Text

Exam Rept 50-482/OL-88-02 on 881128-1201.Exam Results:Of Six Reactor Operators,One Passed & of Nine Senior Reactor Operators,Seven Passed All Parts of Exam
	ML20247G287
Person / Time
Site:	Wolf Creek
Issue date:	03/23/1989
From:	Graves D, Pellet J; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:	;
Shared Package
ML20247G280	List: ML20247G275; ML20247G287;
References
	50-482-OL-88-02, 50-482-OL-88-2, NUDOCS 8904040189
	Download: ML20247G287 (145)
	v • d • e

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

i APPENDIX U. S. NUCLEAR REGULATORY COMMISSION l REGION IV Operator Licensing Examination Report: STN 50-482 Operating License: NPF-42 Docket No.: 40-482 Licensee: Wolf Creek Nuclear Operating Corporation P. O. Box 411 Burlington, Kansas 66839 Facility Name: Wolf Creek Generating Station Examination at: Wolf Creek Generating Station (WCGS)

Chief Examiner: S- 3h3h9 Date grD.N. Graves, Examiner Operator Licensing Section Division of Reactor Safety Approved by:

J.LL. Pellet, Chief I 3k3b9 Date Operator Licensing Section Division of Reactor Safety Summary NRC Administered Examinations Conducted on November 28 - December 1, 1968 (Report 50-482/0L 88-02)

NRC administered examinations to six reactor operators (RO) and nine senior reactor operators (SRO) applicants. One R0 applicant (17 percent) and seven <

SR0 applicants (78 percent) passed all portions of the examination and have been issued the appropriate license. Performance on the R0 written examination was below average. The average score in Category 1, " Principles of Nuclear Power Plant Operation, Thermodynamics, Heat Transfer and Fluid Flow," was 72.2 percent, with 2 candidates scoring below 70 percent, and all 6 candidates scoring below 80 percent. The average total score for the R0 candidates was j 78.7 percent, with 4 applicants (67 percent) scoring less than 80 percent.

Several problems were encountered with the simulation facility during the examinations and are addressed in the Simulator Fidelity Peport.

I 8904040189 DR 890327 ADOCK 05000482 PDC

DETAILS

1. Persons Examined SRO R() TOTAL License Examinations: Pass - 7 1 8 Fail - 2 5 7

2. Examiners D. N. Graves, Chief Examiner J..L. Pellet K. M.' Kennedy T. P. Guilfoil M. E. Stein R. B. Smith

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 WCGS. The only comments addressed in this section are those which were not accepted for incorporation into the examination and/or answer key. Those comments 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 comneents is attached.

2.02 c. With a loss of instrument air, loss of the steam dump 4 6.03 c. system would cause initial steam flow to be less. Later in the event, the effect of the steam line drains failing open would produce a higher steam flow. Recommend deleting this part of question.

Response: The stated reference specifically addresses the answer in the key.

2.06 b. The referenced lesson plan is incorrect regarding CCW pump 6.06 b. response on an SIS. No credit should be given or lost for references to CCW pump starting or stopping.

Response: No credit was lost if the candidate did not mention any change in pump status. If the candidate addressed pump changes, the answer was graded in accordance with the actual plant ~ response.

2.07 a. If the EDG is supplying the bus alone due to undervoltage 6.07 a. (the most likely cause) the ESX relays energize. This locks speed in at 60 HZ. Therefore, also accept "no change" as an alternate answer for speed change.

Response: If the candidate stated that he/she assumed the EDG start was due to undervoltage, "no change" is acceptable.

3.06 c. If Channel II Tavg were to fail high, resulting in the

" failed high auctioneered Tavg", then the Channel II OT delta T setpoint would decrease. Recomend also accepting

" decrease."

Response: Reject.. The question specifically stated the "auctioneered Tavg unit" failed, not a loop Tavg.

4.02 b. If less than 350 F,~RHR could also be used for RCS 7.03 b. heat removal. Should also accept RHR.

Response: RHR accepted if temperature restriction stated also.

4.04 d. Accept "Use of Steam Generators" 7.05 d.

Response: Reject. The referenced procedure specifically states that '

l the steam generators is not appropriate during half loop operation.

4.07 Recommend deleting " energizing backup heaters" as part of 7.08 the required answer. Also recomend accepting for full credit "imediate borate 135 ppm for each control rod not inserted."

Response: Reject. Point value on the backup heater portion of the answer was reduced. The recomended answer above was not accepted because it does not state what the operator has to ;

do to perform the innediate boration.

b. Site Visit Sumary (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 comenting on the examination content validity. It was explained to the licensee staff that grading of the written examinations would not begin until review coments were received by the NRC regional office.

l

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

NRC WCGS E N. Graves U hernoff ,

K. M. Kennedy C. M. Estes J. L. Pellet D. L. Fehr J. E. Gilmore R. Schneider E. J. Taylor (3) The following items were communicated to the facility licensee representatives as comments, observations, suggestions, or deficiencies:

(a) During the simulator portion of the operating examination, the operators tended to get " tunnel vision" with respect to annunciators. They would focus on the first annunciator sighted, acknowledge, and respond to cnly that annunciator even though other alarms had occurred simultaneously.

(b) Simulator fidelity items were discussed. A list of these items is included on the Simulation Facility Fidelity Report, which is included in this report.

(c) The next examination administered at WCGS will be written in accordance with Revision 5 of NUREG 1021 " Operator Licensing Examiner Standards." Training material will need to be provided to cover industrial safety knowledges and abilities in accordance with NUREG 1122, "Knowledges and Abilities Catalog for Nuclear Power Plant Operators:

Pressurized Water Reactors."

(d) Any exauiination retakes from the current set of examinations will be administered in accordance with Revision 5 of the Examiner Standards. Section waiver requests will be evaluated on a case by case basis.

(e) NRC will participate in WCGS' next set of requalification examinations and should expect to have approximately 20 percent of their licenses examined during 1989.

c. Followup Meeting Summary On March 20, 1989. WCGS personnel met with NRC personnel in the Region IV office to review the causes and corrective actions for the high failure rate on this examination set. The handouts from that meeting are attached. The following personnel were present at the meeting:

l l NRC WCGS K. Kennedy U! Eailey S. McCrory G. Boyer J. Milhoan D. Fehr J. Pellet J. Gilmore

0. Maynard M. Williams J. Zell The handouts from the meeting are enclosed. WCGS' analysis of the poor performance attributed it to four contributing causes:

(1) Evaluation criteria used to predict candidate success was not as effective as in the past.

(2) Training material and lesson plans were not directly linked to the NRC K/A catalog.

(3) Training program did not prepare candidates for different styles of examinations.

(4) Candidate background qualifications were slightly lower than in the past.

WCGS personnel consider the first two causes above to be the major contributors to the high failure rate. During discussion, NRC expressed concern that these results were a trend that started after the October 1986 examinations. WCGS staff agreed that the transition to " hot" license candidates with reduced background qualifications had begun after those examinations. However, WCGS training staff had extended the training program by four weeks for this class because of the reduced background experience. WCGS personnel also stated that for future license classes, additional emphasis would be placed on the experience of nonlicensed operators entering the program in addition to increased attention to ongoing performance evaluation during the license training program.

d. Generic Comments The results of the R0 written examination indicate that a significant number of applicants had difficulty with Category 1, " Principles of Nuclear Power Plant Operation, Thermodynamics, Heat Transfer and Fluid Flow." The average score on Category 1 was 72.2 percent, with 2 out of 6 scoring less than 70 percent and all 6 candidates scoring less than 80 percent.

l l

e. Master Examination and' Answer Key Master copies of the WCGS license written examinations and answer keys are attached. The facility licensee comments which were accepted have been incorporated into the answer key.

f.. Facility Examination Review Comments The facility licensee comments 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.

g. Simulation Facility Fidelity Report All items in the attached Fidelity Report have been discussed with the facility staff.

l 1

l 1 L

SIMULATION FACILITY FIDELITY REPORT

~

Facility Licensee: Wolf Creek Nuclear Operating Corporation Facility Licensee Docket No.: 50-4S2 )

l Facility License No: NPF-42 l Operating Tests Administered at: Wolf Creek Generating Station (WCGS)

Operating Tests Administered on: November 29 - December 1, 1988 During the conduct of the simulator portion of the operating tests identified

~

above, the following apparent performance discrepancies were observed:

1. Requesting various computer screen displays from the operator's console in the control room causes the display to_ lock up.

2. Initial conditions (IC's) representing end of life (E0L) conditions do not faithfully reproduce actual plant response or conditions.

3. The plant continued operating at 74 percent power with only one main feed pump operat%g. Several candidates stated that this was unrealistic and did not be* ve one feed pump could maintain steam generator levels at that power . vel.

4. Main feedwater line breaks inside the containment are not modelled correctly. NRC was informed of this prior to beginning the examinations.

5. On three occasions during the examinations, different portions of the control panel froze and would not respond to actions taken by the candidates. The RL 003/04, RL 005/06, and RL 019/022 panels were the malfunctioning panels. Each time the sinolator had to be frozen to restore the proper capabilities to the panels.

WOLF CREEK GENERATING STATION PRESENTATION ON NRC LICENSE EXAMINATION RESULTS FOR NOVEMBER 1988 ARLINGTON, TEXAS MARCH 20,1989 W$LF CREEK NUCLEAR OPERATING CORPORATION L_ _ __ _ _ ____ ___ - - - _ _-----_ ---.----_ _

SUMMARY

OF CONTRIBUTING CAUSES RELATIVE TO -

l NOVEMBER 1988 EXAMINATION RESULTS l

l

- EVALUATION CRITERIA USED TO PREDICT THE SUCCESS OF THE LICENSE CANDIDATES WAS NOT AS EFFECTIVE AS IN THE PAST

- TRAINING MATERIAL OBJECTIVES USED IN THE HOT LICENSE CLASS WERE NOT DIRECTLY LINKED TO GENERIC K/A CATALOG, RESULTING IN POSSIBLE INADEQUATE TRAINING EMPHASIS / INAPPROPRIATE EXAM QUESTIONS

- FAILURE OF TRAINING PROGRAM TO ACCUSTOM LICENSE CANDIDATES TO DIFFERENT STYLES OF EXAMINATIONS

- SLIGHTLY LOWERED BACKGROUND QUALIFICATIONS OF LICENSE CANDIDATES PRIOR TO ENTERING HOT LICENSE CLASS I

i

)

4 CORRECTIVE ACTION

SUMMARY

FOR EXAMINATION PERFORMANCE IMPROVEMENT

- INCREASED SENSITtGTY TO PERFORMANCE INDICATORS THROUGHOUT PROGRAM WITH MORE SOLID PERFORMANCE REQUIRED TO TAKE NRC EXAMINATION.

COMPLETION OF WOLF CREEK SPECIFIC K/A CATALOG WITH CORRESPONDING REVISION OF LESSON MATERIAL AND OBJECTIVES.

COMPLETION OF GENERIC FUNDAMENTALS LESSON MATERIAL AND EXAM BANKS. RESTYLING OF PRACTICE NRC EXAMS TO FOLLOW NRC EXAMINER GUIDELINES.

- ENSURE THE BEST QUALIFIED INDIVIDUALS POSSIBLE ARE SELECTED TO PARTICIPATE IN THE HOT LICENSE PROGRAM.

8 % %

- 3 0 N 5 1

1 5 8 1

O I S T N -

A O 2 T I Y 8 %

8 0 S T A

R A

2 4 1

- 0 G N M N I M I M U 1 7

S 1

T A 8 % %

- 5 4 A X 3 1 8 8 1

E 1

R E E C N E N E S A 5 6 8 %

G N M 0 0

0 1

E R 5 1 K C O E I F E L R R E 9 6 8 %

2 C C P 1 1

6 8

F R L N O 2 5 %

W 2 8 0 5 1

- 0 6 4 1

8 % %

- 9 3 8 0 8 8 1

1 EuEa. ERw 2 2 4 8 9 9 8 6 7 7 vEm 5.@< ERw 2 e

t a l R l e s t s e a a D P O

~

o NCIF CREEK 52-WEEK IUf IJCENSE PROGRAM

?

.- - b 0 *b5 DESCRIPTION SUCCESS CRITERIA

. . 1 Fundamentals

-Reactor teory 8 weekly exams

-% hemodynamics > 70% / exam l -Fluid Recry > 80% overall average 1 -Plant Cmponents 8 wks Syst e_s

-NOGS Plant Systms 8 weekly exams j

> 70% / exam 3

> 80% overall average j l

2 wks Classroorn Review; None; Makeup exams, MCB Normal Simulator Ops I familiarization.

15 wks On-Shift Control Rom Experience None; Cmplete all portions of qualifi-cation card required to be done in the plant.

2 As Nomal Simulator Operations q None. ',

-Startup, heatups, cooldowns 4 wks Fundamentals /Systms None; RO's receive train-Review (RO's) ing in weak areas, SRO's Supervisory Training /SRO Tech are trained in supervisory Trng (SR)'s) responsibilities.

I wk Miticatino Core Damace > 80% on test at weeks end 6 wks Abnormal Simulator Operations Weekly operational exams

-Drergency, Off-NoImal, and given by simulator staff.

E-Plan procedures 6 -ks Review weekly NRC style practice

-Classrocrn lectures, self examinations, simulator study, simulator training, sessions as needed, and plant walkd u s, practice plant walk-

-Startup certification. downs. Must pass start-up certification exam-Figure 2 ination.

l ,

U.S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION Facility: OLF bEEEK Reactor Type: Mi2 - Ld E C N Date Administered: 6 6/ll/2R Examiner: D. GRAVES Candidate:

INSTRUCTIONS TO CANDIDATE Use separate paper for the answers. Write answers on one side only. Staple question sheet on top of the answer shaets. Points for each question are indi-cated 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 Category % of Candidate's Category

_Value Total Score Value Category 26.00 25.00 1. Principles of Nuclear Power Plant Operation, Thermo-dynamics, Heat Transfer and Fluid Flow 2.6.0 0 2.S .0 0 2. Plant Design Including Safety and Emergency Systems 26.00 15.0 0 3. Instruments and Controls 15.00 16.0 0 4. Procedures - Normal, Abnormal, Emergency, and Radiological Control

/00.00 TOTALS Final Grade %

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

Candidate's Signature i

__.________.__J

NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules apply:

1. Cheating on the examination means an automatic dentil of your application and could result in more severe penalties.

2. Restroom trips are to be limited and only one candidate at a time may leave. You must avoid all contacts with anyone outside the examination room to avoid'even the appearance or possibility of cheating. {

3. Use black ink or dark pencil only to facilitate legible reproductions.

4. Print your name in the blank provided on the cover sheet of the examination.

5. Fill in the date on the cover sheet of the examination (if necessary).

6. Use only the paper provided for answers.

7. Print your name in the upper right- hand corner of the first page of each section of the answer sheet.

8. Consecutively number each answer sheet, write "End of Category __" as appropriate, start each category on a new page, write only on one side of the paper, and write "Last Page" on the last answer sheet.

9. Number each answer as to category and number, for example, 1.4, 6.3.

10. Skip at least three lines between each answer.

11. Separate answer sheets from pad and place finished answer sheets face down on your desk or table. l

12. Use abbreviations only if they are commonly used in facility literature.

13. The point value for each question is indicated in parentheses after the j question and can be used as a guide for the depth of answer required.

I

14. Show all calculations, methods, or assumptions used to obtain an answer l to mathematical problems whether indicated in the question or not.

l 15. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE I

QUESTION AND DO NOT LEAVE ANY ANSWER BLANK.

l l 16. If parts of the examination are not clear as to intent, ask questions of I

the examiner only.

l

17. You must sign the statement on the cover sheet that indicates that the work is your own and you have not received or been given assistance in I completing the examination. This must be done after the examination has j l been completed.

1 1

f J

)

L___-_____-----__-____--_- 1

l

18. When you complete your examination, you shall: 'l)

n. As s e.nb l e your examination as follows: -

(1) Exam Questions on top.

(2) Exam sids - figures, tables, etc.

(3) Answer pages including figures which are part of the answer. I

b. Turn in your copy of the examination and all pages used to answer the examination questions. 1 f

c. Turn in all scrap paper and the balance of the paper that you did not use for answering the questions.

d. Leave the examination area, as defined by the examiner. If after leaving, you are found in this area while the examination is still in progress, your license may be denied or revoked.

l l

I

It__BE6CIDB_EBINCIELES_LZ11_IBEBdQDXNedICS Page 4 LZ11_6ND_GDdEDNENIS_L1111_LEUND6dENIeLS_EXedl QUESTION 1.01 (1.00) i A reactor is initially suberitical with a Keff of 0.95 and a source range

. count rate of 200 counts per second (CPS). Which one of the following is the final count rate if control rods are withdrawn to add 0.027 delta k/k reactivity?

a. 250 CPS

b. 300 CPS

c. 350 CPS

d. 400 CPS QUESTION 1.02 (1.00)

In a subcritical reactor, Keff is increased from 0.880 to 0.965. Which one of the following is the amount of reactivity that was added to the core?

a. 0.085 delta k/k

b. 0.100 delta k/k

c. 0.126 delta k/k

d. 0.220 delta k/k I

(***** CATEGORY 1 CONTINUED ON NEXT PAGF, *****) l L___________________ _ _ _ _ _ J

It__BE69198_EBINCIELES_1Zil_IBEB0001N60102 Page 5 LZ11_oND_000E9NENIS_11111_LEUNDodENI6LS_i_adl

)

l 1

QUESTION 1.03 (1.00)

The moderator temperature coefficient (MTC) becomes LEAST NEGATIVE (the ;

absolute value becomes smallest) under which ONE of the following !

conditions? j i

a. Moderator temperature is decreased while boron concentration is i decreased. !

b. Moderator temperature is increased while boron concentration is increased. I

c. Moderator temperature is decreased while boron concentration is increased.

d. Moderator temperature is increased while boron concentration is decreased.

QUESTION 1.04 (1.00)

A control rod has its greatest reactivity worth if it is inserted in which ONE of the following locations?

a. Near the edge of the core.

b. Near the center of the core.

c. In 6 region with high poison concentration.

d. In a region with low fuel concentration.

QUESTION 1.05 (1.00)

Delayed neutrons :

a. are born at thermal energy levels f<1 ev).

b. account for the Importance Factor (I; being < 1.0

c. account for 70% of the f ission neutron inventory,

d. are more likely to cause fast f ission than prompt neutrons.

l l

l

(***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)

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

l l '. I 1

! It__BEeGIQB_EBIUCIELES_LZil_IBEB0001N601G1 Page 6 LZ11_800_00dEQUENIH_L1111_LEUNQodENIeLS_E86dl QUESTION 1.06 (1.00)

Which of the following statements concerning 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 increases the rod worth requirements necessary to maintain the desired shutdown margin following a reactor trip.

c. The power defect is more negative at the beginning of core life due to the higher concentration of boron in the core.

d. The power defect necessitates the use of a ramped Tave program to maintain an adequate RCS subcooling margin.

QUESTION 1.07 (1.00)

Which one of the f ollowir.g statements presents the two (2) primary methods for Xe-135 production in the core.

a. Decay of Iodine-135 and fission.

b. Decay of Samarium-149 and activation of oxygen.

c. Decay of fission products and activation of U-233.

d. Decay of Iodine-135 and activation of oxygen.

QUESTION 1.08 (1.00)

Which one of the following factors proportional to control rod worth is the most important variable for determining rod worth?

a. Moderator temperature

b. Ls (slowing down length)

c. L (thermal diffusion length)

d. (Local Flux / Average Flux) quantity squared

(***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)

.. ' 's

! i L lli__BEeCIQB_EBINGIELES_LZ11_IBEB500I860101 Page 7 4 LZ11_8ND_GDdE9NENIS_L11&l_LEMNDedENI6LS_EEodl i

i QUESTION 1.09 (1.00) l Ouring a reactor startup, just prior to reaching criticality, the.SUR meter indication will respond to a given amount of rod withdrawal;by: (choose-the .;'

best answer)

I

a. Ris ing slowly, then slowly falling off to zero. -

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

c. R is ing slowly, then~ rapidly falling off to zero.

d. Rising rapidly, then rapidly falling off.to zero. <

QUESTION 1.10 (1.00)

During a reactor startup from a Keff of 0.90, the first reactivity addition .

caused count rate to increase from 10 cps to 16 cps. -The second-reactivity 1 addition caused count rate to increase from 16 cps to 32 cps. Which one of the following statements best describes the relationship between the first and second reactivity additions.

a. The first reactivity addition was larger

b. The second reactivity addition was larger

c. The reactivity additions were equal

d. Relationship cannot be determined from the given data QUSSTION 1.11 (1.00)

'The reactor is operating at 50% power, BOL, when a steam dump fails open.

Assume rod contral is in MANUAL, no operator action is taken, and no reactor trip occurs. Which answer below describes finel conditions as compared to initial conditions?

a. Power and Tave are higher

b. Power and Tave are lower

c. Power is the same and Tave is lower

d. Power is higher and Tave is lower

(***** CATEGORY 1 CONTINUE 0 ON NEXT PAGE 2****)

l L 1-

. l l .

.it__BE69IQB_EBINCIELES_LZ*1_INEB0901N6d19S Page 8 1 LZ11_eUD_G9dEQUENIS_L1111_LE9BDedENI6LS_E86dl-

. QUESTION. 1.12 (1.00)-

i 1

During a Xenon free reactor startup, critical data was inadvertently-taken two decades below the level it is normally required. Assuming RCS l l

. temperature and boron concentration do not change, critical data is again !

taken at.the proper level. How would the two critical rod positions.

l compare? (1.0) l l

QUFSTT.0N 1.13 (1.00) 1 The onset of Nucleate Boiling 'is said to occur when: (choose ONE ani.wer I

from below)

a. Bulk fluid temperature reaches saturation conditions.

lb. A thin layer of steam forms at the heated surface. ;l

c. TheLcriti. cal heat flux is reached.

'd . Small bubbles form at the heated surface.

QUESTION 1.14 (2.00)

Inoicote whether the following will cause the power range. instrument to be indicating HIGHER, LOWER, or the SAME AS actual power, if the' instrument

'has been adj usted to 100% based on a calculated calorimetric. l i

a. ~The feedwater temperature used in the calorimetric was higher than actual feedwater temperature. (0.5)

b. The reactor coolant pump heat input used in the calorimetric was omitted. (0.5)

c. The indicated steam flow was lower than actual at the time of the calorimetric. (0.5)

d. The feeowater flow rate used in the calorimetric was lower than actual {

feedwater' flow rate. (0.5) l 1

(

1

(****:4 CATEGORY 1 CONTINUED ON NEX7 PAGE *****)

1

1___BEeCIDB_EBINGIELES_LZ11_IMEBd00188d101 Page 9 LZ11_eUD_C9dEDUENIS_L1111_LEUNDodENIoLS_gxed]

QUESTION 1.15 (2.00)

How will the Departure From Nucleate Boiling Ratio (DNBR) change (INCREASE, DECREASE, REMAIN THE SAME) in response to increasing each of the following parameters? Ccnsider each separately. (2.0)

a. Tavg

b. Priniary system pressure

c. Primary coolant flow rate

d. Reactor power level QUESTION 1.16 (1.00)

Which of the following would be indicative of a LOSS of natural circulation flow (HORE THAN ONE MAY APPLY):

a. Hot leg temperature increases

b. Steam generator pressure decreases faster than corresponding cold leg temperature

c. Cold leg temperature remains relatively constant

d. Steam generator level / rate increases with same AFW flow QJESTION 1.17 (1.00)

The plant is operating at 30 percent load during a load ramp to full power.

If steam flow density compensation fails at its 30 percent load value, which ONl of the following describe the affected steam flow indication when at full power?

a. Indicated steam flow is greater than 100%.

b. Indicated steam flow is greater than 30% but less than 100%. I

c. Indicated steam flow is equal to 100%.

d. Indicated steam flow is equal to 30%.

I

(***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)

i it__BE8CI98_EBINGIELES_LZil_IHEB5001Ned1GS Page la LZ11_8ND_G90E9BENIH_f1111_LEUNDodENI6LS_EEed)

QUESTION 1.18 (1.00)

Select one statement from the following that correctly describes the reason density compensation of the main steam line flow measurement is necessary,

s. Differential pressure across the orifice is propor tional to the volumetric flow rate. Volumetric flow rate is compensated with the fluid density to provide mass flow rate.

b. Differential pressure across the orifice is inversely proportional to the volumetric flow rate. Volumetric flow rate is ;

compensated with the fluid temperature to provide mass flow rate. !

c. Differential pressure across the orifice is proportional to the volumetric flow rate. Volumetric flow rate is compensated with the fluid temperature to provide mass flow rate.

d. Differential pressure across the orifice is inversely proportional to the volumetric flow rate. Volumetric flow rate is compensated with the fluid density to provide mass flow rate.

QUESTION 1.19 (1.00)

A calculated Estimated Critical Position (ECP) is performed for a startup to be commenced 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after a trip from 100% power. Considering each case below independently, state whether the Estimated Critical Position (ECP) will be HIGHER, LOWER, or the SAME As the Actual Critical Position (ACP).

a. The startup is delayed until 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months after the trip. (0.5)

b. The condenser steam dump pressure controller setpoint is increased to just below the steam generator atmospheric steam dump controller setpoint. (0.5)

QUESTION 1.20 (1.00)

Indicate for each of the following conditions whether a greater tensile stress is generated on the INNER or OUTER wall of the pressure vessel:

a. Heating up the Reactor Coolant System at 75 degrees F per hour. (0.5)

b. Increasing system pressure from 2000 psig to 2250 ps ig. (0,5) l l

(***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)

.s li__BgecIDB_EBINCIELES_LZ*1_IHEBdQDINed191' Page 11 LZ11_86D_CQdEDNENIS_L1111_LEUNQedENIeLS_E8ed)

. QUESTION 1.21 (2.00)

n. , What is the subcooling margin of the plant-if the following conditions-exist?- -(1.0)

-Thot = 613' degrees F. Ppzr = 2235 psig Tavg = 586 degrees F Peg = 1000 psig Tcold = 560 degrees F

b. If power is raised from 50% to 100%, does'the subcooling margin INCREASE or DECREASE? EXPLAIN your answer. - ( 1. 0 ) -

QUESTION 1.22 (1.00)

Which one of the following isotopes found in the reactor coolant would NOT.

j be indicative of a potentiet fuel cladding. perforation?

l a. Co-60 l

t. .I-131 I

c. Xe-133 d.- Kr-85 l

l l

h l-I

[***** END OF CATEGORY 1 *****)

e 4 2t__EDEBGENGl_eND_6BNDBDeL_ELeNI_EY9LUIIQNS Page 12 12Zil l

QUESTION 2.01 (3.00)

n. The Ultimate Heat Sink (via ESWS) provides emergency makeup or' backup water supply for what three (3) systems? (1.5)

b. List five (5) automatic actions that occur in the ESWS upon receipt of

a. loss of offsite power signal. (1.5)

QUESTION 2.02 (3.00)

n. What three (3) major groups of valves normally operated by Instrument Air are provided with accumulators (eight hour backup)? (1.5) J

b. Describe the personnel hazard noted with some of these accumulators due to the N2 supply pressure. (1.0)

c. Select the answer below that best indicates how the steam demand, following a loss of instrument air and subsequent reactor trip, will compare vith a normal reactor trip's steam demand. (0.5) i

1. 1% to 5% higher l

2. 6% to 10% higher

3. 1% to 5% lower

4. 6% to 10% lower i

i l

I i

l i

l I

l 1

1 l

l l

l

(***** CATEGORY 2 CONTINUED ON NEXT PAGE *****) !

j

. . I l

l 21__EUEBGEUQI_6UQ_6BNQBd6L_EL6NI_gyQLUIIQNS Page 13 l 12Z31 I

l l

QUESTION 2.03 (3.00)

c. Charging pump discharge flow is 87 gpm and pressurizer and VCT levels are constant. Describe the distribution of this 87 gpm including what letdown flow is necessary to meintain constant pressurizer and VCT levels (CVCS Flow Balance). (1.0)

b. For each volve listed below, state whether it is air or motor operated and in which position each will fail if its motive force Cair or power) is lost: (1.5)

{

1. Low Pressure Letdown Control Valve (PCV-131)

2. Charging Flow Control Valve (FCV-121)

3. Normal Charging Valve (HV-8146)

4. Normal Charging Line Containment Isolation Valve (HV-8106)

5. Letdown Isolation Valves (HV-8160, HV-8152)

6. Alternate Charging Valve (HV-8147)

c. What automatic actions (alarms excluded) occur when the Boron Dilution Mitigation System is activated? (0.5)

QUESTION 2.04 (3.00)

a. Describe how, when using RHR for cooldown, the cooldown rate can be controlled or varied while still maintaining a constant flowrate through the RHR pump (s). (1.0)

b. What two (2) conditions must be met for an automatic shift of RHR pump suctions to occur (include appropriate values)? (0.8)

c. What two (2) automatic actions occur when the automatic shift logic is actuated? (0.8)

d. How can the automatic shift of RHR suctions be defeated? (0.4)

(***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)

2t__EUEB9ENGX_oND_6BUDBd6L_EL6NI_EV9LUIIQNS Page 14 12Zil QUESTION 2.05 (3.00)

n. What are three (3) methods of starting the SI pumps manually, including locations? (1.0)

b. Why must the SI pumps be stopped when aligning the system for hot leg recirculation? (0.5)

c. Where is each of the ECCS pumps (RHR, SI, CCP) taking a suction and discharging to when in the Hot Leg Rectro mode of core cooling? (1.5)

I i

QUESTION 2.06 (3.00)

c. Other than the SIS / Loss of Power load sequencers, what'are two (2) automatic start signals on the CCW pumps? Values NOT required. (1.0)

b. The CCW system is operating with pumps C and D in operation supplying normal CCW loads. Describe the automatic actions that take place in the CCW system if a SIS is received. (1.0)

c. Which CCW flow path from the containment building will be automatically shut on a high flow condition in that line? (0.5) t

d. What two (2) automatic actions take place in the CCW system if high j radioactivity is detected in the system (disregard alarms)? (0.5) l l

1 l

II

(***** CATEGORY 2 CONTINUE 0 ON NEXT PAGE *****) i L_____- - _ - - _ - - _ _ - I

2t__EdEBGENGl_eND_eBN9Bb6L_ELeNI_EVDLUIIQNS Page 15 f2Z11 QUESTION 2.07 (2.50)

a. How are Diesel Generator LOAD (kw), SPEED (frequency), and VOLTAGE affected by taking the Diesel Governor Control Switch to raise / increase if: (1.5)

NOTE: Answer with INCREASE, DECREASE, NO CHANGE !

1. The EDG is supplying its associated ESF bus alone?

2. The EDG is paralleled with the normal power supply to the ESF bus?

b. The EDG is supplying its ESF bus alone when the operator inadvertently trips the output breaker.

1. What prevents the breaker from automatically reclosing? (0.5)

2. What must be done to allow automatic closure of the breaker to the bus in this instance? (0.5) l QUESTION 2.08 (3.00)

o. What provides the driving force for the RCP #3 seal injection? (0.5)

b. To where do the leakoffs from the #2 and #3 seals drain? (1.0)

c. What are two (2) reasons for having #3 seal inj ect ion? (1.0)

d. What portion of the RCP is being protected by the use of the f anti-reverse rotation device? (0.5) 1 L

(***** CATEGORY 2 CONTINUED ON NEXT PAGE *- **)

2t__EUEBGENGL6HD_eBU9BU8L_EL6HI_EY9LVIIQUS Page 16 12Zil QUESTION 2.09 (1.50)

a. What makes the operating time for MSIV closure on a safeguards closure signal much faster than for a normal closure? (0.5)

b. If, during the normal MSIV opening sequence, a Steam Line Isolation Signal occurs, how can fast closure be initiated? (0.5)

c. Which of the following is NOT a Steam Line Isolation Signal: (0.5)

1. Containment pressure greater than 17 psig

2. Steam line pressure <615 psig with RCS >19/0 psig

3. Steam line pressure decreases at a rate >100 psig in 50 seconds with RCS pressure less than 1970 psig and low pressure SI blocked

4. One main steam line pressure > 100 psig lower than any other steam line coincident with lo-lo SG 1evel.

l f'

(***** END OF CATEGORY 2 *****)

E L

g

!i ., .

b ~2t__EL6NI_SYSIEMS_L2all_6ND_EL6HI: WIDE _GENEBIG. Page 17 L BESE9BSIBILIIIES_LIDil l

l l-

' QUESTION 3.01 (2.50) a.. How is the auxiliary feedwater flow rate to the steam generators controlled.following AFW actuation? (1.0)

b. The controller in the control room associated with valve AL-HV-9,'AFW motor operated discharge valve to SG 8, has an amber light marked

" REMOTE" illuminated. What.does this tell the operator about the status of AL-HV-9 control? C0.5) ,

c. Of the conditions'necessary to initiete a motor driven _AFW AFAS state the one(s) that may be bypassed at the main control board. (0.5)

d. What automatic signal will initiate the turbine driven AFW pump but not the motor driven pumps? (0.5)

QUESTION 3.02 (1.50)

The1 reactor is operating at 100% power with all systems functioning l properly. The Pressurizer Pressure Selector Switch is selected to j '

mid-position (P455/P456). Describe the IMMEDIATE response of the components effected in the pressure control system by a failure (HIGH) of

.the P455 pressure transmitter. (1.5)

' QUESTION 3.03 (1.00) l

. Describe HOW and WHY high containment pressure can affect RCS pressure ind ic at io ns '. - (1.0)

QUESTION 3.04 (1.50) a.. With all pressurizer pressure indications being equal, RCS pressure increasing, and both PORV setpoints the same, WHICH PORV opens first and WHY? (1.0)

b. What operator action must be performed before the PORVs can perform their Cold Overpressure Protection function? (0.5) l

(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)

2t__EL6HI_SYSIENS_120%1_86D_EL6NI: WIDE _QENEBIC Page 18 BESEQUSIBILIIIES_ LIQ 11 l

)

QUESTION 3.05 (1.50)

List three (3) Radioactive Liquid Effluent Monitors contained in Technical I Specifications that provide automatic termination of a release. (1.5)

QUESTION 3.06 (2.00)

The reactor is operating at 100% with all systems in a normal lineup with control rods in manual. State the effect each event below will have on the OT Delta T setpoint (Channel II). Answer with INCREASE, DECREASE, or NO CHANGE. No explanation required. (2.0)

c. N42 power range lower detector fails low

b. PT-456 pressurizer pressure transmitter fails high

c. Auctioneered high Tavg unit fails high

d. Power is reduced to 50% with normal pressure and temperature QUESTION 3.07 (2.00)

Match each item in column "A" with one applicable statement in column "B".

"A" "B" (2.0)

a. P-4 1. Auto reset below P-10 I b. P-9 2. Prevents step counter misalignment l

l c. P-12 3. Allows block of SI reactuation

d. C-2 4. 550 Deg F, 2/4 loops

e. C-11 5. Allows reactor trip on turbine trip l 6. >103% power, 1/4 power range channels l

7. Bypasses source range high flux trip 1

1 l

l l

l (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)

2t__EL6NI_SYSIEdS_L28&l_6ND_EL6NI: WIDE _GENEBIC Page 19 BESE9NSIBILIIIES_LIDil QUESTION 3.08 (0.50)

When the Steam Dump Mode Selector Switch is placed in the RESET position, tha control system will: (0.5)

n. Return to the Tavg mode,

b. Return to the Steam Pressure mode.

c. Return to the mode previously selected.

d. Remain blocked until a mode is selected by the operator.

QUESTION 3.09 (1.50)

a. Which controller (s) in the steam dump control system actuate (s) the steam dumps valves as soon as the measured variable exceeds the reference value (i.e., no dead band)? (0.5)

b. All steam dump valves shut when the Lo-Lo Tavg interlock setpoint is reached. How are the steam dumps made available for continued cooldown and which valves are available? (1.0)

L QUESTION 3.10 (3.00) 1

a. What isolation signals are generated DIRECTLY by an SI signal?- (1.0)

b. If a Phase A containment isolation has occurred, what additional l system (s) or flowpath(s) will be affected by a Phase B isolation signal? (0.5) l c. Which isolation signals CANNOT be directly initiated manually? (1.0)

d. What isolation (s) will occur simultaneously with manual Containment Spray initiation? (0.5)

I l

(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)

~

2i__EL8HI_SYSIEUS_L2all_8ND_EL8NI: WIDE _DENEBIQ Page 20 BESEQNSIBILIIIES_11911 QUESTION- 3.11 (2.00)

'e.- What four (4) indications will the operator see on the Digital Rod 8 sition Indication display unit if "A" and "B data has been lost to a wpecific rod? (1.0)

b. It only the "A" data has been lost for a pa-ticular rod, what two (2) indications would the operator see on +Se DRPI display unit? (1.0)

QUESTION 3.12 (3.00)

c. List two-(2) control rod blocks that apply only to automatic control rod withdrawal. (1.0)

b. List two f. 2 ) control rod blocks that are accompanied by main turbine runbacks at the same setpoint, (1.0) c, Arrange the following components in the correct order to reflect the signal path within the Rod Control System. (1.0) 1

1. Power Cabinet

2. Pulser 3 Slave Cycler

4. Master Cycler

5. Reactor Control Unit QUESTION 3.13 (1.50) o.- WHEN and HOW is high voltage removed from the Source Range detectors during a reactor startup? (1.0)

b. If the above did not function, at what point during the power increase would another signal to deenergize the SR High Voltage be generated automatically? (0,5) i l

)

l l

I

(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)

l

~2A__EL8HI_111IENS_12fil_6ND_EL6NI: WIDE _GENEBIG Page 21 l BESEQN21BILIIIE1_L1Dil ;

QUESTION 3,14 (1.50)

s. During a reactor shutdown, a disparity is noted between the readings on the Intermediate Range channels (one is reading significantly higher / lower than the other). A compensating voltage problem is suspected. By observing the IR indication, how can the operator determine whether the probable cause is over or under coutpensation of a channel? (1.0)

b.- The reactor is shutdown and both IR channels are reading slightly less than 10E-11 amps. The signal lead from the IR detector to the IR instrument fails open. What indications, if any, does the operator have that this has occurred? (0.5) t l

l

[

l

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

L _ . _ _ _ _ _ _ _ _ . . _ _ _ _ __ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .

at__BE89IDB_EBIN91ELES_LZ11_INEBdQDINedIGS Page 22 LZil_6ND_CQdEDUENIS_ LID 11_LEUNDodENIeLS_E88dl QUESTION 4.01 (3.00)

a. During a heatup from Mode 5 to Mode 3 with RCS temperature below the indicating range of the RCS Narrow Range Temperature Channels, which indication defines "RCS Temperature" per GEN 00-002, " Cold Shutdown to Hot Standby?" (0.5)

b. At what minimum temperature is one RCP. required to be operating? (0.5)

c. When heating up from Mode 5 to Mode 3, at what point is the first Mode Change made? (0.5)

d. What position should the Motor Operated Auxiliary Feedwater Valves (AL HV-5, 7, 9, ll) be kept in as much as possible, even in Modes 4, 5, and 6. EXPLAIN WHY. (1.5)

QUESTION 4.02 (2.50)

Answer the following questions with regard to operation with " bottled-up" steam generators;

a. What constitutes a " bottled-up" steam generator? (0.5)

b. If all four steam generators are " bottled-up", how should heat be {

removed from the RCS? (1.0)

c. List four (4) negative consequences of continuous operation with

" bottled-up" steam generators in Mode 2 f or prolonged periods. (1.0) l l

l l

l l (***** CATEGORY 4 CONTINUED ON NEX1 PAGE *****)

i i

j

4. Rg6ClQB_EBINCIELE$_[Zil_ldEBdQQXN6 DIG $ Page 23 LZil_6HD_G9dE90ENI$_L1011_LEUNQ6 DEN 16L1_EX6dl f 1

l QUESTION 4.03 (3.00) l Assume the unit is in cold shutdown with the RCS drained for HALF LOOP j operation. i I

a. What is the best (earliest) indicator of RHR pump cavitation? (0.5) l Consider the entire plant, not just the Control Room.

b. State two (2) indications in the control room that would be indicative of RHR pump cavitation. (0.5)

c. If all core cooling is lost and no operator action is initiated, how much time may elapse prior to:

1. Boiling begins; (0.25)

2. Core uncovery? (0.25)

d. If both trains of RHR become inoperable, what are three (3) alternate means of decay heat removal per OFN 00-015, " Loss of Shutdown Cooling (RHR)?" (1.5)

QUESTION 4.04 (2.00)

a. List six (6) parameters associated with RCP operation that require stopping / tripping of the affected RCP if exceeded. Setpoints NOT required. (1.5)

b. What is the maximum reactor power above which a RCP restart should not be attempted? C0.5)

QUESTION 4.05 (1.00)

For a dropped control rod, Tave/ Tref mismatch is initially maintained by taking manual control of: (1.0) s

a. RCS boro.) concentration

b. Turbine load

c. Individual control rod banks

d. Individual control rod groups

(***** CATEGORY 4 CONTINUED ON NEXT PAGE *****)

dz__BE6CI98_EBIUCIELES_LZ11_IBEB0001N60193 Page 24 LZ11_eUD_G90E9NENIS_L191).LEUURodENI6LS_ Exed)

QUESTION 4.06 (2.00) ,

1 l

A reactor trip has occurred (without SI). All parameters respond normally for post-trip conditions except that two rod bottom lights did not illuminate. What actions are called for as a result? Do not include verifications (assume all actions are successfully but be specific as to actions performed. (2.0) i QUESTION 4.07 (1.00)

Assuming a secondary heat sink. is available and r.dverse containment l conditions do not exist, which one of the following sets of conditions would allow termination of SI? (1.0)

PZR LVL SUBC00 LING (SMM) PRESSURE

a. 12% 45 deg stable l

l b. 20% 80 deg decreasing 1

I

c. 4% 60 deg increasing

d. 30% 25 deg stable l

l QUESTION 4.08 (2.00)

{

i For each of the parameters listed below, describe how they should respond

! if natural circulation flow exists as per EMG ES-03 (SI TERMINATION). (2.0)

a. Core exit thermocouple

b. Steam generator pressures l

l

c. RCS hot leg temperatures

d. RCS cold leg temperatures l'

l l

l

(***** CATEGORY 4 CONTINUED ON NEXT PAGE *****)

L_____ ____ !

42__BEeGI98_EBINCIELES_LZ31_IBEBd9010801G3 Page 25 LZil_eND_CQUEQNENIS_L1911_LE9NDodENIoLS_EXedl QUESTION 4.09 (3.00)

n. What two (2) conditions require that ADVERSE CONTAINMENT process parameter values be used in the ERG's? INCLUDE VALUES. (1.0)

b. If ADVERSE CONTAINMENT conditions and values have been used, under what conditions may the operators again use the normal containment values? (1.0)

c. Why do ADVERSE CONTAINMENT conditions require the use of a different set of values than for normal containment conditions? (1.0)

QUESTION 4.10 (2.50)

a. What three (3) parameters comprise the Technical Specification Safety Limits for WCGS? (1.5)

b. What Operational Condition (Mode) must be met, and within what time, if a Safety Limit is exceeded while in Mode 1? (1.0)

I

\

QUESTION 4.11 (1.50)

Arrange the following events in order of occurrence during a startup from hot standby to minimum load. (1.5)

a. Place the Steam Dump Mode Controller in Tavg Mode

b. Block the Source Range High Flux Trip

c. Start one Main Feedweter Pump (turbine) i

d. Block the Source Range Flux Doubling Transfer trip I

e. Place Main Feedwater Pump Turbine Speed controls in AUTO

f. Place the Turbine Generator on the line 9 Block the Power Range Low Power Trips l l

QUESTION 4.12 (0.50) l What is the minimum qualification necessary to assume the control room command function if the Shift Supervisor is absent from the control room l when the unit is is Mode 5 or 6 (per the Tech Specs)? (0.5) l l

l l l

(***** CATEGORY 4 CONTINUED ON NEXT PAGE *****)

St__BEaQIDB_EBINCIELES_LZil_IBEBdQDINad1GS Page 26 LZil_86D_CQUEQUENIS_L1011_LEUNDadENIaLS_E8adl QUESTION 4.13 (1.00)

Which of the following external radiation exposures would inflict the greatest biological damage? (1.0)

a. 1 RAD of neutron b 1 REM of neutron

c. 1 Roentgen of beta

d. 1 RAD of gamma l ,

I i

I 1

l'

(***** END OF CATEGORY 4 *****)

(********** END OF EXAMINATION **********) l I

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

~ ..

1___BE8CIQB_EBINGIELES_LZ11_IHEBdQQXNed193 .Page 27 LZ11_6HD_G0dEONENIS_L1111_LEUNDodENI6LH_EBodl s

ANSWER 1.01 (1. 0 0 ) -

d (1.0)

REFERENCE Suberitical Multiplication Lesson Text 192008K103 3.9/4.0 192008K103 ..(KA's)

ANSWER 1.02 (1.00) b (1.0)

REFERENCE I'

Reactivity and Delayed Neutrons Lesson Plan 192002K111 2.9/3.0 192002K112 2.4/2.5 192002K111 192002K112 ..(KA's) l ANSWER 1.03 (1.00) c (1.0) 4 l

REFERENCE <

Reactivity Coefficients Lesson Plan, pg 15, 16 192004K106 3.1/3.1 192004K106 ..(KA's) l ANSWER 1.04 [1.00) b.

l

(***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)

_ _ _ _ - . - _ _ _ _ _ _ _ _ _ _ . __________-_-_L

i : '.

1

.iz__BEoGIDB_EBINGIELES_1Z11_IHEBdQDINedIGH Page 28 LZ11_oND_G9dEDNEUIS_111&l_LEUNDedENIeLS_Ehedl l

l REFERENCE l Excess Reactivity and Chemical Shim Lesson Text, Section 4 l 192005K106 2.6/2.9 t

! 192005K106 ..(KA's) l l

ANSWER 1.05 (1.00) b (1.0) l l

REFERENCE Reactivity and Delayed Neutron Lesson Plan 192003K107 3.0/3.0 192003K107 ..(KA's) l ANSWER 1.06 .(1.00) b (1.0)

REFERENCE Reactivity Coefficients Lesson Text 192004K113 2.9/2.9 192004K113 ..(KA's)

ANSWER 1.07 (1.00) a (1.0) i REFERENCE I

! Fission Product Poison Lesson Plan l 192006K103 2.7/2.8 1

192006K103 ..(KA's) l l

I l

l l (***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)

1 L_.-__-. .__ _ _ _ - _ _ - _ _ _. _ . - _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ________

l l

l '.

Iz__BE6CIQB_EBINCIELES_IZ11_IBEB0001NedICS Page 29 l

LZ11_8UQ_G9dEQNENI1_L1111_LEUNDodENI6LS_E88dl l

ANSWER 1.08 (1.00)

'd (1.0)

REFERENCE Excess Reactivity and Chemical Shim Lessen Text, pg 25 192005K107 2.5/2.8 192005K107 ..(KA's)

ANSWER 1.09 (1.00) b.

REFERENCE Period Equation Lesson Text 192008K105 3.8/3.9 192008K105 ..(KA's)

ANSWER 1.10 (1.00) a (1.0)

REFERENCE {

Suberitical Multiplication Lesson Text 192008K104 3.8/3.8 I 192008K104 ..(KA's)

ANSWER 1.11 (1.00) d (1.0) !

i l

(***** CATEGORY 1 CONTINUED ON NEXT PAGE *****) )

1

~11__BEeQIQB_EBINCIELES_LZ11_INEBdQQXNedICS Page 30 LZil_6NQ_QQUEQUENIS_L11&l_LEUNQadENIeLS_Ehed) .

i REFERENCE Core Age Effects and PWR Response Lesson Text 192008K121 3.6/3.8 192008K117 3.3/3.4 192008K121 192008K117 ..(KA's)

ANSWER 1.12 (1.00)

The two critical rod positions should be the same (1.0)

REFERENCE Reactivity Coefficients Lesson Text 192008K110 3.3/3.4 192008K110 ..(KA's)

ANSWER 1.13 (1.00) 1 d (1.0)

REFERENCE 1

l Heat Transfer Modes Lesson Plan, pg 33 1 193008K103 2.8/3.1 l

193008K1L ..(KA's) l l

ANSWER 1.14 (2.00) 1

a. lower j b. higher j c. same as I d. lower C.5 each)

REFERENCE Heat Balance L(sson Plan and Text l

015000K504 2.6/3.1 015000A101 3.5/3.8* 193007K108 3.1/3.4 015000K504 015000A101 193007K108 ..(KA's) l l

l l

l

(***** CATEGORY 1 CONTINUED ON NEXT PAGE *****'

: 1 It__BE69IDB_EBINGIELES_1Zil_IHEBdQDIN8dICS Page 31 LZ11_6NQ_PQUEQUENIS_11111_LEUN06dENI6LS_EEodl i

i ANSWER 1.15 (2.00)

n. Decrease ]

b. Increase ;

c. Increase 4

d. Decrease C.5 each)

REFERENCE Introduction to Accident Analysis Lesson Plan !

193008K1033.4/3.6 f,

193008K105 ..(KA's)

ANSWER 1.16 [1.00) e, b (2 at 0.5 each) (c and d not required)

REFERENCE f

i Natural Circulation Lesson Text 153008K122 4.2*/4.2*

4 193008K122 ..(KA's)

) ANSWER 1.17 (1.00) l J

S.

REFERENCE -

Properties of Fluids Lesson Text, pg 54 191002K102 2.7/2.9 191002K102 ..(KA's)

ANSWER 1.18 (1.00) a (1.0)

(***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)

l 12__BE8CIDB_EBINCIELES_LZ11_INEBdDDXN651G3' Page 32 l LZ11_6ND_CDdEDNENIS_L11&l..LEUNDedENIeLs_gxed)

-1 I

REFERENCE Properties of Fluids Lesson Text 191002K102 2.7/2.9 [

191002K102 ..(KA's) i ANSWER 1.19 (1.00)

a. ECP lower than ACP (0.50) !

b. ECP lower than ACP (0."D)

REFERENCE Reactivity Coef ficients and Fission Product Poison Lesson Plans 001015.?,207 3.6/4.2 i

'001010A207 ..(KA's)

ANSWER 1.20 (1.00)

n. OUTER

b. INNER ,

l REFERENCE Pressurized Thermal Shock Lesson Plan ( "

Materials Review 002000K518 3.3/3.6 002000K518 ..(KA's)

ANSWER 1.21 (2.00)

a. Tsat for 2250 psia (2235 psig) = 653 degrees F (+/- 1 degree) (.5)

Subcooling margin = Tsat - Thot = 653 - 613 = 40 degrees F C+/- 1 degree) (.5) {

b. Subcooling margin decreases (.25) because Thot will increase as power {

increases (.375) while pressure remains the same(.375).

f (***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)

i

: l l 1___BE6CIQB_EBINCIELES_LZ11_IDEBUDDXN8 DIGS Page 33 LZ11.6ND_G9dE9NENI1_L11hl_LEUNDodENI6LS_E86dl i

i REFERENCE' l i

STEAM TABLES 001000K556 4.2/4.6 001000K556 ..(KA's) 1 1

ANSWER 1.22 (1.00) l e (1.0) l REFERENCE i Post Accident Primary Radiochemistry Lesson Text 004000A101 2.9/3.8 004000A101 ..(KA's) l 1

l 4

i i

1 2t__EMEBGENCX_6HD_6BNDBdeL_EL6NI_EY9LUIIQU$ Page 34 12Zil l l

l.

ANSWER 2.01 (3.00)

a. Auxiliary'Feedwater (0.5)

CCW (0.5)

Spent Fuel Pool Cooling (0.5)

b. - ESW pumps start

- SW supply to ESW valves shut {

- SW return from ESW valves shut

- ESW return to Ultimate Heat Sink open

--CCW HX outlet valves shut

- Pump suction traveling screen starts

- Screen wash supply valves open

- ESW pump air release valves close

- ESW room cooler starts, supply and discharge dampers open ;

- CCW HX supply valves open

( 5 at 0.3 each)

REFERENCE I Essential Service Water System Lesson Text, pg 21 - 23, 32 ;

Drawings MK2EF01, MK2GD01, M12EF02 076000K101 3.4/3.3 076000K119 3.6*/3.7 076000G007 2.8/3.0 076000K101 076000K119 076000G007 ..(KA's)

ANSWER 2.02 (3.00)

[ a. - Auxiliary Feedwater Flow Control Valves (0,5)

- S/G Atmospheric Reliefs (0.5)

- Main Feedwater Control Velves (0.5)

b. A release of N2 into the room lowers the 02 level in the room to less than a breathable level (1.0). Accept any discussion reflecting this concept.

c. Answer 1 (1% to 5% higher) (0.5)

REFERENCE Instrument and Service Air System Lesson Plan, pg 15, 16, 28 078000K302 3.4/3.6 078000G001 2.9/3.1 078000K302 078000G001 ..(KA's)

(***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)

~

l 31__EdEBGENCX_eND_eBN9BdeL_EL6NI_EV0L9110NS Page 35 L2Z11 ANSWER 2.03 (3.00) 12 gpm seal leakoff (0.25) back to CCP suction (this value may vary a.

. from 0.8 to 20 gpm per 0FN-005. If value other than 12 gpm used,

}f adj ust other values accordingly. j 20 gpm back to RCS via RCP shaft leakage (0.25) 55 gpm charging into RCS (0.25) 75 gpm letdown flow (0.25) l

b. 1. cir, open

2. sir, open

3. air, open

4. motor, as . is

5. air, closed

6. air, open (0.125 for each motive force, 0.125 for each position)

c. RWST to CCP suction valves open (HV-1120 & E) (0.25) -

VCT' Outlet Isolation Valves close (HV-1128 & C) (0.25) :

REFERENCE CVCS Lesson Plan, pg 22, 23, 33 - 34, 50 CVCS Lesson text, pg 31, 32 0FN 005, RCP Malfunctions 004010A204 3.6/4.2 004000K104 3.4/3.8 004000G007 T.3/3.3 i 004010A204 004000K104 004000G007 ..(KA's) i ANSWER 2.04 (3.00)

a. The operator var ies the setpoint (position) of the RHR heat exchanger i discharge valve to vary the RCS coolant flow rate through the HX (0.5) 1 The RHR HX bypass valve automatically depositions to maintain the l required flow through the RHR train (0,5) of 3800 gpm. HX BPV may be j manually varied using the local controller (acceptable for 0.5) l

b. Low RWST level (0.3) of 36% (0.1) and SI signal (0.4)

c. Sump to RHR pump suction valves open (0.4) and the RWST to RHR pump suction valves shut (0.A). ,

l

d. By resetting the SI signal with the 2 reset switches located on main l control board RL018 (0.4). Also acceptable: SI reset pushbutton, f reset "RWST switchover", remove power tr valves.

I I

l l

(***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)

_ - _ _ _ - _ - _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - l

p i

I I 2t__EDEBQEN91_6HD_6BN9BdeL_EL6HI_EVOLUIIQNS Page 36 l

L2Zil l

REFERENCE

[-

f. RHR Lesson Text, pg 18, 19, 32 - 33 l 005000K113 3.3/3.5 005000K403 2.9/3.2 005000K411 3.5*/3.9*

I 005000K113 005000K403 005000K411 ..CKA's) l l

ANSWER 2.05 (3.00)

a. - Switch on the MCB (0.33)

- Switch on the cubicle door of the breaker (0.33)

- mechanical "close" pushbutton inside the cubicle door (0.33)

- Manual SIS initiation also acceptable.

b. During the switchover, they will have no mini-flow protection (0,5),

c. RHR: suction - containment sump (0.25) discharge - RCS hotlegs (0.25), suction of CCPs (0.25), suction of SI pumps (0.25)

CCP: suction - discharge of RHR pumps discharge - RCS cold legs (0.25)

SI: suction - discharge of RHR pumps discharge - RCS hot legs (0.25)

REFERENCE ECCS and SI Lesson Text, pg 53, pg 75 - 80 006000A401 4.1/3.9 006000K406 3.9/4.2 006020K401 2.7/3.0 '

006000A401 006000K406 006020K401 ..(KA's)

ANSWER 2.06 (3.00)

a. - CCP started (0.5) if no CCW pump running in that train already

- Low discharge pump discharge pressure (0.5) with the parallel pump running.

b. Radweste Building loads (0.33) and Post Accident Sample System loads (0.33) will isolate. The CCW cooler bypass valves (temperature control valves) will shut (0.33).

c. RCP thermal barrier return flow (0.5)

d. -Surge tank vent (D.25) and surge tank demin water makeup valves (0.25) shut.

(***** CATEGORY 2 CONTINUED ON NEXT fe Z *****)

2t__EMEB9ENCY_680_6BN9806L_EL6NI_EY9LUIIQUS' Page 37 12Z11 REFERENCE CCW Lesson Text, pg 26, 35, 36 008000K401 3.1/3.3 008000A204 3.3*/3.5 008000A101 2.8/2.9 008000K401 008000A204 On8000A101 ..(KA's)

ANSWER 2.07 (2.50)

n. (6 at 0.25 each) ;

1. load: no change I speed: increase (accept no change if reference made start due to undervoltage) voltage: no change )

2. load: increase speed: no change voltage: no change

b. 1. EDG output breaker anti-pumping logic (0.5)

2. The local operator must take the MASTER TRANSFER SWITCH from AUTO to LOCAL / MANUAL then back to AUTO (0.5). Also acceptable; deenergize DC control power to the breaker, take EDG breaker handswitch to nay position other than normal.

REFERENCE Emergency Diesel Generator Lesson Plan, pg 35, 40 064000A203 3.1/3.1 064000A214 2.7/2.9 064000A401 4.0/4.3 064000A203 064000A214 064000 ado 1 ..(KA's)

ANSWER 2.08 (3.00) l

n. Water level in a standpipe (0.5)

b. #2 - RCDT (0,5) l #3 - Containment Sump (0.5) l '

1 l c. 1. Lubrication of the seal (0.5) l 2. Prevent radioactive gases or water from #2 seal leakoff from I entering the containment atmosphere (0.5) l

d. motor (0.5) l l

' i l

(***** CATEGORY 2 CCNTINUED ON NEXT PAGE *****) f o - - __ _--__ ______ _ _ _ _ _ _ I

4 I

l L .- .

2t__EDEBQENGI_eND_eEN9Bb6L_EL6NI_EVQLUI19NS Page 38 l

L2Z11 l

l

, REFERENCE RCP Lesson Text, pg 16, 18-29 003000K103 3.3/3.6 003000A203 2.7/3.1 003000K103 3.3/3.6 003000A203 ..(KA's)

ANSWER 2.09 (1.50)

a. The valve is operated by a high pressure hydraulic accumulator (0.5) instead of the normal hydraulic pump.

b. Depress AB HS 79 and AB HS 80 (0.5). Accept switch names.

c. 4 (0.5)

REFERENCE Main and Reheat Steam Lesson Plan, pg 19 - 20 039300K405 3.7/3.7 039000K405 ..(KA's)

(***** END OF CATEGORY 2 *****)

2t__r_LeNI_11SIEdS_1281)_6ND_ELeNI: WIDE _QENEBIC Page 39 BESEQU2121L111EA_11Dil )

l i

ANSWER 3.01 (2.50)

a. When the total flow (0.25) to each SG is >300 gpm (0.25), the motor operated discharge valve starts to throttle closeo (0.5) to maintain flow below 300 gpm.

b. Control of the valve is at the Auxiliary Shutdown Panel (0.5).

c. Trip of both main feed pumps (0.5) may be bypassed.

d. UV on NB01 or NB02 safeguards buses (0.b)

REFERENCE AFW Lesson Text, pg 18, 26, 36 061000K402 4.5/4.6 061000K404 3.1/3.4 061000K601 2.5/2.8*

k 061000K402 061000K404 061000K601 ..(KA's) j ANSWER 3.02 (1.50)

- both spray valves would open (0.5)

- PORV 455A would open (0.5) .

- All PZR heaters would turn off (0.5) ]

REFERENCE PZR Pressure and Level Control Lesson Text, pg 12 016000K308 3.5*/3.7*

016000K308 ..(KA's)

ANSWER 3.03 (1.00)

Elevated containment pressures can cause indicated RCS pressure to be lower than actual pressure (0.5). The pressure transmitters are referenced to atmospheric pressure (0.5), so if the atmospheric pressure increases, the indicated pressure would decrease due to the decreased dp. Accept any explanation that describes this concept.

(***** CATEGORY 3 CONTINUE 0 ON NEXT PAGE *****) f i

2t__ELoNI_S1SIENS_12Dil_oNQ_EL6NI: WIDE _DENEBIG Page 40 BESEQNSIBILIIIEh_L1011 REFERENCE PZR Pressure and Level Control Lesson Text, pg 57 010000K601 2.7/3.1

! 010000K601 ..(KA's) l ANSWER 3.04 (1.50)

o. The PORV receiving its signal from the Master Pressure Controller i (455A) opens first (0.5) because of the integral function in the controller (0,5).- The other PORV does not receive this signal conditioning.

b. The system must be manually armed (0.5) from the MCB.

REFERENCE PZR Pressure and Level Control Lesson Text, pg 23 - 24 010000K403 3.8/4.1 010000K403 ..(KA's) l ANSWER 3.05 (1.50)

- Liquid Radweste Discharge Monitor (RE-18) ;

- Steam Generator Blowdown Discharge Monitor (RE-52)

- Turbine Building Drain Monitor (RE-59)

- Secondary Liquid Waste System Monitor (RE-45)

(3 required at 0.5 each)

REFERENCE Tochnical Specifications, Table 3.3-12 073000K401 4.0/4.3 I

! 073000K401 ..(KA's) l l

l l l ANSWER 3.06 (2.00) l

a. decrease (0.5) no ch nge b5) l d. increase (0.5) l l (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) j L __ _

i

2___EL6NI_SISIEd1_I2all_6ND_EL6NI: WIDE _GENEBIC Page 41 BESEQNSIBILIIIES_IIDil REFERENCE Rocctor Protection Lesson Text, pg 23-27 012000A205 3.1*/3.2* 012000K611 2.9*/2.9 012000A205 0'12000K611 ..(KA's)

ANSWER 3.07 (2.00)

a. 3

b. 5

c. 4

d. 6

e. 2 (5 at 0.4 each)

REFERENCE Reactor Protection System Lesson Text, pg 38-45 012000K406 3.2/3.5 012000K610 3.3/3.5 012000K406 012000K610 ..(KA's)

ANSWER 3.08 (0.50)

"a" - Return to the Tave Mode (0.5)

REFERENCE Steam Dump Lesson Text, pg 13 ANSWER 3.09 (1.50) l a. Plant trip controller (0.25) l Steam pressure controller (0.25) l

b. Cycle both steam dump interlock switches through the BYPASS interlock l

position (0.5). This makes the Bank No. 1 dump valves available for operation (0.5).

l l

l

(***** CATEGORY 3 CONTINUED ON N?XT PAGE *****)

w___-_-____- _ _ _ _ .

-2t__EL6NI_SYSIEdS_f2Dil_eUD_EL6NI: WIDE _GENEBIC Page 42 BESEQUSIDILIIIEf_LIDil REFERENCE l Stesm Dump Lessun Text, pg 8, 9, 17 041020K603 2.7/2.9 041020A402 2.7*/2.9*

041020K603 041020A402 ..[KA's)

ANSWER 3.10 (3.00)

a. - CIS phase A !

- SG Blowdown and Sample

- Feedwater (0.33 each)'

b. LcW supply and return to RCPs (0.5)

c. - Main Steam Line Isolation

- Main Feedwater Isolation

- Steam Generator 81owdown and Sample Isolation (0.33 each)

d. CIS Phase B (0.5)

REFERENCE ESFAS Lesson Text, pg 28 - 33 103000K102 3.9/4.1* 103000K406 3.1/3.7 000069A202 3.9/4.4 f 103000K102 103000K406 000069A202 ..(KA's)

ANSWER 3.11 (2.00)

n. - Rod bottom light (0.25)

- General Warning light (0.25)

- Urgent Failure alarm (0.25)

- Rod Deviation alarm (0.25) l (also accept Data A cabinet failure and Data B cabinet failure)

b. - General Warning light (0.5) -

l - Every other LED will light on the display as the rod is moved (0.5) l (also accept Data A cabinet failure) l l

l l

l I

(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)

l-L l :22__EL6NI_SYhIEDS_LS811_6ND_EL6NI: WIDE _QENEBIQ Page 43 l BESEQNSIBILIIIES_11011 l

l REFERENCE RPIS Lesson Text, pg 19, 20 014000K403 3.2/3.4* 014000A206 2.6*/3.0*

1 014000K403 014000A206 ..(KA's)

ANSWER 3.12 (3.00)

a. - High Bank D position (0.5) C-11

- Low power interlock (0.5) C-5

b. - OT delta T (0,5) C-3 i - OP delta T (0.5) C-4

c. 5, 2, 4, 3, 1 (0.25 for each manipulation to put in the correct order) l REFERENCE 1

l Rod Control Lesson Text, pg 30, 51 001000K403 3.5/3.8 001000K407 3.7/3.8 001000K403 3.5/3.8 001000K407 ..(KA's)

ANSWER 3.13 (1.50)

a. When IR reaches 10E-10 amps (0.5) on 1/2 channels (P-6), the SR high level trip is blocked which deenergizes the SRHV (0.5).

b. 10% (0.5) Accept P-10 REFERENCE Excore Nuclear Instrumentation Lesson Text, pg 45 015000K401 3.1/3.3 015000K401 ..(KA's) l l

1 l

l l

(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) g

______.__________________d

f l

l : .

l l

2t__EL68I_SISIEUS_12011_6ND_ELeUI: WIDE _GENEBIQ Page 44.

l BESEDNSIBILIIIES_ LIQ 11 l

l !

)

l l

l ANSWER 3.14 (1.50) 1 l

a. If the higher ' reading channel does not decrease to its normal shutdown reading, it is probably undercompensated (0.5). If the lower reading l channel decreases to below its normal shutdown reading, it is probably overcompensated (0.5).

I b. none (0.5), except when neutron level is increased and no meter I response is noted.

l REFERENCE I

Excore Nuclear Instrumentation Lesson Text, pg 76 l 015000A201 3.5/3.9 015000A201 3.1/3.5*

015000A201 3.5/3.9 ..(KA's) l l

l I

1 I

1 1 i l (***** END OF CATEGORY 3 *****)

42 ._BE6CIQB_EBINCIELgS_LZil_IBEB0001860101 Page 45 flil_6ND_GQUEDNENIS_f1Dil_LEUNDodENI6LS E86dl ANSWER 4.01 (3.00)

a. The highest loop temperature as determined from the RCS Wide Range Temperature Computer or Wide Range Temperature Recorders (0.5).

b. 160 deg F (0.5)

c. >200 deg F (0.5)

d. Open (0.5). When the controller is in the CLOSED position, the field in the motor remains energized, which shortens the life of the actuator (1.0)

REFERENCE GEN 00-002, Rev 13, pg 2, 9, 10 061000GC10 3.5/3.6 003000G010 3.3/3.6 061000G010 003000G010 ..(KA's)

ANSWER 4.02 (2.50)

a. MSIVs and FWIVs shut (0.5) b, Feed one SG (0.3) from the AFW (0.3) while steaming the same SG through its Atmospheric Relief Valve (0.4).

Also accept RHR (0.5) if < 350 deg F (0.5)

c. - increased corrosion

- core power mal-distribution

- feedline cracking

- nozzle transient / fatigue

- increased feedwater cycling (slug flow)

- loss of proper chemistry control j

(4 required at 0.25 each) l REFERENCE l

GEN 00-003, Hot Standby to Minimum Load, Rev 16, pg 3 l

035000G010 3.2/3.4 l

035000G010 ..[KA's) l

(***** CATEGORY 4 CONTINUED ON NEXT PAGE *****)

i I

Sz__BE6CIDB_EBINGIELES_LZ12_IBEB0001N6010$ Page 46 LZ11_eUD_CQUEQUEN1S_ LID 11_LEUNDedENIeLS_EE601 l

l l

l ANSWER 4.03 (3.00) l l

a. Local observation of pump noise (0.5)

b. RHR pump flow, pump, emperage, or pressure oscillation, RCS loop level l oscillation. Accept any two for 0.25 each.

1 l

c. 1. 30 minutes (accept 8 - 45) (0.25)

2. 2.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months (accept 1.0 - 4.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ) (0.25) l j d. - dump from SI accumulators

- RCS feed & bleed from RWST l - Spent fuel pool cooling system l

(3 required at 0.5 each) l REFERENCE OFN 00-015, Loss of Shutdown Cooling, Rev 5, pg 111, 8- 12, 39, 41 GEN 00-007, RCS Drain Down, Rev 9, pg 10 000025A207 3.4/3.7 000025K101 3.9/4.3 000025K301 3.1/3.4 000025A207 000025K101 000025K301 ..(KA's) l l

ANSWER 4.04 (2.00) i l n. - #1 seal dp

! - motor bearing temperature

- #1 seal inlet temperature l

l - pump bearing temperature l

- frame vibration i

- shaft vibration

! - #1 seal leakoff

- Containment pressure

- RCS pressure (6 at 0.25 each)

b. 5% (0,5)

REFERENCE 1

l OFN 00-005, RCP Malfunctions, Rev 6, pg 1 - 111 EMG-E0 l 003000A202 3.7/3.9 0030000010 3.3/3.6 003000A202 003000G010 ..(KA's) 1

(***** CATEGORY 4 CONTINUED ON NEXT PAGE *****)

I : :

e at__BE6CIQB_EBING1ELES_fZil_IBEBUDDINed1CS Page 47 l LZ11.6ND_CQUEDNEUIS_L1Dil_LEVNDedENI6LS_E86dl l

ANSWER 4.05 (1.00) 1 b (1.0) l REFERENCF O F N 0 0 'J 11, Dropped or Misaligned Rod, and Realignment, Rev 2, pg 1 000003A105 4,1/4.1 000003A106 4.0/4.1 1

000003A105 000003A106 ..(KA's)

ANSWER 4.06 (2.00)

- Start both boric acid transfer pumps (0.6)

- Stop VCT makeup (0.6)

- Open immediate borate valve t<i charging pump suction (0.6)

- Energize backup heaters (0.2)

REFERENCE OFN 00-009, Immediate Boration, Rev 1 000024K301 4.1/4.4 000024K302 4.2/4.4 000024G010 4.5*/4.5 000024K301 000024K302 000024G010 ..(KA's)

ANSWER 4.07 (1.00) o (1.0) i REFERENCE EMG E-1, Loss of Reactor or Secondary Coolant, Rev 1, pg 6 013000G001 4.0/4.1*

013000G001 ..(KA's)

I

(***** CATEGORY 4 CONTINUED ON NEXT PAGE *****)

l 4t__BE69I9B_EBINGIELES_LZ11_IBEBdDDINedIGH Page 48 )

LZ11_eUD_GQUEQUENIH_L1011_LEUNDodENIeLS_EXedl 1 ANSWER 4.08 (2.00) l

n. Ch*T 's : Stable or decreasing (0.5)

b. SG pressures: Statie or decreasing (0.5) '

c. RCS hot leg: Stable or decreasing (0.5)

d. RCS :olo leg: At Tsat for SG pressure (0.5)

REFERENCE EMG ES-03, SI Termination, Rev 1, pg 18 000009A237 4.2/4.5 1 000009A237 ..(KA's)

ANSWER 4.09 (3.00) o< Containment pressure > 5 psig (0.5) or Containment radiation >10E5 R/hr (0.5)

b. Containment pressure <5 psig (0.5) Cif 5 psig was exceeded) and the radiation dose must be verified to be <10E6 RADS (0.5) (if 10E5 R/hr was-exceeded)

c. Adverse Containment conditions may cause significant errors in the indications of instruments located inside cor.tainment (1.0).

REFERENCE I

Wes..nghouse Owner's Group Emergency Response Guidelines Executive Volume, Generic Issue - Generic Instrumentation, Rev 1, pg 21 000009k316 3.8/4.1 000009K318 3.9/4.3 103000G010 3.3/3.6 000009K321 4.2/4.5 000009i:316 000009K318 103000G010 000009K321 ..CKA's)

ANSWER 4.10 (2.50)

s. RCS pressure, thermal power, Tavg (RCS temperatures) (3 ct 0.5 each)

b. Hot Standby (0.5) within one hour (0.5) 1 l

l l

l

(***** CATEGORY 4 CONTINUED ON NEXT PAGE *****)

u______ .-__ __ __ - -_ _ _

l I

$___BPSGI98_EB1991ELES_1Z11_INEBd901N80103 Page 49 l LZ11_eUD_C9dE0NENI1_11011_LEUNDedENIeLS_Exodl REFERENCE Technical Specification 2.1 1 002000G005 3.6/4.1 002000G005 ..(KA's)

ANSWER 4.11 (1.52) d, 6, c, t, g, a, e OR do b, c, e, f, g, a (0.25 for each manipulation required to place i n tt'.e correct order).

1 REFERENCE GEN 00-003, Hot Standby to Minimum Load, Rev 16, 194001A102 4.1*/3.9 194001A102 ..(KA's)

ANSWER 4.12 (0.50)

R0 licensed (0,5)

REFERENCE Technical Specifications 6.2.2 194001A103 2.5/3.4 194001A103 ..(KA's)

ANSWER 4.13 (1.00) l a (1.0)

REFERENCE 10CFR20.4 1 194001K103 2.8/3.4 l

194001K103 ..[KA's) l l

(***** END OF CATEGORY 4 *****)

(*****2**** END OF EXAMINATION **********)

TEST CROSS REFERENCE Page 1 QUESIl0B _Y8LUE BEEEBEURE_

1.01 1.00 9000162 1.02 1.00 9000161 1.03 1.00 9000163 1.04 1.00 9000164 1.05 1.00 9000171 1.06 1.00 9000172 l 1.07 1.00 9000173 1.08 1.00 9000174 ;

1.09 1.00 9000175 l 1.10 1.00 9000178 1.11 1.00 9000179 1.12 1.00 9000181 1.13 1.00 9000165 1.14 2.00 9000167 {

1.15 2.00 9000176 1.16 1.00 9000180 1.17 1.00 9000169 .

I 1.18 1.00 9000177 1.19 1.00 9000166 1.20 1.00 9000168 1.21 2.00 9000170 1.22 1.00 9000182 25.00 ;

2.01 3.00 9000183 2.02 3.00 9000184 2.01 3.00 9000185 2.0, 3.00 9000186 f 2.05 3.00 9000187 2.06 3.00 9000188 2.07 2.50 9000189 i i

2.08 3.00 9000190

j. 2.09 1.50 9000191 !

25.00 3.01 2.50 9000192 3.02 1 60 9000193 3.03 1.00 9000194 3.04 1.50 9000195 3.05 1.50 9000196 3.06 2.90 9000197 3.07 2.00 9000198 3.08 0.50 9000199 3.09 1.50 9000200 3.10 3.00 9000201 3.11 2.00 9000202 l_ 3.12 3.00 9000203 3.13 1.50 9000204 3.14 1.50 9000205 25.00 4.01 3.00 9000208 >

L _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ __ _ _ _i

I L -

[

TEST CROSS REFERENCE Page 2 f

QUE111GN _Y6LUE BEEEBENGE_

4.02 2.50 9000209 4.03, 3.00 9000206 4.04 2.00 9000207 4.05 1.00 9000213 4.06 2.00 9000215 4.07 1.00 9000211 4.08 2.00 9000212 4.09 3.00 9000214 4.10 2.50 9000217 4.11 1.50 9000210 4.12 0.50 9000216 4.13 1.00 9000218 25.00 100.0

NRC LICENSE EXMIRATION HAHDOLIT EQUATIONS COISTANTS, MD C0HVERSIONS 6^=m*C*deltaT p 6=U*A*deltaT P = Po*10sur*(t) P = P *et /T SUR = 26/T T = 1*/p + (p-p)/I p T=1/(p-p) T = (p-p)/Xp p = (Xeff-1)/Keff = deltaKeff/Keff p = 1*/TKeff + feff/(1+1T) .

A = in2/tg = 0.693/t 3C = 0.1 seconds-1

~

I = Io*e "*

CR = S/(1-Keff)

R/hr = 6*CE/d2 feet Water Parameters 1 gallon = 8.345 lbm = 3.87 liters 1 ft3 = 7.48 gallons Density 9 STP = 62.4 lbm/ft3 = 1 gm/cm3 Heat of vaporization = 970 Btu /lbm Heat of fusion = 144 Btu /1 1 atmosphere = 14.7 psia =N 29.9 inches Hg.

i Miscellaneous Conversions 1 curie = 3.7 x 10tu disintegrations per second 1 kilogram = 2.21 lbm I horsepower = 2.54 x 103 Btu /hr

{

1 nw = 3.41 x 106 Btu /hr '

1 inch = 2.54 centimeters degrees F = 9/5 degrees C + 32 degrees C = 5/9 (degrees F - 32) r 1 Ptu = 778 f t-lbf

__- -- - i

L : :

U.S. NUCLEAR REGULATORY C0lWISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION f Facility: lA.)ot.F CEEEL Reactor Type: Pta e - t a c. <-J Date Administered: 22/o/7.8 Examiner: 1).cahots Candidate:

i INSTRUCTIONS TO CANDIDATE:

Use separate paper for the answers. Write answers on one side only. Staple question sheet on top of the answer shects. Points for each quesTTon are indi-cated 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 Category % of Landidate's Category Value Total Score Value Category 26.06 2S.co 5. Theory of Nuclear

~

Power Plant Operation, Fluids, and Thermo-dynamics

6. Plant Systems Design,

25. oo ho Control, and Instrumentation

7. Procedures - Normal, 25.c o 25.co ~

Abnormal, Emergency, and Radiological Control 25.00 8. Administrative Pro-ho cedures, Conditions, and Limitations

/co. oo Totals Final Grade All work done on this examination is my own, I have neither given nor received aid.

Candidate's Signature J

i

{

NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules apply:

1. Cheating on the examination means an automatic denial of your application and could result in more severe penalties.

2. Restroom trips are to be limited and only one candidate at a time may leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.

3. Use black ink or dark pencil only to facilitate legible reproductions.

4. Print your name in the blank provided on the cover sheet of the examination. I

5. Fill in the date on the cover sheet of the examination (if necessary).

l

6. Use only the paper provided for answers.

7. Print your name in the upper right-hand corner of the first page of each section of the answer sheet.

8. Consecutively number each answer sheet, write "End of Category __" as appropriate, start each category on a new page, write only on one side of the paper, and write "Last Page" on the last answer sheet.

9. Number each answer as to category and number, for example, 1.4, 6.3.

10. Skip at least three lines between each answer.

11. Separate answer sheets from pad and place finished answer sheets face down on your desk or table.

12. Use abbreviations only if they are commonly used in facility literature.

13. The point value for each question is indicated in parentheses after the question and can be used as a guide for the depth of answer required.

14. Show all calculations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or not.

15. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND 00 NOT LEAVE ANY ANSWER BLANK.

16. If parts of the examination are not clear as to intent, ask questions of the examiner only.

17. You must sign the statement on the cover sheet that indicates that the work is your own and you have not received or been given essistance in completing the examination. This must be done after the e x an. i n a t i o n has been completed.

l l . .

L i.

l l 18. When you complete your examination, you shall: .

! I 1

a. Assemble your examination as follows: l l

l (1) Exam questions on top.

(2) Exam sids - figures, tables, etc.

(3) Answer pages including figures which are part of the answer.

b. Turn in your copy of the examination and all pages used to answer the examination questions,

c. Turn in all scrap paper and the balance of the paper that you did not use for answering the questions,

d. Leave the examination area, as defined by the examiner. If after leaving, you are found in this area while the examination is still in progress, your license may be denied or revoked.

Sz__EdEBGENCX_6ND_8HNDBdeL_EL6NI_EVQL9IIQU$ Page 4 12211 QUESTION 5.01 (1.00)

A reactor is initially suberitical with a Keff of 0.95 and a source range count rate of 200 counts per second (CPS). Which one of the following is the final count rate if control rods are withdrawn to add 0.027 delta k/k reactivity?

a. 250 CPS

b. 300 CPS

c. 350 CPS

d. 400 CPS QUESTION 5.02 (1.00) ,

In a subcritical reactor, Keff is increased from 0.880 to 0.965. Which one of the following is the amount of reactivity that was added to the core?

a. 0.085 delta k/k

b. 0.100 delta k/k

c. 0.126 delta k/k i

d. 0.220 delta k/k l

l I

(***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)

1 l

l St__EDEB9ENCY_6ND_6HN9Bd6L_EL6NI_EYDLUIIQN3 Page 5 j L21h1 i

)

l

{

s 5.03 i QUESTION (1.00)

Tho moderator temperature coefficient (MTC) becomes LEAST NEGATIVE (the absolute value becomes smallest) under which ONE of the following

]

conditions?

a. Moderator temperature is decreased while boron concentration is decreased. .

b. Moderator temperature is increased while boron concentration is increased.

c. Moderator temperature is decreased while boron concentration is increased.

d. Moderator temperature is increased while boron concentration is decreased.

l QUESTION 5.04 (1.00) l A control rod has its greatest reactivity worth if it is inserted d i which ONE of the following locatiens?

l l a. Near the edge of the core.

l

b. Near the center of the core.

l c. In a region with high poison concentration.

l

d. In a region with low fuel concentration.

l QUESTION 5.05 (1.00) l Delayed neutrons :

l

a. are born at thermal energy levels (<1 ev).

b. account for the Importance Factor (I) being < l.0 l c. account for 70% of the fission neutron inventory.

l l d. are more likely to cause fast f ission than prompt neutrons.

l 1

l l

l (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)

1

l l . ..

l i '5___EMEEGENCX_600_eBN0806L_ELANI_EVQLUI19NS Page 6 12211 L

l l

l QUESTION 5.06 (1.00)

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

l l

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

l.

j b. The power defect increases the rod worth requirements necessary to maintain the desired shutdown margin following a reactor trip.

I

c. The power defect is more negative at the beginning of core life I due to the higher concentration of boron in the core.

i

d. The power defect necessitates the use of a ramped Tave program to l maintain an adequate RCS subcooling margin.

QUESTION 5.07 (1.00)

Which one of the following statements presents the two (2) primary methods for Xe-135 production in the core.

a. Decay of Iodine-135 and fission.

b. Decay of Samarium-149 and activation of oxygen.

c. Decay of f iss ion products and activation of U-233.

d. Decay of Iodine-135 and activation of oxygen.

QUESTION 5.08 (1.00) ,

Which one of the following factors proportional to control rod worth is the most important variable for determining rod worth?

1

a. Moderator temperature

]

(

b. Ls (Slowing down length)

c. L (thermal diffusion length) I

d. (Local Flux / Average Flux) quantity squared I

l

(***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)

- _-- _ -__---__-____-______-___ -- --__-_-___ _ __ _ _ _ - _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ .i

Sz__EUEBGEU9X_eND_8BNDBdeL_ELeNI_EVQLUL ' N3 Page 7 12211 QUESTION 5.09 (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 the best answer)

c. Ris ing slowly, then slowly falling off to zero.

b. Rising rapidly, then slcwly falling off to zero.

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

d. Rising rapidly, then rapidly falling off to zero.

QUESTICN 5.10 (1.00)

During a reactor startup from a Keff of 0.90, the first reactivity addition caused count rate to increase from 10 cps to 16 cps. The second reactivity addition caused count rate to increase from 16 cps to 32 cps. Which or.e of the following statements best describes the relationship between the first and second reactivity additions.

a. The f irst reactivity addition was larger

b. The second reactivity isddition was larger i

c. The reactivity additions were equal

d. Relationship cannot be de t e rin ine d from the given data l

QUESTION 5.11 (1.00)

The reactor is operating at 50% power, BOL, when a steam dump fails open.

Assume rod control is in MANUAL, no operator action is taken, and no reactor trip occuro. Wnich enswer below describes final conditions as compared to initial conditions?

a. Power and Tave are higher l

l

b. Power and Teve are lower i

l c. Power is the same and Tave is lower

d. Power .s higher ant Tave is lower l

l

(***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)

St__EdEBGEUGX_800_eBUQBd6L_EL6NI_EV9LUIIQNS Page 8 12211 QUESTION 5.12 (1.00)

During a Xenon free reactor startup, critical data was inadvertently taken two decades below the level it is normally required. Assuming RCS temperature and boron concentration do not, change, critical data is again taken at the proper level. How would the two critical rod positions compare? (1.0)

QUESTION 5.13 (1.00)

The onset of Nucleate Boiling is said to occur when" (choose ONE answer from below)

n. Bulk fluid temperature reaches saturation conditions.

b. A thin sayer of steam forms at the heated surface.

c. The critical heat flux is reached.

d. Small bubbles form at the heated surface.

I QUESTION 5.14 (2.00)

Indicate whether the following will cause the power range instrument to be indicating HIGHER, LOWER, or the SAME AS actual power, if the instrument has been adj usted to 100% based on a calculated calorimetric, l

a. The feedwater temperature used in the calorimetric was higher than 4 actual feedwater temperature. (0.5) i l

1

b. The reactar coolant pump heat input , sed in the calorimetric was j omitted. (0.5)

c. The indicated steam flow was lower than actual at the time of the

[ calorimetric. (0.5)

d. The feedwater flow rate used in the calorimetric was lower than actual Peedwater flow rate. (0.5) 4 l

l l

(***** CATEGORY 5 CONTINUED ON NEXi PAGE *****)

o -- - --- - --- o

52__EdEBGENGX_8HD_oBN9BdeL_EL6NI_EY9LUIIQU$ Page 9 12211 QUESTION 5.15 (2.00)

How will the Departure From Nucleate Boiling Ratio (DNBR) change (INCREASE, DECREASE, REMAIN THE SAME) in response to increasing each of the following parameters? Consider each separately. (2.0)

a. Tavg

b. Primary system pressure

c. Primary coolant flow rate

f. d. Reactor power level QUESTION 5.16 (1.00)

Which of the following would be indicative of a LOSS of natural circulation flow (MORE THAN ONE MAY APPLY):

a. Hot leg temperature increases

b. Steam generator pressure decreases faster than corresponding cold leg temperature

c. Cold leg temperature remains relatively constant

d. Steam generator level / rate increases with same AFW flow QUESTION 5.17 (1.00)

The plant is operating at 30 percent load during a load ramp to full power.

If steam flow density compensation fails at its 30 percent load value, which ONE of the following describe the affected steam flow indication when at full power?

a. Indicated steam flow is greater than 100%.

b. Indicated steam flow is greater than 30% but less than 100%.

c. Indicated steam flow is equal to 100%.

d. Indicated steam flow is equal to 30%.

i e (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)

. 4 St__EdEBQENQX_6NQ_6BNQBd6L_EL6NI_EVQLMIIQNH Page 10 122&l l QUESTION 5.18 (1.00) ,

Select one statement from the following:that correctly describes the reason y density compensation of the main steam line flow measurement is necessary.

e. Differential pressure across the orifice is proportional.to the volumetric flow rate. Volumetric flow rate is compensated with the fluid density-to provide mass flow rate.

b. Differential pressure.across the orifice is inversely proportional to the volumetric flow rate. Volumetric flow rate is compensated with the.

fluid temperature to provide mass flow rate.

c. Differential pressure across the orifice is proportional to the volumetric flow rate. Volumetric flow rate is compensated with-the fluid temperature to provide mass flow rate.

d. Differential pressure across the orifice is inversely proportional to the. volumetric flow rate. Volumetric flow rate is compensated with the fluid density to provide mass flow rate.

QUESTION 5.19 (1.00)

A calculated Estimated Critical Position (ECP) is performed for a startup to be commenced 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after a trip from 100% power. Considering each case below independently, state whether the Estimated Critical Position (ECP) will be HIGHER, LOWER, or the SAME AS the Actual Critical Position (ACP).

a. The startup is delayed until 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months after the trip. (0,5)

b. The condenser steam dump pressure controller setpoint is increased to just'below the steam generator atmospheric steam dump controller setpoint. (0.5)

QUESTION 5.20 (1.00)

Indicate for each of the following conditions whether a greater tensile stress is generated on the INNER or OUTER wall of the pressure vessel *

a. Heating up the Reactor Coolant System at 75 degrees F per hour. (0.5)

b. Increasing system pressure from 2000 psig to 2250 psig. (0.5)

(***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) I

1 l .

Sz__EdEEDENCX_6ug_eBNDBdeL_EL6NI_EV9LUIIQN1 Page 11 l 12211 l

l l

l QUESTION 5.21 (2.00)

a. What is the subcooling margin of the plant if the following conditions exist? (1.0)

Thot = 613 degrees F Ppzr = 2235 psig Tavg = 586 degrees F Psg = 1000 psig Tcold = 560 degrees F

b. If power is raised from 50% to 100%, does the subcooling margin INCREASE or DECREASE? EXPLAIN your answer. (1.0)

QUESTION 5.22 (1.00)

Which one of the following isotopes found in the reactor coolant would NOT be indicative of a potential fuel cladding perforation?

a. Co-60

b. I-131

c. Xe-133

d. Kr-85 1

(***** END OF CATEGORY 5 *****)

_ _ _ _ . _ .___-____-___-_--________-____-______________d

l l' .. .

6t__ELoNI_SXSIEbS_12011_oND_EL8NI: WIDE _QENEBIC Page 12 BESEQN11BILIIIES_11211 QUESTION 6.01 (2.00)

n. The Containment Spray Pumps are pretested to withstand large increases in temperature within a short period of time (37 deg F to 300 deg F within 10 seconds). When would the Containment Spray pumps be required to undergo such a severe temperature transient? (1.0)

b. If a Containment Spray Actuation Signal is present and cannot be reset, what must be done to stop the pump from the control room? (1.0)

c. When shifting containment spray pump suction following receipt of a RWST low-low level alarm, how long does the operator have before the pumps lose NPSH? Part c DELETED following review. (0.0)

QUESTION 6.02 (2.00)

e. In the Steam Dump System (Tave Mode), what is the source of the T ref s ig nal that actual Tave is compared to during:

1. load rejection (0.5)

2. reactor trip (0.5)

b. What occurs in the Steam Dump system when, in the Tavg mode, the LOAD REJECTION HIGH-2 bistable fails in the tripped (actuate) condition? EXPLAIN your answer. (1.0) l

{

(

l l

l 1

l l

1

(***** CATEGORY 6 CONTINUED ON NEXT 2 AGE *****) l l

6t__EL8HI_SYSIEUS_13011_eND_ELeNI:WIgg_ggNEBIC Page 13 BESE98SIBILIIIES_11211 QUESTION 6.03 (3.00)

a. What three (3) maj o r groups of valves normally operated by Instrumont Air are provided with accumulators (eight hour backup)? (1.5)

b. Describe the personnel hazard noted with some of these accumulators due to the N2 supply pressure. (1.0)^

c. Select the answer below that best indicates how the steam demand, following a loss of instrument air and subsequent reactor trip, will compare with a normal reactor trip's steam demand. (0.5)

1. 1% to 5% higher

2. 6% to 10% higher

\

3. 1% to 5% lower

4. 6% to 10% lower QUESTION 6.04 (3.00)

a. Charging pump discharge flow is 87 gpm and pressurizer and VCT levels are constant. Describe the distribution of this 87 gpm including what letdown flow is necessary to maintain constant pressurizer and VCT levels (CVCS Flow Balance). (1.0)

b. For each valve listed below, state whether it is air or motor operated

) and in which position each will fail if its motive force (air or power) is lost: (1.5) 1: Low Pressure Letdown Control Valve (PCV-131) f 2. Charging Flow Control Valve (FCV-121)

3. Normal CLsrging Valve (HV-8146)

4. Normal Charging Line Containment Isolation Valve (HV-810G)

5. Letdown Isolation Valves (HV-8160, HV-8152)

6. Alternate Charging Valve (HV-8147)

c. What automatic actions (alarms excluded) occur when the Boron Dilution Mitigation System is activated? (0.5)

(***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)

l 6 t__ELeNI_SYSIEdS_12011_6ND_EleNI: WIDE _QENEBIC Page 14 BESE9NSIBILIIIES_11211 QUESTION 6.05 (3.00) -

a. What are three (3) methods of starting the SI pumps manually, including locations? (1.0)

b. Why must the SI pumps be stopped when aligning the system for hot leg recirculation? (0.5)

c. Where is each of the ECCS pumps (RHR, SI, CCP) taking a suction and discharging to when in the Hot Leg Recirc mode of core cooling? (1.5)

QUESTION 6.06 (3.00) l '

a. Other than the SIS / Loss of Power load sequencers, what are two (2) automat ic start signals on the CCW pumps? Values NOT required. (1.0)

b. The CCW system is operating with pumps C and D in operation supplying normal CCW loads. Describe the automatic actions that take place in the CCW system if a SIS is received. (1.0)

c. Which CCW flow path from the containment building will be automatically shut on a high flow condition in that line? (0.5) .

d. What two (2) automatic actions take place in the CCW system if high radioactivity is detected in the system (disregard alarms)? (0.5) j l

1 l

l 1

1 1 i I 1 l

l

(***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)

Ez__ELANI_SXSIEUS.12Dil_eUD_ELeNI: WIDE _DENEBIG Page 15 BEREQUHIBILII 'S_11213 QUESTION 6.07 (2.50)

a. How are Diesel Generator LOAD (kw), SPEED (frequency), and VOLTAGE affected by taking the Diesel Governor Control Switch to raise / increase if: (1.5)

NOTE: Answer with INCREASE, DECREASE, NO CHANGE

1. The EDG is supplying its associated ESF bus alone?

2. The EDG is paralleled with the norn al power supply to the ESF bus?

b. The EDG is supplying its ESF bus alone when the operator inadvertently trips the output breaker.

1. What prevents the breaker from automatically reclosing? (0.5)

2. What must be done to allow automatic closure of the breaker to the bus in this instance? (0.5)

QUESTION 6.08 (2.50)

a. How is the auxiliar y feedwater flow rate to the steam generators controlled following /,FW actuation? (1.0) l

b. The controller in the control roem associated with valve AL-HV-9, AFW motor operated discharge valve to S6 B, has an amber light marked

" REMOTE" illuminated. What does this tell the operator about the f status of AL-HV-9 control? (0.5) l

c. Of the conditions necessary to initiate a motor driven AFW AFAS state the one(s) that may be bypassed at the main control board. (0.5)

d. What automatic signal will initiate the turbine driven AFW pump but not the motor driven pumps? (0.5) .

1 l QUESTION 6.09 (1.00)

Describe HOW and WHY adverse containment conditions (high containment pressure) can affect RCS pressure indications. (1.0) l l

l l

l (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)

l l

6___EL6NI_SISIEUS_1SD1]_6NQ_EL6hl:WJQg_QENEBIG Page 16 BESEQNS1HILIIIES_11213 QUESTION 6.10 (3.00)

a. What isolation signals are generated DIRECTLY by an SI signal? (1.0)

b. If a Phase A containment isolation has occurred, what additional system (s) or flowpath(s) will be affected by a Phase B isolation signal? (0.5)

c. Which isolation signals CANNOT be directly initiated manually? (1.0)

d. What isolatios,e) will occur simultaneously with manual Containment Sprey initiation? (0.5) l l

l l

l \

l l l

l 1

t l

l

} (***** END OF CATEGORY 6 *****)

o- - _ - - - _ - - - - - - - - - - - - - - - - - - _ - - - - - - - - 1

Page 17 l

QUESTION 7.01 (2.00)

What are two (2) verifications that must be made prior to moving the first irradiated fuel assembly during refueling? Exclude notifications and permission. (2.0)

QUESTION 7.02 (3.00)

n. During a heatup from Mode 5 to Mode 3 with RCS temperature below the indicating range of the RCS Narrow Range Temperature Channels, which indication defines "RCS Temperature" per GEN 00-002, " Cold Shutdown to Hot Standby?" (0.5)

b. At what minimum temperature is one RCP required to be operating? C0.5)

c. When heating up from Mode 5 to Mode 3, at what point is the first Mode Change made? (0.5)

d. What position should the Motor Operated Auxiliary Feedwater Valves (AL HV-5, 7, 9, 11) be kept in as much as poss ib le, even in Modes 4, 5, and 6. EXPLAIN WHY. (1.5) l QUESTION 7.03 (2.50)

Answer the following questions with regard to operation with " bottled-up" steam generators:

a. What constitutes a " bottled-up" steam generator? (0.5)

b. If all four steam generators are " bottled-up", how should heat be removed from the RCS? (1.0)

c. List four (4) negative consequences of continuous operation with

" bottled-up" steam generators in Mode 2 for prolonged periods. (1.0)

(***** CATEGORY 7 CONTINUED ON NEXT PAGE *****)

1 l Page 18 l

l l

i QUESTION 7.04 (3.00) l Assume the unit is in cold shutdown with the RCS drained for HALF LOOP l operation.

a. What is the best (earliest) indicator of RHR pump cavitation? (0.5)

(Consider the entire plant, not only the Control Room)

b. State two (2) indications in the control room that would be indicative of RHR pump cavitation. (0.5) f

c. If all core cooling is lost and no operator action is initiated, how much time may elapse prior to:

1. Boiling begins? (0.25)

2. Core uncovery? (0.25)

d. If both trains of RHR become inoperable, what are three (3) alternate means of decay heat removal per OFN 00-015, " Loss of Shutdown Cooling (RHR)?" (1.5)

QUESTION 7.05 (2.00)

a. List six (6) parameters associated with RCP operation that r e t, u i r e stopping / tripping of the affected RCP if exceeded. Setpoints NOT required. (1.5)

b. What is the maximum reactor power above which a RCP restart should not be attempted? (0.5) l QUESTION 7.06 (1.00) ;

For a dropped control rod, Tave/ Tref mismatch is initially maintained by !

taking manual control of: (1.0)

a. RCS boron concentration

b. Turbine load

c. Individual control rod banks a

l

d. Individual control rod groups

,I l

i 1

(***** CATEGORY 7 CONTINUED ON NEXT PAGE *****)

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

8 a Page 19 QUESTION 7.07 (2.00)

A reactor trip has occurred (without SI). All parameters respond normally for post-trip conditions except that two rod bottom lights did not illuminate. What actions are called for as a result? Do not include verifications (assume all actions are successful) but be specific as to actions performed. (2.0)

QUESTION 7.08 (1.00)

Assuming a secondary heat sink is available and adverse containment conditions do not exist, which one of the following sets of conditions would allow termination of SI? (1.0)

PZR LVL SUBC00 LING (SMM) PRESSURE

o. 12% 4S deg stable

b. 20% 80 des decreasing

c. 4% 60 deg increasing

d. 30% 2S deg stable QUESTION 7.09 (2.00)

For each of the parameters listed below, describe how they should respond if natural circulation flow exists as per EMG ES-03 (SI TERMINATION). (2.0)

a. Core exit thermocouple j

b. Steam generator pressores

c. RCS hot leg temperatures ]

)

d. RCS cold leg temperatures l

l 1

l l

I f (***** CATEGORY 7 CONTINUED ON NEXT PAGE *****)

l

l l .

l' ,

a l

l Page 20 l

QUESTION 7.10 (3.00) ,

n. What two (2) conditions require that ADVERSE CONTAINMENT process parameter values be used in the ERG's? INCLUDE VALUES, (1.0)

b. If ADVERSE CONTAINMENT conditions and values have been used, under what conditions may the operators again use the normal containment values? (1.0)

c. Why do ADVERSE CONTAINMENT conditions require the use of a different set of values than for normal containment conditions? (1.0)

QUESTION 7.11 (1.50)

Arrange the following events in order of occurrence during a startup from hot standby to minimum load. (1.5)

a. Place the Steam Dump Mode Controller in Tavg Mode

, b. Block the Source Range High Flux Trip l c. Start one Main Feedwater Pump (turbine)

I d. Block the Source Range Flux Doubling Transfer trip

e. Place Main Feedwater Pump Turbine Speed controls in AUTO

f. Place the Turbine Generator on the line

g. Block the Power Range Low Power Trips l QUESTION 7.12 (2.00) l l

a. What are two (2) general instances where radiological hazards may be l involved but s Radiation Work Permit (RWP) is NOT used? (1.0)

b. What " substitution" is allowed for the RWP in the above cases? (0,5)

c. TRUE or FALSE. Only the Health Physics Supervisor can authorize overriding the requirements of a RWP. (0.5) l l

l

(***** END OF CATEGORY 7 *****)

9 4 l

l Page 21 l

l l

l QUESTION 8.01 (2.50)

a. What three (3) parameters comprise the Technical Specification Safety Limits for WCGS? (1.5) l l

b. What Operational Condition (Mode) must be met, and within what time, if a Safety Limit is exceeded while in Mode 17 (1.0)

QUESTION 8.02 (3.00) l

a. List three (3) Radioactive Liquid Effluent Monitors contained in Technical Specifications that provide automatic termination of a l release. (1.5) l

b. List three (3) RCS Leakage Detection Systems required to be operable l l in Modes 1 through 47 (1.5) l l

l l

QUESTION 8.03 (1.50)

a. What is the licensed power level for WCGS (Rated Thermal Power)? (0.5) l

b. Under what conditions is operating with Ex-Core Nuclear Instrumentation indicating >100% NOT a violation of licensed power !

level? (0.5)

c. What is the instantaneous value limit on thermal power? (0,5) l l

l l

l i

1 1

(***** CATEGORY 8 CONTINUE 0 ON NEXT PAGE *****)

J

l Page 22 l

l QUESTION 8.04 (2.00) l l The boron concentration in the RWST shall be verified once per seven days j in accordance with Technical Specification 4.5.5. The RWST was sampled on l the following schedule:

October 1 -- October 8 -- October 15 -- October 23 -- October 31 Assume all samples were taken at 1200 h.urs (noon). Answer each of the following with regard to the above conditions,

a. State whether the surveillance time interval requirements WERE or WERE NOT exceeded on October 23. JUSTIFY your answer. (1.0)

b. State whether the surveillance time interval requirements WERE or WERE NOT exceeded on October 31. JUSTIFY your answer. (1,0)

QUESTION 8.05 (0.50)

What is the minimum qualification necessary to assume the control room command function if the Shift Supervisor is absent from the control room when the unit is is Mode 5 or 6 (per the Tech Specs)? (0.5)

QUESTION 8.06 (3.00)

Approximately twenty minutes prior to shift turnover, one of the RO's on the relieving crew calls in sick and will not be reporting to work. Prior to the call, the relieving shift has 2 SRO's (one was the SS and the other was the Supervising Operator), 3 RO's (control board operators), 4 NS0's (nonlicensed), and one STA (nonlicensed). The plant is operating in MODE 1.

a. Will the shift meet the minimum required staffing per ADM 02-001,

" Operations"? (0.5)

b. How long may a shift crew remain below the minimum required staffing and what acticin must be taken if this time is exceeded? (1.5)

c. What should be done to ensure adequate steffing if the situation above does not meet the minimum requirement? (1.0)

(***** CATEGORY 8 CONTINUED ON NEXT PAGE *****)

l Page 23 QUESTION 8.07 (1.00)

Under what regulation (or conditions) may a R0 licensed individual assume all responsibilities of the licensed SRO? (1.0) i QUESTION 8.08 (1.00)

What four (4) types of procedures are exempt from the requirement to verify revision status prior to their use? (2.0)

QUESTION 8.09 (1.00)

An operator comes to a step in a procecure which requires him/her to establish flow through a particular system and requires an independent verification of this. Operator #1 performs the necessary manipulations and gives it to Operator #2 for the verification. Operator #2 finds the ficw indicator for the system, verifies flow, and signs the verification as complete. Is this appropriate? If not, explain how it should have been accomplished. (1.0)

QUESTION 8.10 (1.50)

a. A reactor operator at the contrcls tells the STA to adjust diesel generator load during a load test surveillance of the diesel. EXPLAIN whether or not this has violated any procedures or regulations. (1.0)

b. Where can a list of tasks be found that are allowable to be performed while stationed "at the controls"? (0.5)

QUESTION 8.11 (2.50)

n. Under what two (2) conditions is it permissible to performs tasks I without the use of a Normal Clearance if the task involves isolating l or de-energizing components? (1.0) l l b. What may be used in lieu of a normal clearance? (0.5) l c -. If the Normal Clearance is not used, and the substitution in part "b" l

I is used, WHEN is the use of the Clearance Order Form required and WHY is it required? (1.0) l l

l l (***** CATEGORY 8 CONTINUED ON NEXT PAGE *****)

l

i

. . i Page 24 QUESTION 8.22 (2.00)

c. Who (by title) has the responsibility and authority to grant permission to restart the reactor following a reactor trip? J. 5)

b. What are three (3) maj or considerations / conditions that must be met before the restart should be authorized per ADM 02-400, Post Trip Review? (1.5)

QUESTION 8.13 (1.00)

The Shift Supervisor is notified that the RO presently at the controls has failed his annual oral requalification examination. Which action below is required (minimum)? [1.0)

a. Immediately remove from licensed duties

b. Remove from licensed duties within 2 days I

c. Retake and pass the examination within one month

d. Obtain permission f rem the Operations Superintendent to continue with licensed duties.

QUESTION 8.14 (2.50)

a. Who has the final decis ion mak ing authority regarding protective actions? (0.5) ,

1 f

b. What authority does WCGS personnel have with regard to ordering i evacuations of the site and the surrounding area? (1.0)

c. What is the minimum emergency classification that requires en evacuation of non-essential personnel from the site? (0.5) {

d. What is the minimum emergency classif ication that requires the '

implementation of personnel accountability? [0.5)

I

(

l l

l

(***** END OF CATEGOR: 8 *****)

(********** END OF EXAMINATION **********)

l L_ -------

St__EdEB9EN9X_6ND_8BN9BueL_EL8NI_EV9LVIIONS Page 25 f2211 ANSWER 5.01 (1.00) d (1.0)

REFERENCE Suberitical Multiplication Lesson Text 192008K103 3.9/4.0 192008K103 ..(KA's)

ANSWER 5.02 (1.00) b (1.0)

REFERENCE

.{

Reactivity and Delayed Neutrons Lesson Plan

'192002K111 2.9/3.0 192002K112 2.4/2.5 192002K111 192002K112 ..(KA's)

)

ANSWER 5.03 (1.00) c (1.0)

REFERENCE Reactivity Coefficients Lesson Plan, pg 15, 16 192004K106-3.1/3.1 192004K106 ..(KA's)

ANSWER 5.04 (1.00) b.

1 i

l i

1 I

(***** *****)

CATEGORY 5 CONTINUED ON NEXT PAGE l

q l

)

: 1 1

St__EDEBGENCX_6BD_aBNDBd6L_EL6NI_EY9LVIIONS Page 26 l 12211 l l

t REFERENCE j Excess Reactivity and Chemical Skfa Lesson Text, Section 4 192005K106 2.6/2.9 {

192005K106 ..(KA's) l ANSWER 5.05 (1.00) b (1.0)

REFERENCE Reactivity and Delayed Neutron Lesson Plan 192003K107 3.0/3.0 l

192003K107 ..(KA's)

{

ANSWER 5.06 (1.00) b (1.0)

' REFERENCE

.Rosctivity Coefficients Lesson Text 192004K113 2.9/2.9 192004K113 ..(KA's) f ANSWER 5.07 (1.00) I a (1.0)

REFERENCE Fission Product Poison Lesson Plan 192006K103 2.7/2.8 192006K103 ..CKA's) l

(***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)

I

i

- l 1

L St__EDEBGENQX_8HQ_6ENDBU8L_EL8NI_EVOLUII9NS Page 27

! L2211 l 1 ANSWER 5.08 (1.00) d (1.0)

REFERENCE Excess Reactivity and Chemical Shim Lesson Text, pg 25 192005K107 2.5/2.8 192005K107 ..(KA's)

ANSWER 5.09' (1.00) b.

REFERENCE Period Equation Lesson Text 192008K105 3.8/3.9 192008K105 ..(KA's)

ANSWER 5.10 (1.00) a (1.0)

REFERENCE Subcritical Multiplication Lesson Text 192008K104 3.8/3.8 192008K104 ..(KA's) i ANSWER 5.11 (1.00) d (1.0)

(***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) .

l 5t__EMEBGEUQ1_6NQ_6BNQBN6L_EL6HI_EyQLMIIQN! Page 28 L2211 REFERENCE Core Age Effects and PWR Response Lesson Text 192008K121 3.6/3.8 192008K117 3.3/3.4 192008K121 192008K117 ..(KA's)

ANSWER 5.12 (1.00)

The ?wo critical rod positions should be the same (1.0)

REFERENCE Reactivity Coefficients Lesson Text 192008K110 3.3/3.4 192008K110 ..(KA's)

ANSWER 5.13 (1.00) d (1.0)

REFERENCE Heat Transfer Modes Lesson Plan, pg 33 193008K103 2.8/3.1 193008K103 ..(KA's) l ANSWER 5.14 (2.00) l

n. lower

b. higher

c. same as

o. Iower (.5 each)

! REFERENCE L 1 l Heat Balance Lesson Plan and Text l

015000K504 2.6/3.1 015000A101 3.5/3.8* 193007K100 3.1/3.4 q 015000K504 015000A101 193007K108 ..(KA's) i l (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)

l L :' .

t Sz__EMEB9ENCX_6ND_6HNDBd6L_EL6NI_EVOL9119N1 Page 29 l 02211 l

l ANSWER 5.15 (2.00) l

a. Decrease L b. Increase I

c. Increase I

d. Decrease (.5 each) l' L REFERENCE l

l Introduction to Accident Analysis Lesson Plan l 193008K1033.4/3.6 1

l 193008K105 ..(KA's) l l

l ANSWER 5.16 (1.00) e, b, C2 at 0.25 each) c and d not required i REFERENCE Natural Circulation Lesson Text 193008K122 4.2*/4.2*

1930n8K122 ..(KA's)

ANSWER 5.17 (1.00) n.

REFERENCE Properties of Fluids Lesson Text, pg 54 191002K102 2.7/2.9 191002K102 ..(KA's)

ANSWER 5.18 (1.00) a (1.0)

(***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)

__________ __________ _ __._____________ _ __ _ o

5___EUEBGENCI_6HD_6HN9BdeL_EL6NI_EV9LUII9NS Page 30 12211 ,

1 i REFERENCE l

l Properties of Fluids Lesson Text {

i 191002K102 2.7/2.9 191002K102 ..(KA's)

ANSWER 5.19 (1.00)

a. ECP lower than ACP (0.50)

b. ECP lower than ACP C0.50)

REFERENCE Reactivity Coefficients and Fission Product Poison Lesson Plans 001010A207 3.6/4.2 001010A207 ..(KA's)

ANSWER 5.20 (1.00)

a. OUTER

b. INNER REFERENCE Pressurized Thermal Shock Lesson Plan Materials Review 002000K518 3.3/3.6 002000K518 ..(KA's)

(

ANSWER 5.21 (2.00)

n. Tsat for 2250 psia (2235 psig) = 653 degrees F (+/- 1 degree) (.5)

Subcooling margin = Tsat - Thot = 653 - 613 = 40 degrees F

(+/- 1 degree) C.5)

b. Subcooling margin decreases (.25) because Thot will increase as power increases (.375) while pressure remains the somet.375). '

(***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)

Sz__EDEBDENCY_6ND_6BN9Bd6L_EL6NI_EVQLUI1QNS Page 31 12211 REFERENCE ,

i STEAM TABLES 001000K556 4.2/4.6 001000K556 ..(KA's)

ANSWER 5.22 (1.00) o (1,0)

REFERENCE Post Accident Primary Radiochemistry Lesson Text 004000A101 2.9/3.8 004000A101 ..(KA's) l l

l l

{; 1 l l L . . I L

l i

1 .

l 64__EL6HI_SXSIENS_120%1.6ND_EL6NI: WIDE _DENEBIG Page 32 I

BESEDNSIBILIIIES_flas?.

ANSWER 6.01 (2.00)

n. During switchover from RWST to recirculation sump (1.0) following actuation. I

b. Place the pump switch in pull to lock (1.0)

REFERENCE Containment Spray Lesson Plan, pg 9, 14 .

026020K403 4.1*/4.3* 026000A401 4.5/4.3 026020K403 026000A401 ..(KA's)

ANSWER 6.02 (2.00)

a. 1. turbine first stage pressure (0.5)

2. No load Tavg (0.5)

b. No actuations occur (0.5), due to no arming signal for the steam dump valves (0.5)

REFERENCE Steam Dump Lesson Text, pg 5,6 , 11 041020K411 2.8/3.1 041020K411 ..(KA's)

ANSWER 6.03 (3.00)

a. - Auxiliary Feedwater Flow Control Valves (0.5)

- S/G Atmospheric Reliefs (0.5)

- Main Feedwater Control Valves (0.5)

b. Leakage of N2 into the room and lovers the 02 level in the room to less than a breathable level (1.0).

c. Answer 1 (1% to 5% higher) (0.5)

(***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)

L._..E L 6NI_ S YSIEdS _ L 2011_6 N D _ E L 6NI: WIDE _QENEBIQ Page 33 BESE9N11SILIIIEH_L1211 4 4

l REFERENCE i

Instrument and Service Air System Lesson Plan, pg 15, 16, 28 078000K302 3.4/3.6 078000G001 2.9/3.1 078000K302 078000G001 ..(KA's) 1

)

i i

ANSWER 6.04 (3.00) {

1

c. 12 gpm seal leakoff (0.25) back to CCP suction (value may be between )

0.8 and 20 gpm. Adj ust other values as necessary if value other than 1 12 used) l 20 gpm back to RCS via RCP shaft leakage (0.25) 55 gpm charging into RCS (0.25) i 75 gpm letdown flow (0.25) l

b. 1. air, open

2. air, open

3. air, open

4. motor, as is

5. cir, closed

6. air, open (0.125 for each motive force, 0.125 for each positior) Jq

c. RWST to CCP suction valves open (HV-1120 & E) (0.25) :!

VCT Outlet Isolation Valves close (HV-112B & C) (0.25)

REFERENCE I

CVCS Lesson Plan, pg 22, 23, 33 - 34, 50 L f CVCS Lesson text, pg 31, 32 004010A204 3.6/4.2 004000K104 3.4/3.8 004000G007 3.3/3.3

]

On4010A204 004000K104 004c000007 ..(xA e3 j l

4 i

. l Et__ELoNI.SYSIEUS_fSDil_eND_EL6NI:WIQE_GENEBIQ Page 34 BESE9NSIBILIIIES_ flail l

ANSWER 6.05 (3.00) l

a. - Switch on the MCB (0.33) {

- Switch on the cubicle door of the breaker (0.33) ;

- mechanical "close" pushbutton inside the cubicle door (0.33)

- manual SIS initiation also acceptable

b. During the switchover, they will have no mini-flow protection (0.5).

c. RHR: suction - containment sump (0.25) discharge - RCS hotlegs (0.25), suction of CCPs (0.25), suction of SI pumps (0.25)

CCP: suction - discharge of RHR pumps discharge - RCS cold legs (0.25)

SI: suction - discharge of RHR pumps {"

discharge - RCS hot legs (0.25)

REFERENCE ECCS and SI Lessen Text, pg 53, pg 75 - 80 006000A401 4.1/3.9 006000K406 3.9/4.2 006020K401 2.7/3.0 006020K401 I 006000A401 006000K406 ..(KA's)

ANSWER 6.06 (3.00)

e. - CCP started (0.5) if no CCW pump runni.g in that train already .

- Low discharge pump discharge pressure 0.5) with the parallel pump running.

b. Radweste Building loads (0.33) and Post Accident Sample System loads (0.33) will isolate. The CCW cooler bypass valves (temperature control valves) will shut (0.33).

c. RCP thermal barrier return flow (0.5)

d. Surge tank vent (0.25) and surge tank demin water mukeup valves (0.25) ,

shut.

l l

l f (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)

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

0- .h 1

I .ht__EL8NI_1X3IENS_f2011_8ND_EL8NI: WIDE _QENEBIC Page 35 l BESEQNSIBILIIIE1_f1211 L

1 L

REFERENCE CCW Lesson Text, pg 26,.35, 36 008000K401'3.1/3.3 008000A204 3.3*/3.5 008000A101 2.8/2.9

- 008000K401 008000A204 008000A101 ..(KA's)

, ANSWER 6.07 (2.50)

c. (6 at 0.25 each)

1. Load; no. change speed: increase (accept no change if stated EDG start due to UV)

' voltage:L no change

2. Load: increase speed: no change voltage; no change

b. 1. EDG output breaker anti-pumping logic (0.5)

2. The local operator must take the MASTER TRANSFER SWITCH from AUTO to LOCAL / MANUAL then back to AUTO (0.5). Also acceptable:

'Deenergize DC control power to the breaker, or take the EDG breaker handswitch to any position other than normal.

REFERENCE Emergency Diesel Generator Lesson Plan, .pg 35, 40 064000A203 3.1/3.1 064000A214 2.7/2.9 064000A401 4.0/4.3 064000A203 064000A214 064000A401 ..(KA's) l ANSWER 6.08 (2.50)

a. When the total flow (0.25) to each SG is >300 gpm (0.25), the motor operated discharge valve starts to throttle closed (0.5) to maintain flow below 300 gpm.

b. Control of the valve is at the Auxiliary Shutdown Panel (0.5).

c. Trip of both main feed pumps (0,5) may be bypassed.

d. UV on NB01 or NB02 safeguards buses (0,5)

(***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)

l_

. 1 f:

l Ez__EL8NI_SISIEMS_L2011_6HD_ELeNI:W1QE_QENEBIG Page 36 L BESEQN11BILIIIE1_11211-l l

l REFERENCE.

I AFW Lesson Text,.pg 18, 26, 36 061000K402 4.5/4.6 061000K404 3.1/3.4 061000K601 2.5/2.8*

061000K402 061000K404 061000K601 ..(KA's)

ANSWER 6.09 .(1.00)

Elevated' containment pressures can cause indicated RCS pressure to be lower than actual pressure (0.5). The pressure transmitters are referenced to atmospheric pressure (0.5), so if the atmospheric pressure increases, .the indi9ated pressure would decrease due to the decreased dp. Accept any explanation that describes this concept.

REFERENCE.

PZR Pressure and Level Control Lesson Text, pg 57 010000K601 2.7/3.1 010000K601 ..(KA's)

ANSWER 6.10 (3.00)

-l

a. - CIS phase A

- SG Blowdown and Sample

- Feedwater (0.33 each)

b. CCW supply and return to RCPs (0.5)

c. - Main Steam Line Isolation

- Main Feedwater Isolation

- Steam Generator Blowdown and Sample Isolation (0.33 each)

d. CIS Phase B (0.5)

REFERENCE ESFAS Lesson Text, og 28 - 33 103000K102 3.9/4.1* 103000K436 3.1/3.7 000069A202 3.9/4.4 103000K102 103000K406 000069A202 ..(KA's)

(

(***** END OF CATEGORY 6 *****)

. l Page 37 i

I ANSWER 7.01 (2.00)

- Rx subcritical for > 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months f

- Ueter level in Refueling Pool > 23' above Rx vessel Flange i

- Crane interlocks and stops demonstrated operable

- Direct communications between the Control Room and personnel at the l refueling station have been established

- Containment integrity (2 required at 1.0 each)

REFERENCE

]

FHP 02-001, Refueling Procedure, Rev 8, pg 14 034000G001 2.3/2.9 034000G001 ..(KA's)

ANSWER 7.02 (3.00)

e. The highest loop temperature as determined from the RCS Wide Range Temperature Computer or Wide Range Temperature Recorders (0.5).

b. 160 deg F (0.5)

c. >200 deg F (0.5)

d. Open (0.5). When the controller is in the CLOSED position, the field in the motor remains energized, which shortens the life of the i actuator (1.0) i REFERENCE GEN 00-002, Rev 13, pg 2, 9, 10 061000G010 3.5/3.6 0030000010 3.3/3.6 061000G010 003000G010 ..(KA's) l l

l l

l l l l

l l-1

(***** CATEGORY 7 CONTINUED ON NEXT PAGE *****) ,

l. _ ._ ._ _ . _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ . _ . _ _ _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _

.l Page 38 ANSWER 7.03 (2.50)

a. MSIVs and FWIVs shut (0,5)

b. Feed one SG (0.3) ftom the AFW (0.3) while steaming the same SG through its Atmospheric Relief Valve (0.4). Also accept RHR (0,5) if less than 350 deg F (0.5)

c. - increased corrosion

- core power mal-distribution

- feedline cracking

- nozzle transient / fatigue

- increased feedwater cycling (slug flow)

- loss of proper chemistry control (4 required at 0.25 each)

REFERENCE GEN 00-003, Hot Standby to Minimum Load, Rev 16, pg 3 035000G010 3.2/3.4 035000G010 ..(KA's)

ANSWER 7.04 (3.00)

a. Local observation of pump noise (0.5)

b. RHR pump flow, pump, amperage, or pressure oscillation, RCS loop level oscillation. Accept any two for 0.25 each.

c. 1, 30 minutes (accept 8- 45) (0.25)

2. 2.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months (accept 1.0 - 4.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ) (0.25)

d. - dump from SI accumulators

- RCS feed & bleed from RWST

- Spent fuel pool cooling system (3 required at 0.5 each)

REFERENCE OFN 00-015, Loss of Shutdown Cooling, Rev 5, pg 111, 8- 12, 39, 41 GEN 00-007, RCS Drain Down, Rev 9, pg 10 000025A207 3.4/3.7 000025K101 3.9/4.3 000025K301 3.1/3.4 i 000025A207 000025K101 000025K301 ..(KA's) l l

i l

l l (***** CATEGORY 7 CONTINUED Gid NEXT PAGE ***** )

1 ;

i

)

L l : .l

)

Page 39 l

l ANSWER 7.05 (2.00)

a. - #1 seal'dp

- motor bearing temperature

- #1 seal inlet temperature

- pump bearing temperature

- frame vibration

- shaft vibration

- #1 seal leekoff

- RCS pressure

- Containment pressure (6 at 0.25 each)

b. 5% (0,5)

REFERENCE EMG-E0 0FN 00-005, RCP Malfunctions, Rev 6, pg 1 - 111 003000A202 3.7/3.9 003000G010 3.3/3.6 003000A202 003000G010 ..(KA's)

ANSWER 7.06 (1.00) {

b (1.0)

REFERENCE {

OFN 00-011, Dropped or Misaligned Rod, and Realigreaent, Rev 2, pg 1 000003A105 4.1/4.1 000003A106 4.0/4.1 1

I 000003A105 000003A106 ..[KA's)

ANSWER ?.07 (2.00) {

l

- Start both beric acid transfer pumps (0.6) )

- Stop VCT makeup (0.6)

- Open immediate borate valve to charging pump suction (0.6) 1

- Energize backup heaters (0.2) )

l l

l

)

1

(***** CATEGORY 7 CONTINUED ON NEXT PAGE *****) I

L l

l Page 40 l

l REFERENCE l

OFN 00-009, Immediate Boration, Rev 1 000024K301 4.1/4.4 000024K302 4.2/4.4 000024G010 4.5*/4.5 000024K301 000024K302 000024G010 ..(KA's) l l

ANSWER 7.08 (1.00) a (1.0)

REFERENCE EMG E-1, Loss of Reactor or Secondary Coolant, Rev 1, pg 6 .

013000G001 4.0/4.1*

0130000001 ..(KA's) 4 ANSWER 7.09 (2.00)

{

o. CET's: Stable or decreasing (0.5) l

b. SG pressures: Stable or decreasing (0.F) {

c. RCS hot leg: Stable or decreasing (0.5) j

d. RCS cold leg: At Tsat for SG pressure (0,5) 1 1

REFERENCE i

j EMG ES-03, SI Termination, Rev 1, pg 18 j 000009A237 4.2/4.5 j i

000009A237 ..(KA's) 1 I

l ANSWER 7.10 (3.00) {

{

a. Containment pressure > 5 psig (0.5) or l Containment radiation >10E5 R/hr (0.5) !

b. Containment pressure <5 psig (0.5) (if 5 psig was exceeded) and the radiation dose must be verified to be <10E6 RADS (0,5) (if 10E5 R/hr I was exceeded)

c. Adverse Containment condit ions may cause s ignif icant errors in the ,

indications of instruments located inside containment (1.0). I l

l

(***** CATEGORY 7 CONTIN 8JED ON NEXT PAGE *****) .

l l

l t l : ;

Page 41 i

l REFERENCE 1

Westinghouse Owner's Group Emergency Response Guidelines Executive Volume, i L Generic Issue - Generic Instrumentation, Rev 1, pg 21 l 000009K316 3.8/4.1 000009K318 3.9/4.3 103000G010 3.3/3.6 000009K321 4.2/4.5 1

1 000009K316 000009K318 1030000010 000009K321 ..(KA's) l ANSWER 7.11- (1.50) l l

l do b, c, f, g, e, e OR do b, c, e, f, g, a

(0.25 for each manipulation required to place in the correct order) l l REFERENCE GEN 00-003, Hot Standby to Minimum Load, Rev 16, 194001A102 4.1*/3.9 l 194001A102 ..(KA's)

ANSWER 7.12 (2.00)

a. - j obs of very short duration

- emergencies

- instances where quick action is necessary

- entry to RCA yard area (2 required at 0.5 each)

b. Continuous escort by a HP Tech may be substituted for a RWP (0.5). l

c. False (0.5)

REFERENCE Radiation Protection Manual Losson Plan, pg 32 - 33 194001K103 2.8/3.4 194001K103 ..(KA's)

(***** END OF CATEGORY 7 *****)

1 Page 42 ANSWER 8.01 (2.50)

n. RCS pressure, thermal power, Tavg (RCS temperatures) (3 at 0.5 each)

b. Hot _ Standby (0.5) within one hour (0.5)

REFERENCE Technical Specification 2.1 002000G005 3.6/4.1 002000G005 ..(KA's) '

ANSWER 8.02 (3.00)

a. - Liquid Radweste Discharge Monitor (RE-18)

- Steam Generator Blowdown Discharge Monitor (RE-52)

- Turbine Building Drain Monitor (RE-59)

- Secondary Liquid Weste System Monitor-(RE-45)

(3 required at 0.5 each)

b. - Containment Atmosphere Particulate Radioactivity Monitoring System

- Containment Normal Sump Level Measurement System

- Containment Air Cooler Condensate Flow Rate Monitoring System

- Containment Atmosphere Gaseous Radioactivity Monitoring System (3 required at 0.5 each)

REFERENCE Technical Specifications, Table 3.3-12 L Technical Specification 3.4.6 073000K401 4.0/4.3 073000G005 3.1/3.6 073000K401 073000G005 ..CKA's) i ANSWER 8.03 (1.50) l

a. 3411 Mwt (0.5) accept +0% to -10%

l l b. As long as the power level can be documented to be less than rated, it 1s not a violation (0,5). Documentation may include the computer l hourly log.

l l c. 3479 Mwt (0.5) .

i l.

l (***** CATEGORY 8 CONTINUED ON NEXT PAGE *****) '

1:

c_____ __ _ _ _ . - _ _ _ . - . _ _ _ _ _ _ .- _ _

l l

[

l l Page 43 l

l REFERENCE

'WCGS Standing Order 34 015000G010 3.3/3.5 0150000010 ..(KA's)

ANSWER 8.04 (2.00) i

n. Were Not (0.5). Eight days does not exceed 1.25 time the specified surveillance interval (0.5).

b. Were Exceeded (0,5). The combined time interval for the last three consecutive surveillance exceeds 3.25 times the specified surveillance interval (0.5). (3.25 X 7 = 22.75 days, Oct 8 to Oct 31 equals 23 days)

REFERENCE Technical Specification 4.0.2 006000G011 3.6/4.2*

REFERENCE 006000G011 ..(KA's)

ANSWER 8.05 (0.50)

R0 licensed (0.5)

REFERENCE Technical Specifications 6.2.2 194001A103 2.5/3.4 194001A103 ..CKA's)

ANSWER 8.06 (3.00)

a. yes (0.5)

b. 2 hourt (0.5) Place the plant in a mode where the minimum shift crew composition is met (1.0).

c. An operator from the previous shift should 'Je held over. Accept any description that displays the knowledge that the shift change is not allowed with less than the minimum staffing. (1.0)

(***** CATEGORY 8 CONTINUED ON NEXT PAGE *****)

i.

/

Page 44 REFERENCE ADM 02-001, Operations, Rev 11, pg 8, Figure 1 194001A103 2.5/3.4 194001A103 ..(KA's)

ANSWER 8.07 (1.00) 10CFR50.54 (1.0). Also accept wording equivalent to 50.54(x) wording.

REFERENCE 10CFR50.54(x)

ADM 02-005 Reactor Operator Qualifications and Responsibilities, Rev 5 194001A103 2.5/3.4 194001A103 ..(KA's) l ANSWER 8.08 (1.00)

- EMG's

- 0FN's

- ALR's

- EPP's (0.25 each)

REFERENCE l ADM 02-021, Use of Procedures in Operations, Rev 11 194001A101 3.3/3.4 l 194001A101 ..(KA's) l l

l ANSWER 8.09 (1.00)

Yes (1.0) )

l REFERENCE

]

l ADM 02-021, Use of Procedures in Operations, Rev 11, pg 7 )

l 194001K101 3.6/3.7 194001K101 ..(KA's) l l

\ \

l (***** CATEGORY 0 CONTINUED ON NEXT PAGE *****) l

[. I

1 , .

Page 45 l l

i l )

l l

l ANSWER 8.10 (1.50) l-l

! d. It has not (0.5). The task does not directly affect reactivity or power level of the reactor (0.5).

l l b. Conduct of On Duty Operations Personnel (0.5) attachment Also accept Standing Orders [#27)

I REFERENCE l

ADM 02-040, Conduct of On Duty Operations Personnel, Rev 7

Standing Order #27 l l 194001A103 2.5/3.4 l

l 194001A103 ..(KA's) l ANSWER 8.11 (2.50)

a. - troubleshooting

- adjusting

- maintenance work of short duration (< 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months )

- all isolation devices can be monitored from a single location (2 at 0.5 each) 1

b. An individual may be assigned to monitor the component (0.5)

c. If the work was on safety related equipment (0.5) to document restoration position verification (0.5)

REFERENCE ADM 02-100, Clearance Order Procedure, Rev 17, pg 19 194001K102 3.7/4.1 194001K102 ..(KA's)

(***** CATEGORY 8 CONTINUED ON NEXT PAGE *****)

d l

l Page 46 i

l )

1 1 i l ANSWER 8.12 (2.00) I l

a. Plant Manager (0.5) or Superintendent in PM's absence

b. - Cause of the trip known and corrected

- Maj or safety related and other important equipment functioned properly or

- Corrective maintenance and testing has been performed or will be performed

- Plant response has been analyzed and responded as anticipated, or

- Abnormalities understood and corrected per TS }

(3 required at 0.5 each) {

REFERENCE ADM 02-400, Post Trip Review, Rev 4 194001A103 2.5/3.4 194001A103 ..(KA's)

ANSWER 8.13 (1.00) b (1.0) may finish the watch, also accept "a" REFERENCE ADM 06-224, Licensed Operator Requalification Training Program, Rev 7, pg 22 194003A103 2.5/3.4 194001A103 ..(KA's)

ANSWER 8.14 (2.50)

a. Coffey County for local emergencies (0.25)

State of Kansas Division of Emergency Preparedness (0.25) for wider scale emergencies

b. WCGS personnel only have evacuation authority over the area controlled or owned by the utility (1.0).

c. Site Area Emergency (0.5)

d. Alert (0.5)

(***** CATEGORY 8 CONTINUED ON NEXT PAGE *****)

l l

u l'

Page 47 l . REFERENCE l

EPP 01-5.1, Exclusion Area Evacuation, Rev 3 EPP 01-6.1, Personnel Accountability, Rev 7 EPP 01-10.1, Protective Action Recommendations, Rev 5 194001A116 3.1/4.4*

194001A116 ..(KA's) 1

(***** END OF CATEGORY 8 *****)

(********** END OF EXAMINATION **********)

n_--_-_______. __ _ _ _ . - _ _ _ - _. _ _ _ . . _

l v l TEST CROSS REFERENCE Page i QUEEIl0N _Y8LUE BEEEBEUGE_

5.01 1.00 9000246 5.02 1.00 9000245 5.03 1.00 9000247 5.04 1.00 9000248 5.05 1.00 9000255 f 5.06 1.00 9000256 5.07 1.00 9000257 5.08 1.00 9000258 5.09 1.00 9000259 5 . 3. 0 1.00 9000262 5.11 1.00 9000263 5.12 1.00 9000265 5.13 1.00 9000249 5.14 2.00 9000251 5.15 2.00 9000260 5.16 1.00 9000264 5.17 1.00 9000253 5.18 1.00 9000261 5.19 1.00 9000250 5.20 1.00 9000252 5.21 2.00 9000254 5.22 1.00 9000266 25.00 6.01 2.00 9000267 6.02 2.00 9000268 f

6.03 3.00 9000269 6.04 3.00 9000270 6.05 3.00 9000271 6.06 3.00 9000272 6.07 2.50 9000273 6.08 2.50 9000274 6.09 1.00 9000275 6.10 3.00 9000276 25.00 7.01 2.00 9000219 7.02 3.00 9000222 7.03 2.50 9000223 7.04 3.00 9000220 7.05 2.00 9000221 7.06 1.00 9000227 7.07 2.00 9000229 7.08 1.00 9000225 7.09 2.00 9000226 7.10 3.00 9000228 74 11 1.50 9000224 7.12 2.00 9000230

f. ______

25.00 l

8.01 2.50 9000232 8.02 3.00 9000233 i

9 :

TEST CROSS REFERENCE Page 2

-QUE11108 _V8LUE BEEEBENCE_

8.03 1.50 9000239 8.04 2.00 9000243 8.05 0.50 9000231 8.06 3.00 9000234 8.07 1.00 9000235 8.08 1.00 9000236 8.09 1.00 9000237 8.10 1.50 9000238 8.11 2.50 9000240 8.12 2.00 9000241 8.13 1.00 9000242 8.14 2.50 9000244 25.00 100.0 l

l 1

1 l

l l l l l

l l

NRC LICENSE EXNilRATION HANDOUT I

EQUATIONS, C0ttSTANTS AND CONVERSIONS 6 '= rIi*Cp *deltaT 6=U*A*deltaT P = Po*10sur*(t) p ,p ,,t/T SUR = 26/T T=1*/p+(p-p)/IP T=1/(p-p) T = (p-p)/X p p = (Keff-1)/Keff = deltaKeff/Keff p = 1*/Reff + jeff/(1+ T.T)

A = In2/tg = 0.693/tg K = 0.1 seconds-1 I = Io*e "*

CR = S/(1-Keff) 2 R/hr = 6*CE/d feet Water Parameters 1 gallon = 8.345 lbm = 3.87 liters 1 ft3 = 7.48 gallons Density 0 STP = 62.4 lbm/ft3 = 1 gm/cm3 Heat of vaporization = 970 Btu /lbm Heat of fusion = 144 Btu /1 %

1 atmosphere = 14.7 psia = 29.9 inches Hg.

i Miscellaneous Conversions 1 curie = 3.7 x 101U disintegrations per second 1 kilogram = 2.21 lbm I horsepower = 2 54 x 103 Btu /hr 1 mw = 3.41 x 105 Btu /hr 1 inch = 2.54 centimeters degrees F = 9/5 degrees C + 32 degrees C = 5/9 (degrees F - 32)

( 1 Btu = 778 ft-lbf 4

/

I e SECTIOi 1 1.20 (5.20)

'niis question can be answered from two different pes. pectives. If the given initial condition is that natural circulation is lost, then all four responses would support this known condition. However, if the examinee takes the pw..gdve that the four responses are independently observed t henomena to an unknown condition (more wra itative of actual operating canditions), responses "c" and "d" are expected outoames during the natural circulation evolution. Response "c", cold leg t---v.,ture runnins relatively constant, is an expected outoame (see ES-03 Attachment D, attached) of steam varretor pressure being stable with T-cold tracking l steam generator t=rarature. Response "d", Steam generator level / rate increases with the same AN flow, would be an expected response as decay heat and subsequent staaming rate decline with time while on natural circulation. We h---4 deleting parts e and d fran this question.

End of section 1 conments.

SECI' ION 2 2.01 b.

Should also accept the following auto actions that occur in the ESN systen l an loss of offsite power:

1. Pump suction traveling screens start (ref MK2EF01)

2. Screen wash supply valves open (EFHV-91/92)(ref. MK2EF01)

3. ESN pump air release valves close (EFHV-97/98)(ref. MK2EP01)

4. ESW rocm cooler starts; supply / discharge elemm open (ref. MK2GD01)

5. CCW heat exchanger supply valves open (EFHV51/52)(ref. M12EF02)

2.02 b. (6.03 b.)

'lhe relief valve on these am-lators has recently been nodified to vent outside of the rom (see attached plant modification). 'therefore any answer which lists that nitrogen release to the ro m will create dangerously low Cbqgen concentrations should be acw zi u for full credit without reference !

to the relief valves. (i.e. pipe rupture, leaks, etc.)

s, .

2.02 c. (6.03 c.)

With a loss of instrument air, the steam dump;systan is also rendered inoperable. This would cause the initial steam flow to be less, as steam pressure rom to lift the SG PNVs and/or the SG safeties. Iater in the event, the effect of the steam line drain valves failing open would produce a higher steam flow. There is no one correct anser to this question, so we r+_,-- s i that part c. to this questian be deleted.

l l

/

c 2.03 a. (6.04 a.)

Seal leakoff is actually a function of #1 seal dP. Design cxmditions call for a total of 12 gpn leakoff (3 gpn/ pump), 2 owever any value of :,2 to 5.0 per pump (.8 to 20 gpn total) should be acceptable since this is the prescribed safe operating range in OFN 00-005 "RCP Malfunctions" '(see attached graph). We recxmnena accepting any answer within this range with the balance of flow (87 - leakoff) for letdown flow.

2.04 a.

This evolution can also be amliahed with =mm1 control of the bypass valve. As the operator varies the position of the heat exchanger outlet valve, he can manually & = te with the HK bypass valve at its controller. Should total flw decrease, the pump recirc valve will open on lw f1w to maintain adequate total pump f1w. We rewme.ui also accepting this manual method.

1 l

2.04 d.

Accept for full credit Depress "SI RHST Reset" pushbuttons (label engraving) m Reset "RHST Switchover" (ref. DG ES-03, attached)

Acceptable alternate answer:

Since RHST supply and recirc sung supply valves to the RHR pumps are notor operated valves, power could be renoved at the 2CC, umum.ing the valves in the " fail as is" position (ref. M12FJ01, M12BN01, attached).

2.05 a. (6.05 a.)

Should ac pt manual (at M3) SIS initiation.

2.05 c. (6.05 c.)

R9)-- Asi reformatting of answer to clearly delineate point value for each answer RHR: suction - containment simp (0.25) discharge - RCS hot legs, CCP suction, SI pump suction (0.25)

(if CCP and SI punps list RHR pump suction as their source of water, the reference here should not be necessary for full credit).

CCP: suction - discharge of RHR punps (0.25) discharge - RCS cold legs (0.25)

SI: suction - discharge of RHR pumps (0.25) discharge - RCS hot legs (0.25) i i

1 1

4 .

2.06 b. (6.06 b.)

'Ihe referenced lessen plan (101400800, attached) is inc.w.wct. 'Ihe CCN pumps are M7r load shed an an SIS, they are only shed on an undervoltage signal on their rspdve bus (see attached chart). We will wu.act the lessan plan, but because of the confusian created by this, .we r+> -----d that the ccznplete answer to this question be:

1. Radwaste loads isolate ( E HV 69A/B, 70 A/B close) (0.33)

2. CCN to/frtIn PASS isolate (F3 HV 72, 73, 74, & 75 close)(0.33)

3. CCN heat exchanger tmp control bjpass valves close (m ' ICV 29/30) (0.33)

No credit should be aMari or renoved for references to CCN pumps starting cr stopping.

/

2.07 a. (6.07 a.)

< #1: EDG supplying the bus alone If the EDG is supplying the bus alone due to bus undervoltage (the nest likely case), the ESK relays energize. 7his causes contacts ESA and ESB to close, which defeats the vvvager control and locks speed in at 60 HZ (ref.

E-13KJ07, vendor print fran tech nanual). Sherefore, should also accept "no change" as an alternate answer for speed change.

l

~2.08 c.

Rm -ris also accepting that the #3 seal injectica prevents radioactive water frcru entering the containment atnesphere.

End of section 2 coments.

h j:-

Section'3 3.01 d. (6.08 d.)

'Ihe coiloct answer for 'IDAFP start (AFAS-T) w/c, MDhFP start (AFAS-M) is IN on NB013_,NB02 (not AND). (ref. 'Ihg drwg NOGS ALO9, attached)

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

3.03 (6.09)

Containment pressure has _ZO effect on RCS Wide Rance pressure instruments since the transmitters are located external to the containment building and reference aux building pressure for signal development. (See attached drawing frm the RCS Instruments lesson text). Sitzce the questian asked about RCS pressure and did not specify an instrument, we suggest the answer also accept "no effect" if it identifies the NR pressure instruments and includes the above explanation.

I l

4

3.06 c.

M delta T setpoint development is based on reopdve loop T-avg. If channel II T-avg were to fail high, resulting in the " failed high auctioneered high T-avg", then the channel II m delta T setpoint would decrease. Re = 4 also accepting " decrease". (see Attached incw.pi, frm Tech Specs.) {

i

I /

3.09 b.

Should also accept cooldown valves in lieu of " Bank 1" dump valves and gggg!

in lieu of "available for operation". (see attached lessen plan)

/ . .

)

1 3.11 a.

Accept also as alternate answers:

- Data A cabinet failure alann

- Data B cabinet failure alam (ref. P. 20 of lesson plan and figure 9. attached) b.

Accept also as alternate answers:

- Data A cabinet failure alarm (same references as above)

I f

/

3.12 a and b

- Accept the control "C" designator also

a. high bank D position = C-11 low power interlock = C-5

b. OT delta T = C-3 OP delta T = C-4 (see attached-lesson text) l 4

l l

t

Section 4 4.01 a. (7.02 0.) )

%e same NR +Prature element feeds both the WR recorders and plant ocmputer, therefore, either answer shotdd be accepted for full credit.

(ref. M12BB01)

.i 4.02 b. (7.03 b.) .

h @estion did mt specify operating mode. If < 350 F, RHR could be used for RCS heat removal when the FWIVs and the MSIVs are shut. Should also accept use RHR" .

I

/

4.03 (7.04)

Itan "e", place nain feedwater pump turbine speed controls in AUIO, would nontelly be the last sequential its of the events given if referencing the main EWP Master speed controller (ref. GEN 00-003 step 4.38.2). However, ,

since its "e" does not specify master controller (vs. individual main EWP !

speed controller), an acceptable alternate answer would be to have its "e" inwrMately after starting a main feedwater pump, it s "c". (ref. SYS AE-121 Turbine Driven Main Feedwater Pump Startup" Step 4.4.22) 'Iherefore, should also accept d,b,c,e,f,g,a. l I

l l

t

ps I

4.04 (7.05)

c. #1 should accept frun 7 to 45 minutes (ref. OFN 00-015, loss of Shutdown Coolina, p. 39 of 42).

2 should accept fran 1 to 4.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months (ref. OFN 00-015, Ioss of Shutdown Coolina, p. 41 of 42)

d. Accept aneximize charging and letdown" (ref. OFN 00-015, p.12, step 13 f.)

In lieu of " reflux boiling", should also accept "use of steam i generators" (ref. OFN 00-015, p. 8, step, 10).

4.05 (7.06)

a. Since p.cetel reference is not given, m.um=ud also accepting:

Containment pressure (ref. HG E-0, and AIR 00-059B, attached),

and Pmsse (ref. DG E-0, foldout page, attached) 1 i

4.07 (7.08) 1he first three respenses on the answer key should be acceptod for full credit, since upon empletien of these three itens, 4mHate boration is in p.up.ess. Energizing the pzr backup heaters does not assist in providing or maintaining shutdown margin. Also, accept valve number (BG IW-8104) for third step of opening 4 M iate borate valve (ref. OFN 00-009, attached).

Also we rre-..."ai accepting for full credit, "idiate borate 135 ppu for each control rod not inserted" (ref. DG ES-02, attached).

Section 5 5.20 see 1.20 1

)

l i

i i

l 1

(

l l

i I

l l

/ , .

Section 6 6.01 We r W deletion of part c. %ere are two RNST 1w-low level alanns; low lw 1 and low-lw 2. At the low-low 1 alarm setpoint of 36%, the containment spray suction is switched to the recirc sump per the foldout i page (attached). At the low-low 2 alann setpoint of 11%, approximately 2 minutes of containment spray operation renains prior to loss of NPSH. %e two minute time period assunes that only the containment spray pumps are running when the low-law 2 alarm is received. %e referenced lessan plan cantains an error and should have said that 2 minutes remain upon receipt of the low-low 2 alarm. Part c. clearly refers to the low-low 1 level alann, since the suction is switched at this point. % ere is no definite answer to this question. If the RHR pumps swap prmptly and automatically, the renaining time may be as great as 15 minutes (6,270 gal / min with 93,420 usable gal renaining at 36%). If the RHR pumps do not automatically swap, the time could be considerably less.

6.03 See 2.02 6.04 See 2.03 6.05 See 2.05 6.06 See 2.06 6.07 See 2.07 6.08 See 3.01 6.09 See 3.03

Section 7 7.01 Should also accept " Containment integrity" (see attached Tech Spec.)

-7.02 See 4.01 7.03 See 4.02 7.04 See 4.03 7.05 See 4.04 7.06 See 4.05 7.08 See 4.07-

___-___: - __ _____ -__- __=____-__- _____-__ ___-_ _____ __- - __ _ - :_- _- - _ _

. *: O l.

f 7.12 so aW " entry to EA M area" (see attached pages fu e tion ewrdon manual),

e i

1

8.07 Should also accept "no" with the aps vr iate explanation that the presence of flow does not rean that the entire systein is lined up correctly. (e.g. A vent or drain valve could be open and still have a flow indication on the NCB).

i

- - - - _ -____ a

/ . >

e.

8.08 a.

Also accept "no" with the explanation that the S'JA is not necessarily qualified and trained in the operation of the diesel (see attached page fmn Conduct of On Dutv hanual).

"h%_ _ - - - - - - - - - _ - - _ _ _ ~ - ^ - ~ ~ . _ _ _ - . - _ _ ~~'"~~. _

/

8.10 b.

Also accept the tenn " Human DtO" in lieu of "irdividual assignEXi to monitor th9 conpanent". (see attached page frun AIM 02-100).

l l

l 1

/

i l

j 8.12 "a" should also be accepted. A sucadw.e change was implemented 8/2/88 which' i

chanpd the requirement (see attached sucadore change).

l 1

_ _ - - - - _ i

ML20247G287

Text

SUMMARY

SUMMARY

Navigation menu

Search