simulator program disks had already been developed to eliminate the deficiencies noted during the simulator examinations. The programs were to be loaded and tested when the current examinations were l

completed.

(c) The material provided by the facility licensee for examination preparation was incomplete in some areas. This caused the examiners to request further material during examination preparation or to ignore those areas where r

information was insufficient for examination item development. Some material, such as P& ids, was virtually useless because it was illegible or poorly organized.

c. Generic Coments (1) A significant number of applicants had difficulty with the following questions in the written examination:

1.21 2.03c 2.06c 2.12 3.05 3.08a 3.09 3.10 4.02 4.03 4.04 4.11 4.12 4.13 4.15

5 NRC suggests that facility licensee training staff review these question areas to determine if revisions to the training program or material is warranted.

(2) There was a significant decrease in performance in category 4 compared to that demonstrated in categories 1-3. Since a number of questions dealt with routine plant operation and since simulator performance indicated a possible weakness in this area, there is indication of the need to evaluate increased training emphasis on normal plant and equipment

, evolutions.

(3) During the exit meeting and in telephone conversations, the facility licensee training staff was made aware of some of the inadequacies of the material provided to the NRC for examination preparation. The following specific departures from the requirements of Enclosure 1 to the scheduling confirmation letter, dated March 8,1988, were found in these material packages:

(a) The lesson plans were incomplete in that they did not contain the simplified drawings, tables, or figures csed in the classroom presentation. Some lesson plans pertaining to areas of operator responsibility were omitted from the package such as those for EDGs and AFW.

(b) Electrical single line diagrams were not provided and the P& ids were of such poor quality that they were virtually useless.

(c) The plant curves book was not provided in the initial package.

(d) System operating procedures were omitted for significant components such as RCPs.

(e) The shortcomings of the simulator were not adequately identified and initial conditions were poorly defined or missing.

(f) Operating procedures were not bound, marked, or indexed the same as those found in the control room. The E0Ps had pages reproduced upside down.

Similar discrepancies in future examination preparation packages may result in delay or cancellation of the scheduled examinations.

0 3 6

d. Master Examination and Answer Key Master copies of the STP license examinations and answer keys are attached. The facility licensee. comments which have been accepted are incorporated into the answer key,

e. Facility Examination Review Comments The facility licensee cvaments regarding the written examination are attached. Those comments which were not incorporated into the examination answer key have been addressed in the resolution section of this report.

f. Simulation Facility Fidelity Report All items in the attached Fidelity Report have been discussed with the facility simulator instructor personnel, t

4 l

l l

l i

i i

SIMULATION FACILITY FIDELITY REPORT Focility Licensse: Houston Lighting & Power Company Facility Licensee Docket No.: 50-498 Facility License No.: NPF-76 Operating Tests Administered At: South Texas Project (STP) Facility Operating Tests Given On: May 17-23, 1988 During the conduct of the simulator portion of the operating tests identified above, the following apparent performance and/or human factors discrepancies were observed:

1. The simulator program had a tendency to "lock up" during the evolutions.

There was no indication of a "lock up" at the control panels and parameter indications appeared normal. However, the computer was not updating parameter changes with respect to transients in progress.

During a routine boron concentration change for power ascension, a "lock up" resulted in a reactor trip when the simulator instructor noticed the condition and attempted to correct the condition. The trip was caused by a high reactivity rate resulting from the computer instantly jumping from the parameter values which existed at the time of "lock up" to the real time values which had been changing over the previous several minutes.

2. During a manual EDG startup and parallel evolution, the voltage adjustment controls for two EDGs did not function. The output breaker for one of the EDGs would not shut, even though all interlocks were apparently satisfied.

3. The simulator does not yet have the RM 11 Radiation Monitoring Display and Alarm system. As a result, operators are not alerted to radiation levels reaching setpoint values from any detectors having alarm functions. This tends to hinder early problem detection and event diagnosis.

4. Many of the basic instrument malfunctions for primary system parameters were not available. This significantly limited the scope of testing applicant response to instrument malfunctions. l 1

The facility licensee informed the examiners of numerous other deficiencies in  !

the simulator performance prior to scenario development or examination l administration. Additionally, the simulator has not yet been declared i certified in accordance with prescribed standards by the facility licensee. i Finally, facility licensee staff assured the Chief Examiner that new program disks were waiting to be loaded upon completion of the May 1980 examinations and that the deficiencies noted during examination conduct had been corrected 1 in the next program generation.

l 1

U. S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION FACILITY: _SOUIB_IEXeS_1-- - ___

REACTOR TYPE: _ EWE =WECd________________

DATE ADMINISTERED:_88ZQSZ16______= - --

EXAMINER: _UCCEDEY._S._____________ '

CANDIDATE: _ _ _ _ _ .___=- --

iblSIEUCI1OUS_IQ_CeUDIDGIE1 Use separate paper for the answers. Write answers on one side cnly.

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 six (6) hours after the examination starts.

X OF CATEGORY  % OF CANDIDATE'S CATEGORY

__UhLDE_ _IDIAL --_SCDBE___ _UaLDE__ - _ _ _ - - _ - CGIEBDEX___ . _ _ _ _

_25o00__ _25.00 ___- --

_____ 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW-

_25eQQ__ _25.QQ ____ - ________ 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS i

_25.QQ__ _25.QQ - - -

. . - - - 3. INSTRUMENTS AND CONTROLS

_25.QQ__ .25.QQ ___________ == 4. PROCEDURES - NORMAL ABNORMAL.

EMERGENCY AND RADIOLOGICAL CONTROL ,

i 1QQ.QQ__ -- . - _ _ _

-  % Totals Final Grade All work done on this examination i s my own. I have neither given nor received aid.

Candidate's Signature 1

i i

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

1 %._EE4NCIELES_DC_UUCLEGE_EDWEE_EL6HI_DEEEellDU. PAGE 2 IEEBtdDDXUatd1CS % BEGI_IBaUSEER_auD_ELUID_ELOW QUESTION 1.01 (1.00)

Which of the following statements conc *rning the power defect is correct?

a. The power defect is the difference between the measured power coefficient and the predicted power coefficient.

b. The power defect is more negative at beginning of core life because of the higher boron concentration.

c. The pecer defect increases the rod worth requirements necessary to maintain the desired shutdown margin folluaing a reactor trip.

d. The power defect necessitates the use of a ramped Tavg program to maintain an adequate Rea-tor Coolant. System subcooling margin.

l ANSWER 1.01 (1.00)

C (1.0)

REFERENCE EQB WEC4 GENERIC RT & HTFF STP LP LOT 101.09, EO-16 192004K108 ...(KA'S)

Q UE S~,10N 1.02 (1.00)

Choose the correct phrase to complete the sentence below.

I As the core aces, the ratio of PU239 atoms to U235 atoms increases. This l' chaaging r at i o causes the

a. delayed neutron fraction to increase.

l l

b. reactor period to decrease. I

c. Moderator Temperature Coefficient to become less negative,

d. Vold Coefficient to become less negative. l 1

1

1.__EHlUClELES_QE_ NUCLEAR _EDUER_2 leu 1_QEERallOM. PAGE 3 IHEEMODYuaMICS._UEaI_IEauSEER_auD_ELulD_ELOW ANSWER 1.02 (1.00)

B. (1.0)

REFERENCE EQB GENERIC WEC4 RT & HTFF STP LP LOT 101.08, EO-14 192003K106 ...(KA'S)

QUESTION 1.03 (1.00)

Which one of the following best describes the effect that DECREASING RCS Tave from 585 degrees F to 560 degrees F will have on MTC?

a. It becomes less negative because the rate of change in the density of water per degree temperature change is less at l owe r temperature which causes a lesser change in rate in resonance escape probability.

b. It becomes less negative because boron and water molecules are swept into the core as a result of the outsurge from the pressurizer, therefore, neutrons spend more time in the resonance region.

c. It becomes more negative because thermal utilization increases and resonance e sc ap e probability decreases,

d. It become s more negat i ve because as temperature i s l ow e r e d , the moderator becomes more dense, this increases probability of capture by the boron a t oms in the water.

ANSWER 1.03 (1.00)

A. (1.0)

REFERENCE EQB GENERIC WEC4 RT & HTFF STP LP LOT 101.09, EO-09 l 001000K526 192004K106 ...(KA'S) l l

I l

1 I

(***** CATEGORY 01 CONTINUED ON NEXT PAGE *****>

1s- EBlUCLELES DE UUCLEaB EDUEB EL6UI DEE66TLDUa PAGE 4

. IBEEUDDYuaulCSe BEaI IEGUSEER_AND ELUlD ELDU GUESTION 1.04 (1.00)

During a reactor startup from an initial Keff of .90, the first reactivity addi t i on caused courit rate to increase from 10 cps to 16 cps. The second reactivity addition caused count rate to increase from 16 cps to 32 cps.

Which DNE of the f ol l owi ng sta temen ts BEST de scr i be s the relationship between the first and second reactivity additions,

a. There is not enough data given to determine the relationship.

b. The second reactivity addition was the larger of the two.

c. The first and second reactivity additions were equal,

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

ANSWER 1.04 (1.00)

D. (1.0)

REFERENCE EGB GENERIC WEC4 RT & HTFF STP LP LOT 101.05 EO-19 192002K108 192002K112 192008K105 ...(KA'S) l l

QUESTION 1.05 (1.00)

Which ONE of the following statements most correctly describes the change I 1

in the Fuel and Moderator Temperature Coefficients (FTC and MTC) as the )

core ages? i l

a. FTC becomes more negative and MTC becomes more positive.

b. FTC becomes more negative and MTC becomes more negative.

c. FTC becomes more positive and MTC becomes more negative,

d. FTC becomes more positive and MTC becomes more positive.

1.__EB1UCIELES_DE_UUCLEaR_EDWEE_ELaMI.LEEEaIlONo PAGE 5 IBEEUDDXUat11CSo_BEAI_IEaMSEER_auD. ELUID_ELDW I

I ANSWER 1.05 (1.00) 1 S. (1.0)

REFERENCE ,

EQB GENERIC WEC4 RT & HTFF I' STP LP LOT 101.08. EO-21, LOT 101.09, EO-08 192004K107 ...(KA'S)

GUESTION 1.06 (1.00)

In the event of a rod ejection accident, which one of the f ol l ow i n g w i l l be i the first reactivity coefficient to insert negative reactivity? i

a. Moderator temperature coefficient,

b. Pressure coefficient.

c. Void coefficient.

d. Doppl.e coefficient.

ANSWER 1.06 (1.00)

D (1.0)

REFERENCE EQB GENERIC WEC4 RT & HTFF I STP LP LOT 101.08 T0-02 )

000001K118 ...(KA'S) l l

l l

l l

1

(***** CATEGORY 01 C ONT I NUE D ON N EXT PAG E * * * * * )

)

i I

l l

l

{

1.__EElMC1ELES_QE_UUCLEeE_EQUER_ELeNI_DEEReIlDN6 'PAGE 6 IBEEMODYueMICSo_MEeI_IEauSEER_auD_ELU1D_ELOW QUESTION 1.07 (1.50)

Assume the reactor is Xenon free. It then is taken to criticality and the power is raised to 50% at 5%/ min.. If a trip occurs as power reaches 50%,

how will the Xenon concentration be trending in the f ol l owi ng three situations?

Use one of the choices (1-5) be l ow to answer the three qtaestions.

1. Increasing towards peak Xenon concentration.

2. Increasing towards 100% equilibrium.

3. Decreasing toward a dip.

4. Decreasing toward zero percent power equ i l i br i um val ue .

5. At zero percent equilibrium value,

a. One hour after the trip,

b. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the trip.

c. If after 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> from the trip, the reactor was taken back to criticality and power returned to 50% at 1%/ min. What woul d be the trend as power reaches 50%?

ANSWER 1.07 (1.50)

a. 1. Increasing towards peak Xenon concentration.

l

b. 4. Decreasing toward zero percent power equilibrium value. l l

c. 3. Decreasing toward a dip.

[0.5 ea.)

REFERENCE l EQB GENERIC WEC4 RT & HTFF STP LP LOT 101.10 EO-08 192006K110 ...(KA'S) l l

I i

(+*+** CATEGORY 01 CONTINUED 04 NEXT PAGE ***+*)

7 1.__E21UC1ELES_QE_UUCLEeE_EDWER_ELauI_DEERaIlDU. PAGE 7

. IB E Etd QDYuatd1CS._U eat _IEau SE ER_au D_E L U1D_ELOW QUESTION 1.08 (1.00)

During a startup it was determined that Keff was equal to 0.9 when the Source Range (SR) instrument was reading 50 cps. What would the SR instrument be reading if rods were withdrawn to bring keff equal to 0.957 Assume BOL conditions.

a. 100 cps

b. 125 cps

c. 150 cps

d. 175 cps ANSWER 1.08 (1.00)

A (1.0)

REFERENCE EQB GENERIC WEC4 RT & HTFF STP LO LOT 101.12. EO-03 192003K102 ...(KA'S)

QUESTION 1.09 (1.00)

A reactor is shutdown with a boron concentration of 1100 ppm and a SDM of 2 percent delta K per K. The source range channel indicates 10 cps. The boron concentration is then reduced by 100 ppm. Assume DBW is -10 pcm/ ppm.

Choose the answer that is closest to the final Keff,

a. 0.980

b. 0.985

c. 0.990

d. 0.995 ANSWER 1.09 (1.00)

C 0.990 (1.0)

REFERENCE EQB GENERIC WEC4 RT & HTFF STP 1P LOT 101.05 EO-14 001000A404 1?2002K110 192002K114 ...(KA'S) ,

(***** CATEGORY 01 CONTINUED ON NEXT PAGE ++++*)

1 1.__ERENCIELES_QE_ NUCLEAR.20 WEE _ELaul_DEEEaIlON. PAGE 8 IBEEMOQulaMICS._MEaI_IEGUSEEE_aMD_ELu1D_ELOW QUESTION 1.10 (1.00)

Select the ONE answer below which BEST completes the following statement.

The reactor is just critical at 10E-8 amps when +5 pcm is added to the core. Neutron population and coca power will increase ...

a. until turned by the power defect at which time core p owe r w i l l level out at a sl ightl y higher p owe r .

b. by an amount equal to 0.005 percent.

c. indefinitely until the operator inserts -5 pcm by inserting control <

rods or boron.

d. until c ancel l ed b;' the power detect at which time core power will return to the or i gi nal p owe r .

ANSWER 1.10 (1.00)

A (1.0)

REFERENCE EOB GENERIC WEC4 RT & HTFF STP LP LOT 101.15. T0-02 192008K110 192008K114 ...(KA'S)

QUESTION 1.1 (1.00)

During a reactor startup, just prior to reaching criticality, the SUR meter indication will respond to a given amount of rod withdrawal by: (choose l the best answer) l i

a. R i s i n g s l owl y , then sl owl y falling off to :ero j

b. Rising sloaly, then rapidly falling off to zero '

c. Rising rapidly, then slowly falling off to zero ,

1

d. Rising rapidly, then rapidly fallir.g off to zero i 4

l l

1-_ EBlGCl2LES DE UDCLEb8 EDWEB 2L6NI DEEBbILDN.

PAGE 9 IBIEUDDYMAMICS _BEGI_IEateSEEE_auD_ELUID_ELDW i

ANSWER 1.11 (1.00)

C (1.0) l REFERENCE l EGB GENERIC WEC4 RT & HTFF STP LP LOT 101.15 EO-01 015000A102 015000K506 192008K105 ...(KA'S) l QUESTION 1.12 (1.00) l l

The decay heat generation rate immediately following a reactor trip from l

extended full power operation is approximately ___ of rated thermal power.

(Select the best answer from those l i s t e d be l ow . )

i i a. 14%

l

b. 6%

c. 1%

d. 0.7%

ANSWER 1.12 (1.00) 1 l

l B (1.0) l l REFERENCE l EOB GENERIC WEC4 RT & HTFF l 001000K528 192008K127 ...(KA's) l 1 l l

QUESTION 1.13 (1.00) l l

l Which ONE of the following will cause the Axial Flux Difference to become 1

more positive (less negative)? i l

l i

a. A p owe r increase with power defect compensated by rod withdrawal only.

l

b. A power increase with p owe r defect compensated by dilution only.

c. The buildup of xenon in the top portion of the core, j l l

( c. The burnup of xenon in the bottom portion of the core. I l

l l

i l

l I

\

l

-1

I .

la__EBldCIELES_DE_UUCLEGR_L'DUER_ELeUI_DEEBeI1CN. PAGE 10 IBERUDDYueblCS _BEGI_IBeUSEER_eUD_ELulD_ ELL'd ANSWER 1.33 (1.00)

A (1.0)

REFERENCE EQB GENERIC WEC4 RT & HTFF STP LP LOT 101.14 T0-01 001000K506 ...(KA'S)

QUESTION 1.14 (1.00)

The -1/3 DPM SUR following a reactor trip i s caused by which or,e of the f ol l owi n g?

a. The amount of negative reactivity added being greater then the shutdown margin.

b. The decay constant of the shortest-lived group of delayed neutrons.

I c. Doppler adding positive reactivity f ol l owi ng a trip due t o cool down ,

d. The decay constant of the longest-lived group of delayed neutrons.

ANSWER 1.14 (1.00)

D. (1.0)

REFERENCE E08 GENERIC WEC4 RT & HTFF STP LP LOT 101.06, TO 192008K123 ...(KA'S) l 1

l l

(***** CATEGORY 01 CONTINUED ON NEXT PAGE * * * * * )

l l

i

7 _ __ _

1.__EEIUCIELES_DE.BUCLEGE_EOWEE_ELGUI_DEEEellOU. PAGE 11

. IEEEBODrueu1CS._UEeI_IEGUSEER_eUD_ELU1D_ELOW QUESTION 1.15 (1.00)

The plant is operating at 50% cower with RCS Tave at 573.5 degrees F and a steam pressure of 730 psig. To what must Tave be changed in order to maintain these conditions with 10 percent of the tubes in each steam generator plugged? Assume RCS flow rate is constant.

a. 580.5 degrees F

b. 578.5 degrees F

c. 576.5 degrees F

d. 574.5 degrees F ANSWER 1.15 (1.00)

A (1.0)

REFERENCE EGB GENERIC WEC4 RT & HTFF 002020K501 002020K508 ...(KA's)

QUESTION 1.16 ( .50)

Choose the answer which most correctly completes the sentence:

"In the condensate system, the operating point for two pumps operating in parallel will be at --- (choose f r om be l ow) --- as ccepared to the operating point when one pump is operating and the other pump is i sol at e d. "

a. the same flow rate and the same head

b. a higher flow rate and a higher head

c. a higher flow rate and the same head

d. the same f l ow r a t e and a higher head ANSWER 1.16 ( .50)

8. (0.5)

A4__EB1UC12LES_DE_NUCLEeE_EDUEB_ELGUI_DEEBeIIDU. PAGE 12 IbEEidDDYUGUICS~BEeI_I R AN REER_auD_ E LUID_ELOW REFERENCE E0B GENERIC WEC4 RT & HTFF 191005K109 ...(KA'S)

OUESTION 1.17 (1.00)

In regards to DNBR, choose the ONE correct statements

a. DNBR increases with decreasing Tavg.

b. DNBR decreases with decreasing reactor power.

c. DNBR decreases with increasing pressurizer pressure.

d. DNBR increases with dec r eas i ng f l owr a t e .

At45WER 1.17 ('.00)

A. (1.0)

REFERENCE E0B GENERIC WEC4 RT & HTFF 193008K105 ...(KA'S)

QUESTION 1.18 (1.00)

In order to maintain a 200 degrees F subcooling margin in the RCS when reducing RCS pressure to 1600 psig, steam generator pressure must be reduced to aporoximately: (Choose the ONE correct answer)

a. 45 psig

b. 245 psig

c. 445 psig

d. 645 psig ANSWER 1.18 (1.00)

B. (1.0)

REFERENCE 1 EQB GENERIC WEC4 RT & HTFF I 193003K125 ...(KA'S) l

(*+**+ CATEGORY 01 CONTINUED ON NEXT PAGE ++***)

l l

l

1.__ERIUC1ELES_QE_UUCLEaR_20WER_ELauI_DEEEaIl0U. PAGE 13 IBEEdQDYuablCSo_BEaI_IEauSEER_aND_ELulD_ELOW QUESTION 1.19 (1.00)

Choose the correct order of the boil ing phases listed below as they would occur in a cool ant channel with high heat flux.

1. Cr i t i c al Heat Flux

2. bulk boiling

3. film boiling 4 sub-cooled nucleate boiling

a. 2 4, 3, 1

b. 2, 4, 1, 3

c. 4, 2, 3, 1

d. 4, 2, 1, 3 ANSWER 1.19 (1.00) 0 (1.0)

REFERENCE EQB GENERIC WEC4 RT & HTFF 193008K103 ...(KA'S)

QUEST I ON 1.20 (1.00)

Which ONE set of par ame t er s be l ow be s t describes centrifugal pump runout conditions?

a. High discharge pressure, high flow, high power demand i

b. High di sch a r ge pressure, l ow flow, low power demand

c. High discharge pressure, low flow, high power demand j

d. Low discharge pres 3utc, high flow, low power demand

e. Low discharge pressure, high flow, high power demand l

l

_- _ -_ - _-_- -_ - - --_______--_-_---_-___-_____________-_____-__-__-_____-____]

r 1.__EB1UC1ELES_QE_UUCLEeE_EDWEE_ELeUI_DEEEellOU. PAGE 14

. IBEEMODruau1CS._UEeI_IEGUSEER_suD_ELU1D_ELOW ANSWER 1.20 (1.00)

E (1.0)

REFERENCE EQB GENERIC WEC4 RT & HTFF 191004K112 ...(KA'S)

QUESTION 1.21 (1.00)

Which statement is true if natura! circulation is lost s

i. Core delta T decreases. S/G pressura decreases.

b. Core delta T increases, S/G pressure decreases,

c. Core delta T decreases, S/G pressure increatas,

d. Core delta T increases, S/G pressure increases.

ANSWER 1.21 (1.00) 8 (1.0)

REFERENCE EQB GENERIC WEC4 RT & HTFF 193008K122 ...(KA'S)

QUESTION 1.22 .50)

Choose the correct answer. The 2200 degrees F maximum peak cladding temperature limit is used because:

a. It is 500 degrees F bel ow the fuel cladding melting point.

b. Any clad temperature higher than this correlates to the fuel melting point temperature at tne fuel center line,

c. The cladding beccmes weaker, because of a zirconium phase change at temperatures above 2200 degrees F.

d. A zircalloy-water reaction is accelerated at temperatures above 2200 degrees F.

1.__EB1GC1ELES_DE_UUCLEGR_EDUER_ELAUI_DEERGIIDMo PAGE 19

. ZMERUDDXUaL11CS _BEGI_ZBhUSEEB 6MD_ELUlD_ELOW ANSWER 1.22 ( .50)

D. (0.5)

REFERENCE EQB GENERIC WEC4 RT & HTFF 193009K105 ...(KA'S)

QUESTION 1.23 (1.00)

Given: Four reactor coolant (RCP) pumps operating in parallel, each with a flow rate "m" and a core flow rate "M". If one RCP :s secured, which of the f ol l ow i n g be s t describes the effect on core flow "M" and the individual f l ea "m" of the remaining operating RCPs?

a. "M" will decrease as "m" decreases,

b. "M" will increase as "m" increases,

c. "M" will decrease as "m" increases,

d. "M" will not change as "m" increases.

ANSWER 1.23 (1.00)

C (1.0)

REFERENCE EQB GENERIC WEC4 RT & HTFF 191004K114 ...(KA'S) l i

l i

I l

l l

(*++++ CATEGORY 01 CONTINUED G1 NEXT PAGE *****)

I

r 1.__ER1UC1ELES_DE_UUCLEGR_EDUER_ELeUI_ DEER 6I1DU. PAGE 16 IB E Etd O DYHatd1C S o_ B EaI_IEatdS E E R _at2D_ EL UID_E LOU QUESTION 1.24 (1.00)

Select one statement f r om the f ol l ow i ng that correctly describes why density compensation of the main steam line f l ow me asur emen t is necessary,

a. The temperature of the steam lines is proportional to the volumetric f l ow r a t e . Volumetric f l ow r a t e is compensated with the fluid temperature to provide mass flow rate.

b. Differential pressure across the orifice is sversely propor t i onal to the volumetric flow rate. Volumetric flow t is compensated with the fluid temperature to prov I de mass fl ow rate .

c. Differential pressure across the orifice is proportional to the volumetric f l ow r a t e . Volumetric flow rate is compensated with the fluid density to provide mass f l ow r a t e ,

d. The temperature of the steam lines is inversely proportional to the volumetric flow rate. Volumetric flow rate is compensated with the fluid density to provide mass flow rate.

ANSWER 1.24 (1.00)

C (1.0)

REFERENCE E0B GENERIC WEC4 RT & HTFF 191002K102 ...(KA'S) i i

\

QUESTION 1.25 ( .50) l Operating a positive displacement pump with insufficient net positive suction head will cause which one of the f ol l owi ng to occur?

, a. Slip 1 1

b. Decreased pump speed l j

l c. Vapor binding l l

l

d. Viscosity loss l l

l l

l l

l l

w

1 - 221GC12LES DE UUCLEeB 2DUEB EL6UI DEEBaILDU. PAGE 17

. IBEEtSDDXUhtLLCS EEal IBatt!SEEB aND ELULD ELDW I

ANSWER 1.25 ( .50)

C (0.5)

REFERENCE EQB GENERIC WEC4 RT & HTFF 191004K106 ...(KA'S) '

i QUESTION 1.26 (1.00)

Which one of the f ol l owi ng ac t i ons has the LEAST impact on natural circulation?

a. Lowering steam generator level

b. Lowering RCS pressure

c. Increasing RCS temperature

d. Increasing pressurizer level ANSWER 1.26 (1.00)

D (1.0)

REFERENCE EQB GENERIC WEC4 RT & HTFF 193008K123 ...(KA'S) i i

i

(***** END OF CATEGORY 01 ***+*)

2s__EL931_DEh10N_1ULLUD1UU 16EE1X_GUD_huhhuhuCY_SY.41hus PAbE 2 QUESlION 2.01 (1.00)

If the operating instrument Air compressor and automatic start controls do not respond to place a standby compressor in service,

a. how long does the operator have to place a compressor on line before instrument air header pressure is signiticantly reduced it instrument air demand is high? (0.b)

b. What design feature of the system provides this butter or grace period? (U.b)

ANSWER 2.01 (1.00)

a. 2 minutes (accept 2- 10 min.)

b, I.A. receiver OR SA/1A crossover valve opening (0.5 ea)

REFERENCt S1P LP LO1202.26 EO-Vo 0/8000K401 ...(KA'S)

OUES110N 2.02 ( 2. 50 )

a. What are two (2) sources of water for maintaining AFW storage tank level? (0.d)

b. What two (2) conditions / signals are necessary to i n i t i a t e AtibAO (AlWS Mitigation System Actuation Circuitry)? Include coincidence. (U.d)

c. Excluding the turbine driven AFW pump and it associated components, list tour (4) responses of the AFW system to AMSAC initiation. (1.0)

d. How does AFW response due to LOOP initiation differ from the response to AMSAC initiation? (0.d)

2a__R46UL, DhSISN_1NCLUDIND SehhlY_AND_EUERC+Lcdor_SYS1hdS PAUh 3 ANSWER 2.02 (2.50)

a. Demin wa;er (0.31)

Condenser hotwell (0.31)

b. OdLETED

c. Motor driven pumps start Crossover valves close (if open)

Isolation valves open

^>to recirc valves close (when pump at rated speed) valves open to restore level

<4 at 0.31 ea)

d. ' ster driven pumps are started by the load sequencer (0.32) and run in recirc until a lo-lo level or $1 signal is received (0.32).

REFhkENCE STP LP LOT 202.28 EO-03, rn-01 061000K107 061000K40< . . . ( $'Y S )

GUESTION 2.03 (2.50)

a. What type ot power is available to the Class 1E 12U VAC inverters and how is 120 VAC obtained from t h e NORf ML p owe r supply? (1.0)

b. What is the siternate power available to the Class 1E 12U VAC bus? (U.D)

c. What prevents the operator trom paralleling AC sources through 120 VAC class and non-cless busses? (1.0) 1 1

1 .

I 1

i

' 2p__ELedl_DhSibu_1NCLUD1UD_SehhlY_eule EUhhhhdLY_SYSlhUS PAGE 4 ANCWER 2.03 (2.50)

a. 126 DC and 480 AC. (0.63 Normal 480 VAC is rectified to DC and then inverted to produce 120 VAC. [0.5J (1.0)

b. A vol tage regul ator supplied from a different 480 V MCC than the ene supplying the inverter. (0.6)

c. Class: A manually operated bar interlock permits energizing from eitFer source if the other source is open. (0.d/

Non-class: '1 h e auto transfer switch will select only one source at a time. (0.b)

REFERENCE STP LP Lor 201.38, f0-01 062000K410 ...(KA'S)

QUES TI ON 2.04 (3.00)

a. If it becomes necessar y to manually start and load a Standby Diesel Generator, what is the first load that should be placed on the energized 4160 UAC bus? Why? (0.76)

b. What can cause the Stancby Diesel to auto trip if it has started in the "Emergency Mode"? (1.0)

c. What will auto start the Standby Diesel in the "Emergency Mode"? (0.6)

d. Wha $ are 6 of the 6 con trol s af f ec ted by the Standby Diesel Generator Mode Selector Switch? (0./6)

2 __EL6NI_ DESIGN _1NCLUDIND_SeEE1X_.6ND_ENEEGENCY_SYS1 EMS PAGE b ANSWER 2.04 (3.00)

a. ECW pump CO.5) as it supplies cooling water to the S8G. [0.25]

l

b. 1. Overspeed I

2. Gen. Differential l

3. Loss of 125 VDC control power. l

4. Low lube oil pressure (0.26 ea.)

c. 1, SIS

2. Undervoltage on respective bus (0.26 ea.)

l l

d. 1. Start /Stop l

2. Volt. reg. Auto / man.

3. Vol t . Reg. adjust

4. Governor speed con trol l

5. Governor Mode

6. Gen. Output Bkr. j

7. Sync scopy control (any 5 at 0.15 ea)

REFERENCE STP LP LOT 201.36. 10-01 064000A301 064000A401 064000K401 ...(KA'S)

QUESTION 2.05 (2.50)

a. What heat loads will normally be supplied by an operating Essential Cooling Water (ECW) train? (0./5)

b. What is the normal ECW train configuration for the unit at steady state power and how does it change for startup or shutdown? (0./6)

c. What are four (4) additional actions that will occur au t oma t i c al l y on an ECW Pump start due to train actuation? (1.0) i i

I l

1 l

1 1

1

2 __ELGU1_DESIGU_1UCLUDIUD_SeEE1Y_eUD_EUEBLEUCY_SYS1EUS '

PA - 6 7 ,

ANSWER 2.05 (2.50)

a. 1. CCW HX

2. Essential EAB HVAC chillers

3. CCW Pump supplementary (room) cooler E0.25 ea)

EDG accepted but not required.

b. Normal: 1 train operating, 1 train in standby, 1 train off. (0.8)

Startup or shutdown: Switch to 2 trains operating, 1 in standby.(0.25)

c. 1. Start ECW discharge strainer.

2. Open ECW blowdown.

3. Open pump discharge valve.

4. Provides signal to Sodium Hypochlorinator.

5. Starts ECW room vent fans.

6. 1 raveling screen starts.

7. Scr.?n wash pump starts. [.7y 4, 0.25 ea.]

REFERENCE STP LP LOT 201.13. TO-01 076000K118 076000K402 ...(KA'S)

QUESTION 2.06 (2.50)

a. List six (6) specific components whose failure will result in radioactive leakage into the CCW system. (0.9)

6. What happens to CCW system excess inventory due to in-leakage? (0.6)

c. Describe all CCW system automatic action that may result from CCW IN-LEAKAGE and GUT-LEAKAGE. (Answer each s e p a r a t e .' y . ) (1.0) ,

)

l l

l i

l l

l l

2 .__EL*6UI_DESIGu_1NCLUQ1NG_SeEEIY_GUD_EMEEGENCY_SYSIEUS PAGE /

ANSWER 2.06 (2.50)

a. RHR HX, RCP Thermal Barrier, LD HX, Excess LD HX, Seal Water HX, RCDT dX, Sample Coolers. [Any 6, 0.15 ea3

6. Overflow vent discharges to the floor drain which leads to the CCW sump (which is subsequently processed by liquid waste system). (0.6)

c. OUT-LEAKAGE:

1. Auto make up

2. Auto i sol a t i on of non-ESF train

3. Auto i sol a t i on of RCP thermal barriers (common header supply & ret)

4. CCP cross-connect shuts

5. CCW train A supply and return from charging pump header isolate

6. CCW outlet valves from RHR open IN-LEAKAGE:

1. Surge tank over flows via vent

2. RCP thermal barrier i sol a te s (0.125 for each action)

REFERENCE Si'P LP LOT 201.12, 10-01 008000K102 ...(KA'S)

QUESTION 2.07 (1.00)

When the 25 KV system trip relay (86-G1) is energized due to a fault condition, a generator trip occurs. Excluding annunciation, L181 the 2 actions that will occur automatically?

AN SWE R 2.07 (1.00)

a. trips main turbine (0.5)

b. trips permanent magnet generator supplv breaker (41M). (U.S)

c. generator output breaker (0.S)

(ANY 2)

REFERENCE STP LP LOT 202.17 EO-04 045000A304 ...(KA'S)

(++*** CA'I EGORY 02 CONTINUED ON NEXT PAGE *****)

2.__ELeUI_ DESIGN _1NCLUQiNG_SeEELY_oND_ EMERGENCY _SYSIEMS PAGE 8 QUESTION 2.08 (1.50)

Expl ai n , wi th respec t. to Vil AL BUSES, DIESEL GENERAlORS (DG), and DG BREAKER (s) CLOSURE, what happens during an ESF loading sequence where an SI is coincident with a site olackout (mode 111). Load sequence not required.

ANSWER 2.08 (1.50)

1. All equipment operation on vital buses is terminated on loss of power by the l oad shed si gnal . (0.5)

2. Diesel generators start and connect to the vital buses (in 10 seconds subsequen t l y vital power restored). (0.5)

3. ESF loading sequence commences on DG breaker (s) closure. (0.b)

REFERENCE STP LP LOT 201.22 EO-10 013000K407 064000K411 ...(KA'S)

QUESTION 2.09 (3 50)

List three (3) ways in which the spent fuel pool is protected from a c omp l e t e loss of water.

2 r__EbeUI_ DES 15U_IUCLUDING_SeEE1Y_GUD_EUERGENCX_SYS1EUS PAGE 9 ANSWER 2,09 (1.50)

(ANY 3 AT 0.5 EA)

1. There are no drains installed in the pool.

2. The return lines contain antisiphon holes.

3. The spent fuel pool liner has continuous weld seam drains. (Any leakage would drain to a central collection point for leak de tec t i or )

4. The spent fuel pit cooling pump's suction penetrates the pool near the normal water level so that gravity draining due to a line break is prevented.

4

5. Accidental opening of the transfer canal gate would lower water level by aniy 6 feet.

6. Multiple water sources are available for reflood (Demin water, Reactor Makeup)

REFERENCE STP LP LOT 201.28. EO-07, LOT 201.07-3.1.2.G GENERIC WEC4 EQB  ;

033000K401 ...(KA'S)

QUESTION 2.10 (1.50)

]

l The air operator for FCV 205, Charging Flow Control Valve, develops a large 1 air leak. HOW and WHY does the failure of thi s valve affect RCP seal 1 injection f l ow?

l l

I l

ANSWER 2.10 (1.50) j The large air leak will cause the valve to fail open (0.b). RCP seal l i

injection flow will decrease (0.5) due to the reduced backpressure from l FCV-205 (0.5). l REFERENCE l GTP LP LO201.06, EO-21 l GENERIC WEC4 EQB i 004000K104 ...(kA'S)

(***++ CATEGORY 02 CONTINUED ON NEXT PAGE *****)

2 p__EL,eUI_DESIGU_1NCLUDING_SeEEIY_6ND_SSE8GENCY_SYSIEds PAGE 10 QUESTION 2.11 (2.50)

List five (5) radioactive LIQUID effluent monitors which have automatic control functions, AND briefly describe the control function for each monitor listed.

ANSWER 2.11 (2.50)

1. Boron Recycle system - Diverts flow back to the BRS Evaporator Feed Demineralizers (or recycle holdup tank).

2. Liquid Waste Processing System - Diverts waste back to the waste monitor tanks.

3. Turbine Generator Building Sump and Drain System - Stops the sump pump.

4. Condensate Polishing System - Closes discharge valve to neutalization basin.

5. Steam Generator Blowdown System - Closes discharge valve to neutralization basin.

(0.5 EACH)

REFERENCE STP LP SOT 202.41, EO-09 073000K401 ...(KA'S)

QUESTION 2.12 (1.b0)

a. State to what each of the following Chemical and Volume Control System (CVCS) relief val ves di scharge . (1.0)

1. 75 psig VCT relief. (PSV 3101)

2. 600 psig RC purification pump relief.

I

3. 300 psig Low pressure relief valve .PSV 3201) l

4. 150 psig Leak Off Header Relief valve (PSV 3200) i

b. Which of the CVCS relief valves has a downstream temperature monitor to indicate when the valve has lifted? (0.5) l l

l I

q

2r__EbeNI_DESISU_IUCLUDING_SeEE1X_eUD_EMERDENCY_SYS1EUS PAGE 11 ANSWER 2.12 (1.50)

a. 1. Boron recycle system tv. tank

2. VCT

3. UCT

4. PRT (0.25 ea)

b. 600 psig Relief on the outlet of the letdown orifices (PSV 3100)

REFERENCE STP LP LOT 201.06 EO-23 004000K108 004000K122 004000K123 004000K105 ...(KA'S)

OUESTION 2.13 (1.S0)

a. What are two (2) indications or symptome which will be observed if a tube leak occurs in a RCP Thermal Barrier heat exchanger. (Assume NO alarm setpoints are reached.) (1.0)

b. If the tube l e a k; continues to increase in severity, WHA T AU TOMA f l C action will occur? (0.S)

ANSWER 2.13 (1.50)

a. 1. Rising CCW surge tank level

2. Incteasing CCW system radioactivity

3. Increasing CCW heat exchanger inlet temperature (any two at 0.5 each)

b. The CCW return isolation valve on the affacted thermal barrier heat exchanger will shut OR CCW thermal barrier HX outlet shuts on high flow. (0.6)  !

1 REFERENCE )

STP LP LOT 201.12 EO-10 1 008000K102 008000K104 ...(KA'S)  ;

1

y-- _ _ . ,

i 3.__1NSIEUUEUIS_AUD_CONIROLS PAGE 27 !

' l QUESTION 3.01 (1.00)

Which ONE of the f ol l owi ng componen t s is used in the Rod Control Tave Control Unit to compensate for reactivity changes?

a. Variable Gain Unit.

b. Non-Linear Gain Unit.

c. Lead-Lag Compensator,

d. Rod Speed Programmer.

ANSWER 3.01 (1.00)

a. Variable Gain Unit.

O F<

c. Lead / lag unit REFERENCE GENERIC WEC4 EQB 001000K402 ...(KA*S)

QUESTION 3.02 (1.C')

Which ONE of the f ol l oa i n g is the correct symptom of an OPEN Cold Leg RTD?

a. T cold indication goes low.

b. Delta T indicatior goes low,

c. T average indication goes low,

d. Both T cold and T average go low.

l ANSWER 3.02 (1.00) l REFERENCE l GENERIC WEC4 EQB i 002000K606 ...(KA'S) ,

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

g -

30__1NSIRudEUIS_eUD_CONIROLS PAGE 28

. o QUESTION 3.03 (1.00)

Which one of the following is an indication of an Intermediate Range Channel be i ng sl i gh tl y (5- 10 /*. vol tage error) undercompensated?

a. Automatic energizing of the soJrce range when the first intermediate range channel drops below the P-6 setpoint.

b. Actual neutron level falls into the sourc? range without indication.

c. Indication remains above 10E5 cps in the source range on both channels,

d. Automatic energizing of the source range when the P-10 interlock was cleared on both channels.

ANSWER 3.03 (1.00) b REFERENCE GENERIC WEC4 EQB 015000K401 015000K604 ...(KA'S)

QUESTION 3.04 (1.50)

a. What minimum signals are required to generate permisive P-47 (0.5)

b. List four (4) functions of P-4. (1.0)

I l

I l

l 1

l 4

Sp _INSIBUMEUIS_eUD_CONIBDLS PAGE 29 ANSWER 3.04 (1.50)

a. One reactor trip breaker and its bypass breaker both open. (0.5)

b. 1. Trips the main turbine (via P-16)

2. Closes FW reg valves when Tavg decreases below low se tpoin t (of 574 degrees F).

3. Allows manual block of SI

4. Inputs P-15 for excessive cooldown protection.

5. Prevent auto reactuation of SI (any 4 at 0.25 each)

REFERENCE STP LP LOT 201.20, EO-07 012000G004 012000K603 012000K610 ...(KA'S)

QUESTION 3.05 (2.00)

List t he AUTOMATI C s i g.ial s wh i ch wi l l give a Main Steam Isolation Siqnal.

(Include setpoints, coincidence, and when in effect where applicable .N ANSWER 3.05 (2.00)

Containment High Pressure (HI-2), 3.0 psig, 2/3 Low Steam Generator Pressure, 735 psig, 2/3 in 1/4 P-15 (P-4 or 2/4 NI <10%) and LoLo Tc 532 deg,F, 2/3 in 1/4 High Steam Pressure Rate, -100 psi /sec, 2/3 in 1/4, in effect only if ECP (p-15) is blocked. -

l (0.5 ea - 0.2 for signal, 0.15 for setpoint, & 0.15 for coincidence)

REFERENCE STP LP LOT 202.02, EO-13 I 000040A101 000040A204 000040G011 ...(KA'S) l

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

i

r 3.__1NSIRudEMIS_6UQ_COUIROLS PAGE 30

. s GUESTION 3.06 (2.50)

State five (5) uses of the output of the first stage impulse pressure transmitter. Setpoints are NOT required.

ANSWER 3.06 (2.50)

1. Used to input to SDCS for load reject (C-7).

2. Used to develop the P-13 signal.

3. Used to generate Tref.

4. Used to generate steam generator water level program,

5. Used to generate a rate of change of power ( i r, the automatic rod control circuit).

6. Block auto rod withdrawal be l ow 15% turbine power.

7. used to generate T(error) for rod control

8. used to generate T(error) for steam dump modulation (any 5 at 0.5 ea)

REFERENCE STP LP LOT 201.20, EO-03, LOT 201.18, EO-06, LOT 202.15, EO-04 001000K403 001000K407 ...(KA'S)

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

3.__luSIEUMEUIS_auD_CQUIROLS PAGE 31 QUESTION 3.07 (1.50)

Match the following permissive interlocks in column "A" with their respective function in column "B".

COLUMN _A COLUMN _B

a. P-11 1. Turbine Trip Feedwater I sol a t i on < Low TaV9r arms condenser dumps. Al l ows bl ock of Safety injection signal after time delay block,

b. P-9 2. Allows block of Source Range reactor trips.

c. P-7 3. Unblocks "At Power" reactor trips,

d. P-8 4. Unbl oc k s the 1/4 Loss cf Loop Flow,

e. P-6 5. Al l ows bl ock of the I.R. High Flux l ow 9e tpoi n t reactor trip,

f. P-10 6. Allows reactor trip on turbine trip.

7. Blocks automatic and manual Rod Withdrawal.

8. Actuates Turbine Runback.

9. Allows Manual Block of Low Pressurizer Pressure.

Safety injection, and Low Steam Pressure Safety Injection.

ANSWER 3.07 (1.50)

a. 9 d. a

b. 6 e. 2

c. 3 f. 5 (0.25 EA)

REFERENCE STP LP LOT 201.18, EO-06 GENERIC WEC4 EQB 012000K610 ...(KA'S)  !

l l

l

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

l

3.__1MSIEudEUIS_eUD_CQUIROLS PAGE 32

. QUESTION 3.08 (1.50)

Assume 75% p owe r , EOL, and Roc Control is in. automatic. State the effects of the following Power Range nuclear instrumen t channel failures on the Rod Control sytem and N0 operator action. Include any changes in steady state RCS/ core parameters,

a. Controlling (selected) NI channel f a i l s h i gh .

o. Controlling (selected) N1 channel fails l ow .

ANSWER 3.08 (1.50)

a. 1. Rods will only drive in until the derivative ckt times out. (0.5)

2. The reactor will not trip but Tave will remain l ow s i n c e a rod stop (C-2) has occurred. (0.5)

b. No effect because highest reading channel is used for control. (0.5)

(Give 1/2 credi t for discussion assuming failure downstream of the auctioneering circuit.)

REFERENCE GENERIC WEC4 EQB STP LP LOT 201.18 015000A202 ...(KA'S)

QUESTION 3.09 (1.50)

State the response of the reactor trip (RT) and bypass (BY) breakers given the following three (3) sets of initial conditions:

a. One train is placed in test while the other train's BY breaker is closed.

6. An attempt is made to close both BY breakers at the same time.

c. A solid state protection system (SSPS) train "R" reactor trip signal is generated.

l i

I I

i

3,__lNEI2)MEUIS_eUD_CDUIEDLS PAGE 33 ANSWER 3.09 (1.50)

a. BOTH RT (0.25) and BOTH BY breakers will trip (0.25).

b. All FOUR (4) breakers will trip (RT "R" & "S" and BY "R" & "S") (0,5)

c. The RT "R" (0.25) and BY "S" (0.25) breakers will trip.

REFERENCE GENERIC WEC4 EQB 012000A307 ...(KA'S)

QUESTION 3.10 (2.00)

For each of the following situations determine whether the rod control interlocks should prevent outward rod motion. For those conditions where outward rod motion is prevented, explain what actions must be taken to reestablish outward rod motion. Assume rod control is in MANUAL. Consider each case separately,

a. An intermediate range nuclear instrument fails high during a plant startup with reactor power at 10%.

b. A power range nuclear instrument f ails high during a plant startup with reactor power at 60%.

c. The turbine first stage impulse pressure transmitter fails low during a plant startup with reactor power at 20%.

d. Simultaneously Loop i Th fails high and Loop 1 Tc fails low while operating at 100% power.

-~ -

3 __INSIBUMENIS_eUD_DDUIBDLS PAGE 34-ANSWER 3.10 (2.00)

a. Rod motion is prevented Block C1 signal (Accept "No effect" if C-1. blocked) (0.5)

OR reactor trip for 1/2 IR >25X

b. Rod motion is prevented Position Rod stop bypass switch. (0.5)

c. No ef f ec t (0,5)

d. No ef f ec t (0.5)

REFERENCE GENERIC WEC4 EQB 01200K6106 ...<KA'S)

GUESTION 3.11 (2.00)

With the plant operating at 100% power and all control systems in auto, the selected control channel level detector in the pressurizer level control system fails LOW. List four (4) immediate component actuations (NO alarms) that will be initiated by the detector failure.

ANSWER 3.11 (2.00)

One letdown i sol at i on val ve closes.

All letdown orifice isolation valves close.

Pzr backup he..ter groups are deenergized.

Pzr variable heaters are deenergized, increase chargi ng fl ow (or PDP speed increases or charging FCV opens).

(any 4 at 0.5 each) l REFERENCE GENERIC WEC4 EGB i 011000A203 ...(KA'S)

QUESTION 3.12 (1.50) ,

While at 96% power, steady-state, the reactor trips. Simul taneousl y, T-hot f a i l s h i gh for loop 3. Describe how the Steam Dump System will operate under these conditions assuming all other equipment functions normally with no operator action concerning the failed Thot instrument.

1

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

3.__luSIEUbEUIS_eND_CDUIEDLS PAGE 35 ANSWER 3.12 (1.50)

The Tavg vs. Tno-l oad mi smatch wi l l trip the high-high bistable (30 degrees) and cause all dump valves to trip full oper. [0.53.

All dump val ve s stay full open until a Lo-Lo Tave signal (P-12) is received (0.5)

Then all dump valves will shut (0.5]. (The hi-hi bistable will not clear.)

REFERENCE STP LP LOT 202.09 EO-14 041020K105 041020K411 041020K414 ...(KA'S)

QUESTION 3.13 (2.50)

a. List the inputs to the Feedwater Byp ass Con trol Valve system and ,

explain why the inputs are used compared to the inputs used for l controlling the Feedwater Control Valve. (1.0) '

b. Assuming 100% powar, is automatic protective action more likely to I result from a FAILED HIGH or FAILED LOW Steam Generator Level Control System Steam Pressure Detector. Justify your answer. (1.5)

ANSWER 3.13 (2.50)

a. Level error (0.25] and auctioneered high nuclear power. [0.25] Nuclear power used in lieu of flow error due to inherent inaccuracies at low flow conditions. [0.53

b. Failing low is more likely to resul t in protective action. (0.5)

The pressure detector directly affects the flow transmitter output and the highest output of the flow transmitter is (133%) [0.25]

and a flow error of (33%) is correctable by level error before a trip point is reached. CO.25) A low failure on the other hand will result in a 100% error which is not correctable by level error before a trip setpoint i s reached. CO.5] (1.5)

REFERENCE STP LP, SGLWC, Pp. 24,27 059000401 ...<KA'S) l (**+*+ CATEGORY 0 3 CONTINUED G4 NEXT PAGE * * * * * )

l l

l l

l l

3.__lMSIEUMEUIS_6UD_CONIROLS PAGE 36 QUESTION 3.14 (2.00)

Describe HOW and explain WHY the RCP Undervoltage and the RCP Underfrequency trips function differently.

ANSWER 3.14 (2.00)

A Low voltage trip will trip the reactor [0.5] where an Underfrequency trip will trip the reactor and the RCP breakers. [0.53 Breakers are tripped on-underfreqLency to prevent the sl owi ng of pumps and reduc i ng f l ow coas tdLwn time. [1.03 REFERENCE STP LP, SSPS, Pp. 10,11 012000K402 ...(KA'S)

QUESTION 3.15 (1.50)

The reactor is in hot shutdown with RCS pressure at 1800 psig. The reactor trip breakers have been reset and the shutdown banks are fully withdrawn with the intent of continuing plant startup. I & C maintenance personnel want to perform a calibration on the Turbine Impulse pressure channels.

What will be the consequences, if any, of allowing the calibration to be done at this time?

ANSWER 3.15 (1.50)

Placing turbine impulse in test will deenergize the interlock circuit P-13 which feeds P-7. 'O.5) This will unblock the low pressurizer trip (0.5) and the shutdown control rods will trip (0,5).

REFERENCE GENERIC WEC4 EQB STP LP LOT 201.20 012000K406 ...(KA'S)

(***** END OF CATEGORY 0 3 *** * * )

a.__EEOCEDURES_=_ NORMAL +_aEMORMAL._EMERGEUCY_eUD PAGE 37 RADIOLOGICAL _CONIROL QUESTION 4.01 (2.50)

a. What are two (2) major factors that.may influence RCP motor winding temperature to INCREASE as well as DECREASE during heat up of the RCS?

(1.0)

b. What are 3 abnormalities or problems indicated by required frequent filling of RCP M 3 seal s t an dp i r e s? (0.75)

c. With a RCP seal temperature indication going off scale, what other indication should be checked to ascertain whether a seal or instrumentation problem exists? (0.75)

ANSWER 4.01 (2.50)

a. May decrease as the fluid being pumped becomes less dense and less winding current is required. May increase due to increased contalment ambient temperature. May increase due to repeated motor starts during seal venting. i (any 2 at 0.5 each)  ;

l

b. 1. Damaged seal

2. Wor r. seal

3. Seal not fully seated

4. Leak in RHR i

5. Leak in standpipe system (any 3 at 0.25 each)  ;

c. 1. Inj. temp.

2. Inj. flow

3. Leakoff f l ow

4. Other RTD,

5. Seal delta P

6. High CCW water temp (any 3 at 0.25 each)

REFERENCE STP AOP 1 POP 04-RC-0002, REV. 3 003000A201 003000A203 ...(KA'S) 1

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

i

, d.__EROCEDUBES_=_UDEdeL._eBNDEdeLo_ EMERGENCY _eUD PAGE 38 Ea'010 LOGICAL _COMIROL l

I QUESTION 4.02 (2.00)

During the performance of "Excessive RCS Leakage" (1POPO4-RC-0003): l 1

a. What three (3) leakage detection systems would be indicative of a leak l within the containment? (1.0) )

b. If the leak was not inside the containment (according to the'above indication) or outside containment by thorough visual inspection, what three (3) other components should be checked to determine the source of leakage out of the RCS? (1.0) i ANSWER 4.02 (2.00) l

a. 1. Containment atmosphere gaseous radiation monitoring system. l

2. Sump level and flow monitoring system. I

3. Containment atmosphere particulate radiation monitoring system.

(0.33 each)

b. 1. RCDT (level, temp.)

2. PRT (level, temp.) l

3. S/G (activity, feed /stm flow, level) [0.33 ea.)

REFERENCE STP AOP 1 POP 04-RC-0003 REV.2 002000K405 ...(KA'S)

GUESTION 4.03 (2.00)

a. Why does 1 POP 02-DG-0001 (EMERGENCY DIESEL GENERATOR 411) caution against placing the Control Mode Switch on the engine control cabinet I in the "0FF" position? (0.75)

6. When an EDG has been operated for sir (6) hours at no load or "light load", it must be run for 15-30 minutes at >75% load. What is "light load" per the procedure? Why is this action necessary? (0,5)

c. If the EDG starts in automatic and the normal supply breaker to the ESF bus is closed and the EDG output breaker is open, when may the EDG be shutdown? (0.75)

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

Ao__ERDCEDUBES_ _NDEdeL._eBUDRbeLo_EMEESENCY_eUD PAGE 39

. %DlDLDDICeL CDtG8DL ANSWER 4.03 (2.00)

a. The EDG will not start (in either emergency (0.5) er manual (0.25) modes) with this switch in "0FF". (0.75)

b. "Light load" is defined as (50%. (0.25) This is done to reduce carbon buildup in the engine (which may degrade performance). (0.25)

c. The EDG may be shutdown after:

1. SI has been reset

2. The EDG h as been released from the emergency mode

3. The AC busses have been verified energized (0.25 each)

REFERENCE STP OP 1 POP 02-DG-0001, REV. 4 QUESTION 4.04 (1.00)

Precautions in Power Operations (1 POP 3-2G-0008) state that the rate of power increase shall not exceed 5%/ Min. or a 10% step change. Aside from "good engineering practice," what are two (2) reasons that rate of increase is routinely LESS than stated above?

ANSWER 4.04 (1.00)

1. Fuel conditioning limits. (0.5)

2. Turbine Generator loading limits. (0,5)

3. Rod control system design limits

4. Prevent SG level transients

5. Limitations on rate of change of boron concentration to change power (any 2 at 0.5 each concepts only) l REFERENCE STP NOP 1 POP 03-ZG-0008, REV. 2 002000SG13 ...(KA'S) l l

l l

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

_._- _ _ . . _ . . . . , __ - . . _ _ _ , . _ _ _ _ . _ _ _ . . . . ..J

do__EROCEDURES - NOEdeL+_eBUDEdeL ,_EMERGENCX_6ND PAGE 40 Reb 10 LOGICAL _CONIEOL QUESTION 4.05 (1.50)

a. For pressurizer bubble formation, what components are manipulated to i n i t i al l y control:

1. Chargi ng f l ow rate at greater than 50 GPM?

2. Reactor Cool ant pressure between 75 and 100 psig? (1.0)

b. If it is decided to add Hydrazine to the RCS during i n i t i al heatup, WHAT CHANGE must be made to the CVCS lineup and WHY? (0.5)

ANSWER 4.05 (1.50)

a. 1. Charging flow (Pzr Level) control valve (1*FCV-0205)

2. Le t down pressure control valve (1*PCV-135) [0.5 ea]

b. Divert letdown flow f om demi neral i zer [0.33 es demineralizer may release undesirable ions (upset RCS chemistry) OR resin may deplete.

(0.2)

REFERENCE STP NOP iPOP03-2G-0001 REV. 7 004101K618 011000K101 ...(KA'S)

OUESTION 4.06 (2.00)

a. In "Natural Circulation Cooldown with Steam Void in Vessel" (ES03),

why is the ooerator instructed to maintain a LOW pressurizer level when initially starting the procedure and a HIGH level for starting a Reactor Coolant Pump? (1.0)

6. Why is the operater cautioned not to depressurize the RCS until the entire system is below 200 deg's F.? (0.5)

c. Why is there a priority for running specific Reactor Coolant Pumps after they become av a i l abl e? (0.5) i l

l l

iL__EEDCED])RES_ _UDRdet _eBUDEtdeL_EldERDENCY_eUD PAGE 41 BdDlDLDDICAL_LDUIRDL l

ANSWER 4.06 (2.00)

a. Low level to accommodate void growth. (0.5).

High level to prevent pressurizer from emptying. (0.5)

6. May f orni voi ds in loops OR RCS (0.5)

c. Provide normal pressurizer spray. (0.5)

REFERENCE STP EOP 1 POP 05-EO-ES03, REV. 2 000015K101 ...(KA'S)

QUESTION 4.07 (1.00)

Explain how shielding from irradiated fuel is provided while removing the Reactor Vessel head.

ANSWER 4.07 (1.00)

As water level in the refuesing cavity is raised, the vessel head is raised just above the water level until there is sufficient level to provide shielding. (1.0)

REFERENCE STP LP LOT 201.28 034000A401 ...(KA'S) 1 QUESTION 4,08 (2.00) j 1

a. Immediate action i r, "Reactor Trip or Safety injection" (EO-E000) requires the operator to verify feedwater i sol a t i on . State the valves that must be checked to cenfirm proper isolation. (1.0)

b. What are the primary and alternate methods of verifying Phase "A" containment isolation? (1.0)

I 1

l

d e__EROCEDUEES_=_NORdeL._aBUQEdeL._EUERGENCY_aWD PAGE 42 RADIOLOGICAL _COMIBOL ANSWER 4.08 (2.00)

a. o Flow control valves o Flow control valve bypass valves o FW isolation valves o FW i sol at i on B/P val ves o S/G bl owdown isolation o Sample i sol a t i on o FW preheater bypass valve (0.143 each)

b. Primary: ERFDADS (ESF status monitor lights)

Alternate: MCB Indication (0.5 ea.]

REFERENCE STP EOP 1 POP 05-EO-E000, REU.3 000007SG10 ...(KA's)

QUESTION 4.09 (1.50)

a. When the operator is instructed to "Check for faulted S/G" per EO-E000, what indication is observed? (0.5)

b. According to the Steam Generator Tube Rupture procedure (E030), what are four (4) f l ow p a t h s of concern when the operator is instructed to "Stop flow FROM the ruptured Steam Generator"? (1.0)

ANSWER 4.09 (1.50)

a. S/G pressure (0.5)

b. PORV, MSIV, MSIV bypass, St?am supply to AFW Pump, and Bl owdown i Isolation Valves. (any 4 at 0.25 each) i l

REFERENCE '

STP E0P 1 POP 05-EO-E000, REV. 3, 1 POP 05-EO-E030, REU. 4 000038A100 000038A201 ...(KA'S) i I

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

. , _ _ __ _ . . _ __ _ _ _ . . . ___ _ _ , - . _ . _ _ . - - ~ ,

A.__EROCEDUBES_=_UDEdaL+_aBUORMaL._EMERGEUCY_auD PAGE 43 red 10 LOGICAL _CQtdIROL QUESTION 4.10 (2.00)

a. According to EO-FRS! (Response to ATWS or Power Generation), what are four (4) viable methods of stoppirg the Main Turbine, should it fail to trip automatically? (1.0)

6. Step 7 of the above procedure requires the operator to verify all dilution paths isolated or secured. What are the two (2) dilution paths of concern? (0.5)

c. What action is the operator directed to take if immediate boration rate i s sl ow due to high RCS pressure and RCP's are stopped? (0.5)

ANSWER 4.10 (2.00)

a. 1. Man u al l y trip from MCP

2. Stop EH control pumps

3. Trip from front standard

4. Shut MSIV's (0.25 ea.]

b. 1. Letdown demineralizers

2. Reactor makeup water (pumps) [0.25 ea.)

c. Open pzr PORV's OR initiate aux spray (0.5)

REFERENCE STP EOP IPOP05-EO-FRS1, REV. 2 000029A100 ...(KA'S)

QUESTION 4.11 (2.00) 1

a. Define each of the following: (1.0) l l

1. Radiation Area  !

2. High Radiation (include locked space criteria)

)

b. When using a hand held frisker to exit a radiologically restricted I area, personnel contamination is said to exist based on what l indication? (0.5) l i

c. What is the maximum background radiation level in which a hand held l frisker can be used reliably? (0,5) l l

l l

_, -. . , , - , - - . , - . , - . - - , . , . - , , - , . , _ . .,_,,.g., _ . , , , , - . ..,,--,.-.e , - - . . - - ,

A __EBDCEDUEES - NDEdaLo_eBUDEdeLe_ EMERGENCY _AND PAGE 44 BADlDLDDlCeL_CDNIBDL ANSWER 4.11 (2.00)

a. 1. Accessible area where whole-body dose of =>2.5 mr can be recieved in one hour. OR Whole body dose rate > 5 mrem /hr or 100 mrem in 5 consecutive days. (0.5)

2. Accessible area where whole-body dose of =>100 mr can be recieved in one hour.(0.3) Areas of >1000 mr/hr shall be locked and controlled by radiaticn protection personnel.(0.2)

b. A reading of =>100 counts above background (on any part of the body or clothing will be considered as contamination). (0.5)

c. 300 cpm (0,5)

REFERENCE STP OP OPRP01-2A-0032, REV. 1 194001K103 ...(KA'S)

CUESTION 4.12 (2.00)

Give the South Texas whole body QUARTERLY exposure limits for each of the f ol l owi ng condi t i ons/ personnel :

a. Visitors

b. Pregnant women

c. Non GET !! trained employees

d. Radiation workar with complete exposure history on file and j supervisory approval up through the H&SS Division Manager and Plant 1 Manager.

ANSWER d -12 (2.00)

a. 100 mrem j

b. 100 mrem OR 500 mrem during gestation period l

c. 100 mrem i b 5 es l l

REFERENCE STP OP OPRP01-2A-0032, REV. 1 194001K103 ...(KA'S)

(+**++ CATEGORY 04 CONTINUED G4 NEXT PAGE *****)

fL__ E B O C E Q U E E S_= _tJ O Etde L._.e BN QEt:16L o_ EtS E R G EN CY _au Q PAGE 45

. EAQ10 LOGICAL _COtJIROL OljESTI ON 4.13 (1.00)

Which of the f ol l owi ng annunc i ators woul d NOT be initially indicative of a dropped control rod?

a. "ROD DEVIATION"

6. "ROD CONTROL NON-URGENT ALARM"

c. "PR CHANNEL DEV" d, "PR FLX RATE HI RX TRIP ALERT" ANSWER 4.13 (1.00) b (1,0)

REFERENCE STP AOP 1POPO4-RS-0001, REV. 2 014000A203 ...(KA S)

QUESTION 4.14 (1.00)

Ha4 is the positive reactivity compensated for while recovering a dropped rod? (Two (23 methods required.)

ANSWER 4.14 (1,00)

Adjust turbine load CO.5) AND/OR boron concentration .CO.5)

REFERENCE STP AOP iPOPO4-RS-0001, REV. 2

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

L_ R B O C E D U R ES _ = _tJ O Rtde L._e BN O RbiB L._ Eld E RG EN CY_eN D PAGE 46 red 10 LOG 1CeL_CONIROL QUESTION 4.15 (1.50)

a. A condition of an operator's license is that it be "active" before the operator may function in an operating postitlen requiring'a license.

Give the conditions which must be satisfied for a license to be considered "active",

b. What minimum requirement must be satisfied before you, as a licensed operator, al l ow a non-l i c ensed individual to manipulate reactivity controls under your observation? DO NOT consider authorizatior.s which may be required from on-shift supervisory personnel.

ANSWER 4.15 (1.50)

a. The licensee must be on shift in a licensed position for at.least:

1. seven (7) shifts of eight (8) hours each OR

2. five (5) shifts of twelve (12) hours each per calendar quarter.

OR The licensee is current in the requalification program and has completed forty (40) hours under instruction in a licensed position in-the current calendar quarter.

(Accept any one tf three possible answers for full credit, 0.75 pt) 1

b. The l',J i v i du al must be currently participating in f ormal training to  !

obtain a licens9 (0.5) The licensed operator must have previously performed the evolution. (0.25)

REFERENCE 10 CFR 55.51, 10 CFR 55.13 010CFR5513 010CFR5551 ...<kA'S)

I l

l l

l l

l

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

. 6 COMMENTS ON NRC REACTOR OPERATOR EXAMINATION MAY 16, 1988 SOUTH TFXAS PROJECT SECTION 1 1.05 accept "c" also: FTC is temperature dependent and at same T* BOL to E0L FTC becomes more positive. Ref. FSAR Fig. 4.13-27 (attached)

SECTION 2 2.01a accept answers ranging from 2-10 minutes as the wording on the question "instrument air demand high" is vague. Lesson plan does not define high demand. Reference Lot 202.26 2.0lb also accept answers which discuss SA/IA crossover valve opens on low IA header pressure. Reference LOT 202.26 1.4.1.F IPOP04-IA-0001

.r 2.02b delete b - AMSAC actuation is not currently installed on Unit 1 AFK actuation signals. Signnis were not taught to this class, however, it will be taught as part of Dual License Training.  ;

Reference SS-14-9-Z 40131 Logic 2.02d should not require "in Recirc" for credit. This is implied by ,

system design, 2.04d also accept: operation of synchroscope switch Reference Logic 5Z-10-9-Z-42121 t

2.05b also accept: 2 trains running one in standby at all times. '

Reference LOT 202.36, LOT 202.37 ventilation requires 2 Trains ECW '

running normally. Base <1 on T' requirements for Essential Chilled i Water damand.

2.05c accept: Blowdown valve gets closed signal on safety train actuation. Reference LOT 201.13-1.4.8.A.2 "Train actuation" wording is vague and dcas not define if normal actuation or safety actuation.

2.06b accept any one of below.

(1) vent or overflow (any one of 2) or (2) overflow to floor drain which drains to CCW sump er (3) surge tank level increases to accommodate excessive leakage omit:

processed by liquid waste system as not relevant to question or l accept: I processed by Chemical Operations Department I Reference P&lD CCW System 5R209F05017 1 _ _ . --,

1 l

l 2.06c outleakaae change Key to: (Any 4, .2 ea action)

1. auto makeup

2. auto isolates non-essential header (non ESF Train)

3. CCW common header supply and return valves isolate (lose CCW to RCP thermal barrier)

4. CCP cross connect shuts also accept:

5. CCW Train A supply and return from charging pump header valves isolate also accept:

6. .CCW outlet valves from RHR open (to ensure minimum flow)

Reference IP0P04-CC-0001 Supplementary actions.

2.06c inleakaae: also accept: RCP thermal barrier isolates Reference IP0P04-RC-0002 auto actions also accept: surge tank overflows out vent or overflow Reference PalD 5R209F0517 2.09 add to Keyf Class IE Safety Grade water okeup from Reactor Makeup water system always available to Spent fuel Pool (Normal supply -

Demineralized Water System)

Reference LOT 201.7-3.1.2.G LOT 201.28-3.4.1.E.2 2.12b also accept:

"Relief on outlet of lctdown orifices" common plant name - relief valve number not required. Also delete Key requirement "to the PRT" since question doesn't ask for this.

2.13a should also accept CCW return from Thermal Barrier Heat Exchanger temperature increasing.

Reference IP0P09-AN-04M7 2.13b also accept:

self actuating pressure valve on CCW outlet from thermal barrier Heat Exchanger will close on high pressure.

Reference LOT 201.12 page 25 G-1 SECTION 3 3.01 accept either A or C Question is confusing with wording "Rod Control Tava Control Unit". Can lead license candidate to believe speaking of Tavg portion of Rod Control only.

also accept "C" Reference We:;tinghouse Transient rnd Accident Analysis Section 8 page 4 Note "a" is correct also per LOT 201.18 page 22 6.A

o

• 3.04b answer #3 Separate into 2 different functions as follows

1. allows manual Block SI

2. prevents auto Reactuation of SI

Reference:

5-2-10-9-2-42115 Logic print Westinghouse Logic 8758022 Sheet 8 - attached 3.05 Do not deduct credit for (P-4 and no P-10) P-15 Not required for credit on Key accept: low S/G press. 735 2/3 on 1/4 (without ECP Blocked) accept: P-15 and LoloTc 532*F 2/3 on 1/4 (without ECP Blocked) change: "low steam line pressure MSLI is blocked" to "with ECP Blocked" Reference 52-10-9-2-42112 Logic Print change: containment Hi-2 setpoint to 3.0 psig Reference T.S. Table 3.3-4 ESF Instrumentation Tables 3.06 accept any of the following along with Key answers

1. Generates Tref for Steam Dump Load Rejection Controller

2. Generates C-7 Load Rejection Signal to arm Steam Dumps

3. Feeds Tref input to C-17 Low temperature return to power Turbine Stop Loading

4. Feeds Tref in Rod Control System Tavg/ Tref mismatch

5. Feeds Power mismatch circuit and Variable Gain units in Rod Control System

Reference:

Westinghouse Transient and Accident Analysis Book 1 Tab 6 Page 20, 21, 25, 26 3.08b Question used the words "controlling (selected)" NI channel. This leads the examinee to believe the failure is downstream from the Auctioneering Circuit. The Auct Hi Nuc Pwr signal fails low therefore a description of the failing low actions should be accepted, such as Rods stepping out, etc.

3.09c change answer to RTR and BYS 3.09c also accept (due to type in question): Train A signal will send a signal to Both Train R and Train S Reactor trip signals. Train R signal will trip R Rx Trip Breaker and S Bypass Breaker. Train S signal will trip S Rx Trip Breaker and R Bypass Breaker. (Assume Train 8 or C signal was already present)

Reference logic 52-10-9-2-42110 3.10a also accept: Rx trip due to IR amps >25% 1/2 Westinghouse Transient and Accident Analysis Volume 1 Tab 6 page 19 l

l i

]

. w SECTION 4 4.01a Answer should also accept motor starts (due to Seal Venting)

Reference:

IPOP02-RC-0004 4.0lb add to Key: leak in standpipe system

Reference:

Engineering practice 4.01c accept:

1. Seal Delta P

2. Hi CCW Water T* (with no seal injection)

Reference IP0PO4-RC-0002 4.02a Key answer incorrect - change answer to:

1. Containment Atmosphere Gaseous Radioactivity Monitoring System

2. Containment Normal Sump Level and Flow Monitoring System

3. Containment Atmosphere Particulate Radioactivity Monitoring System delete: RCFC drain flow monitoring cystem Reference Technical Specifications 3.4.6.1 also accept:

Containment Atmosphere Monitoring Systems as 1 & 3 above 4.03c Revise Key to accept 1 or 2 for full credit. Do not give or take credit for 3.

1. Reset SI (and Load Scquencer)

2. Release from emergency mode

3. Local /off/ remote switch remote Reference (1) IP0P05-E0-ES11 (2) 50-15-9Z-42100 Rev 8 Logic Print also accept:

Verify AC emergency bus energized from offsite power Reference IP0P05-E0-ES11 Step 21 4.04 IP0P03-ZG-0008 no longer exists. Has been deleted, accept the following concepts along with Key answers.

1. stay within design of Rod Control System

2. prevent S/G water level transients (ex: swell) which could actuate protective signals or ensure remain within the capacity of SGWLC

3. at power with all Rods out - dilution process to increase power and keep Tavg + 1*F of Tref is slow, cannot accommodate rapid loading (or similar concept)

Reference:

Westinghouse Transient and Accident Analysis 4.05b accept: "upset RCS chemistry" as is synonymous to "release undesirable ions" 4.08a add to Key: Feedwater Preheater Bypass valve Reference IP0P05-E0-E000 Step 5.6

<*o 4.09b Since question asks for flow paths, not steps in procedure, accept: Main Steam Isolation valve closed as one path and Main Steam Isolation Bypass valve as separate path 4.10c FRS1 Does not address "boration rate is slow" or "RCP status".

Question is confusing therefore should also accept alternate feasible methods of pressure reduction i.e., aux spray 4.11a.1 also accept: accessible area where whole body dose of >5 mrem /hr or 100 mrem in 5 consecutive days.

Reference:

Health and Safety Services Definitions Procedure OPRP01-ZA-0001 4.llb Delete from Key "....on any part of the body or clothing will be considered as contamination." not required as question implies quantity desired only 4.12 OPRP01-ZA-0032 has been deleted accept Key answers per old procedure also accept following answer per current procedure

b. delete "not"

c. 100 mrem

Reference:

OPGP03-ZR-0042 - 4.6 (attached) 4.15a Request question be deleted.

10CFR55 requirements to maintain or reestablish an active license status are incorporated into IP 8.9Q, Operator Requalification procedure. This procedure is currently being reviewed by the NRC for approval prior to implementation. For this reason, these requirements were not taught to this hot license class. If question cannot be deleted, full credit should be given for discussion on standing watches (no hours or days) and/or attending Licensed Operator Requalification.

4.15b Question may be interpreted to ask what ypog, as a licensed operator, are required to do before you can allow a non-licensed (implies authorized) individual to manipulate controls, accept: Must have performed the evolution previously

Reference:

Plant Conduct of Ops 0PGP03-ZO-0004 4.11.1.3 l

l l

l 1

. -