Text

Exam Rept 50-456/OL-87-03 on 871214-22.Exam Results:One Senior Reactor Operator Candidate Failed Exam,Six Operator & Seven Senior Reactor Operator Candidates Passed Exam.Rept for Both Units
	ML20148R734
Person / Time
Site:	Braidwood
Issue date:	01/20/1988
From:	Burdick T, Damon D, Lennartz J, Sunderland P; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:	;
Shared Package
ML20148R464	List: ML20148R734;
References
	50-456-OL-87-03, 50-456-OL-87-3, NUDOCS 8802020267
	Download: ML20148R734 (106)
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U.S. NUCLEAR REGULATORY COMMISSION REGION III Report No. 50-456/0L-87-03 Docket Nos. 50-456; 50-457 Licenses No. NPF-72; NPF-75 Licensee: Commonwealth Edison Company Braidwood Station R. R. 1, Box 84 Braceville, IL 60407 Facility Name: Braidwood Station Examination Administered At: Braidwood Station and Production Training Center Examination Conducted: December 1.4-22, 1987

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Examiners: d n'"'c'f'If 'T / M '# f D. J. Damon Date N g7 )c , ,,, _ , , , /; <,]py Lennartz Date '

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f ':-Vb ffrL //2 /tr P. R. Sunderland Date Approved By: h < M( / N c'/'f 5 Thomas M. Burdick, Chief Date Operating Licensing Section Examination Summary Examination administered on December 14-22, 1987 (Report No. 50-456/0L-87-03))

to six operator and eight senior operator candidate.

Results: One senior reactor operator candidate failed the examination.

B602020267 000127 PDR ADOCK 05000456 V pop

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REPORT DETAILS

1. Examiners

D. J. Damon J. A. Lennartz P. R. Sunderland

Chief Examiner

2. Exit Meeting On December 23, 1987 the examiners met with members of the plant staff to discuss findings made during the course of the examinations. The following personnel attended the exit meeting.

Commonwealth Edison Company (CECO)

E. Fitzpatrick, Station Manager G. Masters, Assistant Operations Superintendent D. O'Brien, Services Superintendent W. McGee, Training Supervisor G. Vanderheyden, Training Instructor D. Huston, Training Instructor US NRC T. Tongue, Senior Resident Inspector P. R. Sunderland, Region III Examiner J. A. Lennartz, Region III Examiner J. A. Hopkins, Region III Examiner

a. Generic Strengths (1) In over half of the simulator scenarios, the candidates were required to trip bistables as a result of an instrument malfunction. The candidates demonstrated positive control in each phase of the tripping procedure.

(2) The candidates exhibited strong team work and practiced good communication skills by using "repeat backs" for most communications and acknowledgements on most orders.

(3) The candidates exhibited good familiarity with the General, Normal, Abnormal, and Emergency Procedures.

b. Generic Weaknesses (1) In general, the NS0s, especially the 80Ps, did not perform all of the immediate actions of BwEP-0, "Reactor Trip or Safety Injection," without the SR0 first reading the steps.

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e (2) In simulator scenarios when an inadvertent Phase A isolation occurred, the NS0s did not verify that all required valves changed position and did not restore all systems to their '

normal lineup. In two cases, a Technical Specification (TS) violation occurred on containment temperature.

c. General Comments Although these topics were not covered by every examiner and are not considered generic ici nature, the examiners feel they deserve mention in this report.

(1) Some SR0s demonstrated ALARA awareness by advising "B-men" sent into radiation areas to wait in "low dose zones" while a malfunction was being evaluated.

(2) The candidates were unsure how to apply the 5 (N-18) "dose bank" in 10 CFR 20.101.b.2.

3. Examination Review Following are facility comments on the written examinations and their respective NRC resolutions:

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R0 EXAM COMMENTS Question 1.10 a, b Facility Comment: Exactly five hours for xenon to peak after a power to decrease may not always be exactly correct. Suggest a band of 4-7 hours be acceptable.

NRC Resolution: Concur. Answer key has been modified to reflect this.

Question 1.11.b Facility Comment: 1. Increasing FW flow to the S/G's reduces Tave.

a. Since steady state power is constant, aT is constant.

b. If AT is constant, Th and Tc decrease by the same amount.

2. Since density changes are greater at higher temperatures, more positive reactivity is added to the top of the core by a decrease in Th than at the bottom of the core by an equal decrease in Tc.

3. This causes flux to shift up in the core and al becomes more positive.

NRC Resolution: Concur. Answer key has been modified to reflect this.

Question 2.05 Facility Comment: Since the question asked for four "conditions" that will cause the "250 VDC Batt CHGR 123 TRBL" alarm to alarm, the probable causes listed on the attached BwAR 1-20-C10 should also be considered for acceptable answers.

NRC Resolution: Concur. The answer key has been modified to accept answers from the reference provided that are not redundant to answers on the key.

Question 2.08 a, b Facility Comment: 2.08 a The question asks for interlocks to open 8804B.

In parenthesis, the question states this is the charging pump suction crossover from RHR. In reality, the 8804B is the SI pump crossover. We suggest that either valve interlock should be accepted.

2_. 08 b Overpressurization of CV pump suction would be the correct answer if 8804A is used in part a. ,

1 o NRC Resolution: Concur. Either valve interlock will be accepted for part a, and the associated reasons for the valve used in part a will be the correct answer for part b. The question will be modified for future exams.

Question 2.10 Facility Comment: 2.10 b The response "inserts speed and voltage cuntrol while maintaining only the emergency trips" should be acceptable since a specific list was not requested by the question.

NRC Resolution: Concur. The answer key has been modified to reflect this.

Question 2.12 Facility Comment: Another acceptable answer should be loop flow indications.

NRC Resolution: Concur. The answer key has been modified to reflect this.

Question 3.09 b Facility Comment: Lo Tave value indicated in exam key (6, ) should be (564 ).

NRC Resolution: Concur. Answer key has been modified to reflect this.

Question 3.11 a Facility Comment: Present inputs to Subcooling Margin Monitor are:

1. Average of 10 highest CET's.

2. RCS wide range pressure.

3. Containment pressure,

4. Containment radiation.

This change is still in routing and has not been incorporated into all of the Braidwood training material.

Any of these four answers should be accepted.

NRC Resolution: Concur. The answer key has been modified to accept any three of the proposed four answers for full credit.

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i e Question 3.13 a Facility Comment: Answer should be FALSE. The LOCAL / REMOTE switch does not affect switchgear operation. A pump may always be started (no trips present) by locally installing the switchgear breaker and closing it.

NRC Resolution: Concur. The answer key has been modified to reflect this.

Question 4.08 Facility Comment: Other acceptable answers related to the upper limit of < 1000 psig should be thermal shocking of the pump shaf t, bearing and seal, a general statement concerning damage to the pump components.

NRC Resolution: Do not concur. Thermal shock of the pump shaft, seal, and pump bearing would occur only if a loss of seal injection were experienced as stated in the provided referer.ce.

Therefore, credit will be given for the proposed response only if the candidate states that a loss of seal injection has occurred. A general statement about damage to pump components by itself will be given partial credit.

Question 4.14 a Facility Comment: a. These switches are placed in the ISOL position in the event:

Damage has possibly occurred to any remote DG Control Circuitry OR Control Room has been evacuated A fire in the C.R. or AEER is only one example of possible damage - many other types of damage could cause us to go to ISOL.

Full credit should be given for other events that could cause damage to remote circuitry or the above l listed answers. )

NRC Resolution: Concur. The answer key has been modified to reflect this.

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\ e Question 4.15 a Facility Comment: Key is only partially correct. In addition to lowering pressure to allow low head injection to occur it is also to recover the core via SI accumulator injection.

NRC Resolution Concur. The answer key has been modified to reflect this.

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s e SRO EXAM COMMENTS Question 5.01 Facility Comment: By the definition of QPTR in Tech Specs if one detector is inoperable it is not used in QPTR calculation. Recommend an alternate acceptable answer be "no change" if above assumption made.

NRC Resolution Concur. Answer key expanded.

Question 5.08, b Facility Comment: 1. Increasing FW flow to the S/G's reduces Tave.

a. Since steady state power is constant, AT is constant,

b. If AT is constant, Th and Tc decrease by the same amount.

2. Since density changes are greater at higher temperatures, more positive reactivity is added to the top of the core by a decrease in Th than at the bottom of the core by an equal decrease in Tc,

3. This causes flux to shift up in the core and al becomes more positive.

NRC Resolution: Concur. Answer key corrected.

Question 5.09 Facility Comment: It is felt that RCS pressure should be an acceptable alternative to pressurizer pressure, in that pressurizer pressure controls RCS pressure and the pressure in the RCS is the concern in DNB.

NRC Resolution: Concur. Answer key expanded.

Question 5.10 d and e f acility Comment: To obtain gauge pressure 15 psia should be subtracted from !

the answer, not added.

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d. 1161-15 = 1146 psig

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e. 893 psia - 15 = 878 psig NRC Resolution: Concur. Answer key corrected.

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Question 6.02 facility Comment: If the breaker is racked in and shut the pump will be running. A more appropriate answer would be the breaker racked in with DC control power available.

NRC Resolution: Concur. Answer key modified.

Question 6.06 Facility Comment: The limit of 325 psig also accounts for NPSH requirements, ,

backpressure, pressure losses, and instrument losses. Any combination of these along with the seal AP requirements should be acceptable.

, NRC Resolution: Concur. No credit will be deducted for discussion of these other factors, as long as seal delta-P requirements are also discussed.

Question 6.07 s Facility Comment: The question specifically asks about the sequence of events "from the time the annunciator is received until voltage is restored to the bus." The last statement of the answer key, "Loads are sequenced back on bus," occurs after voltage is restored to the bus and thus should not be required for full credit.

NRC Resolution: Concur. Answer key modified and point valve adjusted.

Question 7.04 a Facility Comment: In general, this statement is true, since skipping steps is almost always an exception based upon plant conditions i not assumed by the procedure. We s;ggest this question ;

be deleted. (

l NRC Resolution: Do not concur. It is apparent from the comment and phone conversations with facility personnel that this question '

was interpreted to say that all steps must be completed in order prior to preceding to the next step. However, the words "in order" did not appear in the question.

The original reference cited in the question supports the .

I answer as given in the original answer key. The facility l

. submitted no additional reference material to refute the l original reference. Therefore, the answer key remains i unchanged. '

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. O Question 7.05 Facility Comment: The question infers that all of the RNO steps could not be completed. Therefore, the first portion of the answer key, "if further contingency actions are provided, perform the next contingency action" should not be required for full credit.

NRC Resolution: Concur. Answer key modified and point valve adjusted to 1.0.

Question 7.08 Facility Comment: BwCA 0.1 and BwCA 0.2 should also be acceptable since it is stated the status trees are monitored for information only and NOT to implement the BwFR's.

NRC Resolution: Concur. Answer key expanded to include:

4. During BwCA 0.1 Steps 1-9

5. During BwCA 0.2 Steps 1-7 Question 7.09 Facility Comment: 7.09 b Since the IB CCP has been out of service for > 72 hrs, and the plant is still in MODE 1 (was not placed in hot standby in the following 6 hrs, etc.) conditions have degraded beyond the Tech Spec limitations. Thus, an alert level should be acceptable per EAL 14.

7.09 f Not enough information given to warrant activation of GSEP by condition 25 (Fuel Handling Building exhaust has been diverted through the charcoal filters) at this point.

For cond' tion 31, the stated conditions would probably develop into a GSEP conditions, but for the point in time pertaining to conditions stated in the question, NONE should also be an acceptable answer.

NRC Resolution: Partially concur. Answer key for part b is modified as requested. Answer key for part f is modified to accept either "None" or "Unusual Event."

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eO Question 8.05 Facility Comment: It is felt that the following should be added as acceptable answers.

1. Write a temporary or permanent change if required.

2. Return the system to the as found positions in the applicable M or E lineup if the procedure is to be terminated.

3. System placed in a stable condition.

NRC Resolution: Partially concur. The facility requested answers dealing with system lineups are added to the answer key. However, the N50 is not normally the person who makes the decision and implements writing procedure changes. Since the question specifically asked for NS0 actions, this answer is not added to the answer key.

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EnfEGUATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION FACILITY: _BRAlpWggp_1Lg___________

REACTOR TYPE: _PWR-WEg3________________

DATE ADMINISTERED: _8?f1?fid________________

EXAMINER: _QAMQNz_pz_______________

CANDIDATE: _________________________

INSIBUCIJgNS_IQ C9Np1991El Use separate paper for the answers. Write answers on one side only.

Staple question sheet on top of the answer sheetn. Points for each question are indicated in parentheses after the question. The passing grade requires at least 70% in each category and a final grade of at least 80%. Examination papers will be picked up six (6) hours after the examination starts.

% OF CATEGORY % OF CANDIDATE'S CATEGORY

__YOLVE_ _I9106 ___SGQ6E___ _YO6VE__ ______________G91 Egg 6Y_____________

_2@t99__ _2Et2D ___________ ________ S. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND THERMODYNAMICS

_29tE9__ 2312E ___________ ________

6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION

_26sE9__ .23119 ___________ ________

7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL

.2@t99__ _2E12E ___________ ________ 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS

_22199__ ___________ ________% Totals Final Grade All work done on this examination is my own. I have neither given nor received aid.

Candidate's Signature

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o NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS ;

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During the administration of this examination the f ollowing rules apply: ;

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

i I i 2. Restroom trips are to be limited and only one candidate at a time may j leave. You must avoid all contacts with anyone outside the examination ;

, room to avoid even the appearance or possibility of cheating. j

! I j 3. Use black ink or dark pencil gnly to facilitate legible reproductions.

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

1 1 5. Fill in the date on the cover Sheet of the examination (if necessary). [

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) 6. Use only the paper provided for answers.

7. Print your name in the upper right-hand corner of the first page of gagh i section of the answer sheet. j O. Consecutively number each answer sheet, write "End of Category .." as !

appropriate. start each category on a new page, write only on one side ,

j of the paper, and write "Last Page" on the last answer sheet. [

9. Number eachanswer as so category and number, for example, 1.4, 6.3.

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10. Skip at least thtee lines between each answer.

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11. Separate answer sheets from pad and place finished answer sheets face [

down on your desk or table. .

l i 12. Une abbreviations only i f they are commonly used in facility L(1gtgigtg.

a p l 13. The point value for each question is indicated in parentheses after the l 1 question and can be used asa guide for the depth of answer required.

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14 Sow all calculations, methods, or assumptions used to obtain an answer !

to mathematical problems whether indicated in the question or not.

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15. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE l GUESTION AND DO NOT LEAVE ANY ANSWER BLANK. f i

16. If parts of the exan.ination are not clear as to intent, ask questions of l f the twgmLQgt only, f I !

j 17. You mt .t 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 )

completing the examination. This must be done after the examination has j been completed. j

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A18. When you complete your examination, you shall 1*

. a. Assemble your examination as follows:

(1) Exam questions on top.

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

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

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

c. Turn in all scrap pape- 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 thic area while the examination is still in progress, your license may be denied or revoked.

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0.5 43x10 30 ----------

24x10 6 cm 2, ,,c 10 17 Linear Absorption Coefficients p (cm~I)

Energy (MEV) Water Concrete Iron Lead 0.5 0.090 0.21 0.63 1.7 1.0 0.067 0.15 0.44 0.77 1.5 0.057 0.13 0.40 0.57 2.0 0.040 0.11 0.33 0.51 2.5 0.042 0.097 0.31 0.49 3.0 0.038 0.000 0.30 0.47

. 5s__IdE93y_gg_NyC(gg3,[Q[{f_@69NJ QfEBSJjgN _E6UJpS 2 2_999 PAGE 2 l IdE50991N3DjCS I t

QUESTION 5.01 (1.50)

The plant is operating at 50% power with control rods in manual. How does a HIGH failure of power range channel N-44 LOWF.R detector affect the following indications? Limit your answer to INCREASE, DECREASE, MORE NEGATIVE, LESS NEGATIVE, or NO CHANGE. (.5 ea)

a. Lower Quadrant Power Tilt Ratio

b. Delta Flux indication (channel 4)

c. OP delta T setpoint (channel 4)

QUESTION 5.02 (1.50)

A cooling water pump is operating at 1500 rpm. Its capacity is 250 gal / min at a discharge pressure of 15 psig which requires 40 KW of power.

Determine the pump capacity, speed and power requirement if the pump discharge pressure drops to 10.0 psig due to reduced speed.

QUESTION 5.03 (2.00)

Unit 1 is operating at 100% power (3411 MWt) as indicated on nuclear power instrumentation. The following data is recorded:

Feedwater Temperature 439 deg F Total Feedwater Flow 15.1x10E6 LBM/HR Steam Pressure 992 psig Feedwater Enthalpy(hf) 418.5 BTU /LBM Other System Losses and Gains -

0-From the information provided determine the actual percentage power output of the primary system.

QUESTION 5.04 (1.00)

Although the control rods may be posi tioned axially anywhere in the core, the rods must be above a specified height during reactor operations. This

, height is referred to as the rod intirtton limit. State the three reasons for the control rod insertion limits.

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

Dz__IbE95Y_9E.UUSLE98_EDWEB.EL90I_9EEBBI190i_EL91952.999 PAGE 3 IbEBD9910901G5 t i

t QUESTION 5.05 (2.00) 6

! Indicate whether the following situations result in SUBCOOLED, SATU9ATED,

or SUPERHEATED fluid conditions. Assume NOT/NOP, 100% power.

4 f a. Presnurizer PORV relieving to the PRT (0.5)

b. Steam generator safety valve relieving to atmosphere (0.5)

c. Steam f rom a Moisture Separator Reheater entering a low pressure turbine (0.5)

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j d. Condensate exiting the condenser hotwell (0.5) ,

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QUESTION 5.06 (3.00) 1 j A questionable FCC calculation shows that criticality should be achieved

when 3000 pcm has been added to the core. A boron diluion of 150 ppm !

i (1500 pcm) is planned, followed by control rod withdrawal to criticality. !

l The initial count rate is 50 cps. ]

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a. WHAT is the expected count rate after the 150 ppm boron dilution? (1.0) f l l j b. Following the first 75 ppm dilution, the source ranges indicate 80 cos, j 3

WHAT amount of reactivity in pcm should the original ECC calculation !

have derived as sufficient to reach criticality? (2.0) i QUESTION 5.07 (2.50)

! l l After operation at 100% power for several weeks near the end of cycle, it h I

is decided to reduce power to 75% using rods only. I l a. After reaching 75% power, what rod motion would be required to !

maintain the plant at 75% power over the nomt 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months assuming l l no change in boron concentration? Include any applicable time )

periods. (1.0) :

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b. Explain how the fiosion product production and removal mechanisms !

cause a reactivity transient after a power reduction from 75% to l 50% power. Include time periods for the various reactivity effects up !

to equilibrium. (1.5) {

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QUESTION 5.08 (1.50)

Would the Axial Flux Difference become MORE NEGATIVE or LESS NEGATIVE for the following conditions? STATE THE REASONING FOR YOUR CHOICE. (.5 ea)

a. OT Delta-T runback from 100*/ power with rods in automatic to 50% power.

b. Feed flow increases to the steam generators with rods in manual.

c. Xenon is building into the bottom of the core more than in the top of the core.

QUESTION 5.09 (3.00)

Name the THREE primary parameters that affect DNB and DNBR which can be controlled by the reactor operator, other than core flow or flux distribution. Briefly explain how an INCREASE in each of these other three i parameters affects the DNBR. Treat each parameter separately and assume all other parameters remain constant.

QUESTION 5.10 (2.50)

The plant is operating at 33% power when the 18 S/G Main Steam I sol at i on Valve fails shut. Using the below initial conditions, calculate the new steady state values for the listed parameters.

Assume no operator action, rod control system in manual, all other control systems in automatic, no reactor trip and no SI actuation. ,

State all assumptions and show all work.

Initial conditions: Tavg = 554 F j Tstm = 539 F Core Delta T = 18 F '

a. Turbine power j

b. Tavg (loop 18) {

c. Tavg (l oop 1D)

d. S/G pressure (loop 18)

e. S/G pressure (loop 1D) l l

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QUESTION 5.11 (1.00)

TRUE or FALSE?

a. As Keff approaches unity, a smaller change in neutron l evel will result for identical changes in Keff.

b. As Keff approaches unity, a longer period of time is required to reach the equilibrium neutron level for identical changes in Keff.

QUESTION 5.12 (1.00)

During a reactor startup, 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 one of the f ollowing statements describing the relationship between the reactivity values of the first and second reactivity additions is correct?

a. The first reac ti vi t y addition was larger,

b. The second reactivity addition was larger,

c. The first and secon reactivi ty addi tions were equal,

d. There is not enough data given to determine relationship of reactivity values.

QUESTION 5.13 (1.00)

When parforming a reactor S/U to full power that commenced five hours after a trip from full power equilibriun conditions, a 0.5% per min ramp was used. How would the resulting xenon transient vary if instead a 2% per min ramp was used? (Choose one)

a. The xenon dip for the 2% per min ramp would occur sooner and the magnitude of the dip would be smaller.

b. The xenon dip for the 2% per min ramp would occur later and the magnitude of the dip would be smaller,

c. The xenon dap for the 2% per min ramp would occur sooner and the magnitude of the dip would be larger,

d. The xenon dip for the 2% per min ramp would occur later and the magnitude of the dip would be larger.

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QUESTION 5.14 (1.50)

A reactor is critical at 10 -8 amps in the intermedi ate range. An inadvertent boron dilution puts the reactor on a 0.5 DPM startup rate.

Calculate the change in boron concentration caused by this dilution. STATE any assumptions you make and assume BOL conditions.

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(***** END OF CATEGORY 05 *****)

ku__ELeNI_gXgIges_pgSigui_ggu1896,_egp_1ggIBygggIeI1gN PAGE 7 QUESTION 6.01 (2.50)

Concerning the steam dump system, state all the conditions that will activate each of the following permissives. Include setpoints and coincidence, where applicable. (1.25 pts each)

1. C-7 (loss of load)

2. C-8 (turbine trip)

GUESTION 6.02 (2.00)

What 4 conditions must be satisfied in order for the common "0" CCW pump to auto-start? Assame NO safety injection or blackout. Setpoints not required.

QUESTION 6.03 (1.50)

Complete the following table regarding steam generator level setpointst

(.25 pts each) l Item Unit 1 Unit 2 Hi Hi Turbine Trip (X NR) (a) ______% (b) ______%

Hi Level Alarm (% WR) 92.4 % 92.4 %

Normal Operating Level (% NR) (c) ______% (d) ______%

Lo Level Alarm (% NR) 45.8 % 22 %

Lo Lo Reactor Trip (% NR) (e)

______/. (f) ______%

i QUESTION 6.04 (2.00) !

Concerning the RHR System: l i a. What is the purpose of and the reason for the minimum flow recirculation lines? (1.0)

b. What is the purpose of and the reason for the heat exchanger bypass flow control valves (FCV-618 FCV-619)7 (1.0) 1

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6a__P6$yI_pYgIgD}_gg}]GN 2,CgN]6963,9ND_Jy}IBUDENISIJgN PAGE B QUESTION 6.05 ( .50)

True or False?

The major reason that the pressurizer spray line taps off of a cold leg is because the lower temperature coolant wil reduce pressure in the pressurizer faster than would coolant from a hot leg.

QUESTION 6.06 (1.50)

RCP's may be operated only when the RCS pressure is greater than 325 psig.

Explain the basis for this restriction.

QUESTION 6.07 (2.50)

Describe the sequence of events associated with a 4160V ESF bus that occur when the bus undervoltage annunciator is illuminated, from the time the annunciator is received until voltage is restored to the bus. Assume the cause of the annunciator is a degraded transformer that must be replaced ,

l and that bus voltago is 90% of nominal. Assume NO operator action.

QUESTION 6.08 (1.50)

There are 18 automatic and manual trips associated with the Emergency Diesel Generators. During an emergency start, all but three of these trips are disabled. What three automatic and/or manual trips are still operational during an emergency start?

OUESTION 6.09 (2.50)

! Unit 1 is at 75% power, Cycle 2, 450 ppm baron concentration. CVCS is lined up with a 75 gpm orifice on line, IB centrifugal charging pump in operation, and control systems in automatic. The makeup system is set up for a 5 ppm boration. All other control systems are in automatic.

Pressurizer level channel 459 (controlling channel) then fails to 0%.

Several minutes later you notice rods stepping out and Tave dropping 1 rapidly. After rods stop, Tave continues to drop, j Assume no reactor trip and no operator action. Explain why Tave is dropping, including in the explanation any initiating signals and t

interlocks.

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5' QUESTIO 6.10 (1.50) 4 Following a blackout on Unit 2, both diesel generators automatically ,

start, but you notice that breaker 2423 (2B DG output breaker) did not ,

j close. What are THREE (3) logic conoitions needed for breaker 2423 to l

, automatically close? Setpoints not required. ,

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1 i GUESTION 6.11 (1.50) ,

j Unit 1 has tripped. You are given the following data concerning l

'l parameters immediately prior to the tript (Assume all channels read the r j same) l l

] Reactor power 95% l

}

Unit Aux transformer output voltage 5200 volts .

I i Loop f l ows 96*/. f

! t Turbine emergency trip system oil pressure 440 psig !

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]' Pressurizer pressure 2285 psig -

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Steam generator levels 50% j i

List all possible causes of the reactor trip from the above data. Include I i in your answer the applicable setpoints (coincidence not required). f r

QUESTION 6.12 (1.50) 3 Unit 1 is in mode 3 with shutdown banks withdrawn. A shutdown was j performed 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ago to repair a f ail ed-l ow turbine impulse channel. ILC f i technicians are performing repairs on the failed channel.

)

l The IbC foreman has requested permission to test the failed channel. A l temporary procedure change was written to allow testing of the channels in f other than mode 1. What precautions / limitations must be observed before you will allow the test? Why) l.

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6.__E690I_!!!IEDS_95!19di_990IB962_909_19!ISUdEUISIJgy 2 PAGE 10 QUESTION 6.13 (1.50)

The reactor operator reports to you that there is a demand for automatic rod withdrawal, but the rod control system is not responding. You direct him to place rod control in manual and attempt to withdraw rods. The rods move outward in manual.

What TWO (2) possible rod withdrawal interlocks may have existed to prev- ..

the automatic withdrawal of rods?

QUESTION 6.14 (2.00)

On the previous shift, loop 1 Thot RTD failed low. The appeceriate bistables were tripped and repairs are being performed. It i s estimat ed that repairs will require 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

One hour into your shift, pressurizer pressure channel 456 (division II) fails low.

What actions should be performed with regard to the bistables associated with the pressurizer pressure channnel? Assume mode 1.

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(***** END OF CATEGORY 06 *****)

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. 869196991G66_G99IB96 QUESTION 7.01 (3.00)

For each of the following cases, state whether or not emergency boration is required per BwCA-PRI-2, "Emergency Boration": (.375 ea)

a. One control rod f ails to insert on a reactor trip

b. Reactor is in mode 6 with boron concentration of 1900

c. Reactor power is 1 0 0*/. w i t h control bank D at 70 steps

d. Delta 1 is at -17. Target delta 1 is -3

e. RCS temperature is stable at 551 degrees F following a trip when a steam generator becomes faulted

f. Reactor is in mode 3 with Keff of .98

g. During a startup, the reactor goes critical with the "Rod Insertion Low Limit" alarm lit

h. During a reactor startup, a steam dump failure results in a cooldown to 550 degrees F f

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. S99196991C86_CgN]3Q6 QUESTION 7.02 (3.00)

While functioning as Shift Supervisor, a condition arisen which requires entry into containment while critical at 30*/. p ower . The operator entering will receive an estimated whole body dose od 40 mrem. The f ollowing data is available:

Operator 1 2 3 4 Sex Male Female Male Female Age 27 24 38 20 Wk/ Exposure 35 mrem O mrem 100 mrem 30 mrem Otr/ Exposure 1230 mrem 165 mrem 970 mrem 1120 mrem Life Exposure 5200 mrem 54730 mrem 9970 meem Remarks History 2 months Form 4 Form 4 Unavailable pregnant on file on file Each operator is technically competent and physically capable of performing the task. Emergency limits do not apply and Rad-Chem will not approve extensions. These are the only operators available and at least one of them MUST be chosen for the job.

Give your reasons (based on legal / admin limits) for accepting or rejecting EACH operator. (.75 ea)

QUESTION 7.03 (1.50)

I I What are the entry condi tions f or BwEP ES-0.0, "Rediagnosis"?

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i GUEST 10N 7.04 (1.50) i Concerning the BwEP's, answer the following TRUE or FALSE: (0.5 each)

a. In general, a required task as stated in a procedural step MUST be completed prior to proceeding to the next step.

b. The procedures are applicable in modes 1 through 5.

c. The only entry point into the BwEP's is through BwEP-0.

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. l QUESTION 7.05 (1.00)

While performing BwEP-1, "Loss of Reactor or Secondary Coolant," you enter a step where the Action / Expected Response is not satisfied (lef t hand column). You enter the Response Not Obtained (right hand column) for that step and find that you cannot complete the actions as stated. What is your next action concerning use of the BwEP7 GUESTION 7.06 (1.50)

While performing DwEP-3, "Steam Generator Tube Rupture," conditions are such that you decide to use the "adverse containment" values for performance of the BwEP. State ALL conditions that must be satisfied before you can again use the "normal containment" values in the BwEP.

State any assumptions you make.

QUESTION 7.07 (1.00)

The reactor operator reports that he intends to trip the RCP's while you are performing BwEP-1, Loss of Reactor or Secondary Coolant. The following data is available to you.

RCS cooldown rate: 30 degrees F/hr on steam dumps RCS pressure: 1250 psig Charging Flow 75 gpm CC water to RCP'st available Containment Phase B not actuated i Assume all other indications / system status are normal.

Per the foldout page for DwEP-1, do you allow the RO to trip RCP's? Why or l

why not7 (What criteria are/are not met?)

4 QUESTION 7.08 (1.S0)

Describe two instances, while performing emergency procedures, when an exit to a functional restoration guideline from the CSF status trees is not performed, even if a red path is obtained.

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- 599196991C96_CggIggL QUESTICN 7.09 (4.00)

Using the attached pages from Bw2P 2OO-1A1, classify each of the f oll owing events. Consider each event separately. Limit your answer to None, Unusual Event, Alert, Site Emergency, or General Emergency. Assume that any condition not stated is normal and satisfies LCO requirements.

4. A fire in the control room resul ts in thick smoke in the control room and subsequent evacuation of the control room.

b. 1B centrifugal charging pump has been out of service for the last 7 days. Assume mode 1.

c. A steam generator code safety is blowing by and cannot be isolated.

d. A steam generator tube fails, resulting in a 70 gpm leak in 2D steam generator. Leak rate prior to the failure was 3 gph.

e. An ILC error during surveillance results in an ECCS actuation.

Primary pressure remains stable at 2235 psig.

f. An irradiated fuel assembly is dropped in the cavity. Bubbles escaping from the assembly are reported.

g. An aircraft crashes in the switchyard. The resulting fire requires l the complete de-energizing of the switchyard ring busses.

h. A demonstration at the main gate prevents the oncoming crews from entering the station for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , t

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Zs..E89GE998EE_ .NQBd@bt_@@yQ6096t_Edg8QgGQX,QUQ PAGE 15 609196901606_G99I696 QUESTION 7.10 (2.25)

Given the following data concerning the power range nuclear instruments:

Channel NR41 NR42 NR43 NR44 Upper detector current 104 0 116 114 Upper 100% current 208 224 224 216 Lower detector current 106 0 112 100 Lower 100% current 212 220 224 216 All readings are in milliamps. NR42 is inoperable and out of sersice with bistables tripped.

a. What is the quadrant power tilt ratio? 19wCS 2.4.1.a-1 is included for your use. (1.25)

b. Awsuming the OPTR is greater than 1.09, what actions must be taken according to Technical Specifications? Assume that control rods and shutcown rods are aligned properly, and that power is 75%. Time limits not required. (1.0)

QUESTION 7.11 ( .75)

You are working in containment when your self-reading dosimeter falls out of your pocket. You retrieve it and the indicator is missing. What 3 actions must be taken by you per DwRP 1000-A1, "Radiation Protection Standards"?

QUESTION 7.12 (2.50)

a. Per DwRP 1000-Al, "Radiation Protection Standards," describe the differences between a Type 1 RWP and a Typo 2 RWP, concerning the following items: (2.0)

1. Dose rate

2. Length of time that the RWP is valid

b. True or False?

l A worker may be allcwed to enter an airborne radioactivity area under j a Type 1 RWP. (.5) l 1

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. 22__eggcEguagg_:_yggessi_egsgetegi_EggggEygy_909 PAGE 16 I 599196991c06_c90IB96 GUESTION 7.13 (1.00)

A startup is performed on Unit 1 with an ECC of Bank D at 150 steps.

Criticality is not achieved by the time Bank D reaches 220 steps. Per BwGP 100-2, "Plant Startup," what 2 actions must be performed?

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- Du__990101EI69IIVE P6QQgQW655t_QQUQlIlQU$t_60Q_(10118IlgG5 PAGE 17 QUESTION 8.01 (1.00)

Answer the following TRUE or FALSE per BwAP 330-6, "Caution Card Procedure":

a. All caution cards shall be authorized by the Shift Foreman (or designee).

b. Only the person that requested a caution card may authorire removal, i

QUESTION B.02 (1.50)

Refer to the attached page f rom BwEP-1.

BwAP 340-1, "Use of Procedures for Operating Department," contains specific guidance for the use of "open bullets" and "closed bullets" in the BwEP's.

What is the difference, to you as an operator, between "open bullets" and "closed bullets" when using the BwEP's?

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Di __99dINJ)]SSIlyg PQQgEpySgS 3 gQNQlllgN}i,9NQ,blDlI@IlgNg PAGE $8 QUESTION 8.03 (5.00) .

l For each of the following conditions, state whether or not a Technical i Specification LCO should be entered (yes/no only - no explanation 1 required). Treat each case independently. Assume all other conditions not stated satisfy LCO requirements. (0.5 ea)

a. Primary containment average air temperature is 126 degrees F. The i reactor is in mode 6.

b. RWST boron concentration is 2000 ppm with temperature of 40 degrees F. The reactor is in mode 1.

c. MSIV's are tested and stroke from full open to full closed in 30 seconds. The reactor is in mode 3.

d. The containment purge isolation system is inoperable. Purge isolation valves are shut. The reactor is in mode 1.

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e. One containment air lock door is innperable. The reactor is in mode 4 g f. One transformer of the System Auxiliary Transformer bank is out of 1 service due to an inoperable disconnect. 1he reactor is in mode 3.

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g. One of the transmission lines from the switchyard is out of service.

l The reactor is in mode 1.

h. Shutdown margin is .13% delta k/k. The reactor is in mode 1.

1. "B" centrifugal charging pump discharge valve is shut and inoperable.

The reactor is in mode 2.

J. Boric acid storage tank temperature is 70 degrees F.

I GUESTION 8.04 (1.00)

Answer each of the following True or False according to BnAP 300-1, l "Conduct of Operations." (.5 pts each) i

1. Control room personnel will man the fire brigade af required to 1 fight a fire.

2. If an NSO must go behind the back panels of the control board, he 15 still considered "At the controls." i

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e QUESTION 8.05 (2.00)

Low power testing is in progress on Unit 2 when the NSO discovers that two approved procedures for the testing appear to conflict. The NSO directs that testing be halted and notifies the shift supervisor. According to DwAP 340-1, "Use of Procedures for Operating Department," what 2 additional actions should be taken by the NSO?

I QUESTION 8.06 (2.50)

List in order, from me?t severe to least severe, the critical safety function status trees and the color priorities for the status trees.

QUESTION O.07 (2.25)

Per DwAP 1300-3, "Preparation and Approval of Temporary Procedures and Temporary Changes ta the Permanent Procedures", 3 criteria must be met before a temporary t'.r oc edur e or temporary change may be written. What are t h e s t- criteria?

QUESTION B.08 (1.00) i l

If a temporary procedure / change is NOT authorized for EXTENDED use, when l does it become invalid?

1 QUESTION 8.09 (1.75) 7 Tschnical Specification 3.4.8 places limits on reactor c ool ant specific l activitieb. Per Tech Spec Danes, what are these limits based on? Include any applicable time limits. !

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j QUESTION O.10 (1.50)

Reforence is made in the technical specifications to various systems, ,

I components or pieces of equipment being OPERABLE. Per the technical l l specifications definttion, what is meant by OPERADLE?

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9t__0901Ni@l@@IlyE_PQQCEQUQEgt_CQNgillgNS t_QNQ, Lid,{I@IlQU@ PAGE 20 QUESTION 8.11 (3.00)

Technical Specification 3.4.6.2 addresses RCS leakage. In this Tech Spec, limits are placed on pressure boundary leakage, unidentified leakage, identified leakage, and controlled leakage.

Per the Tech Spec de'initions, define IDENTIFIED LEAKAGE, CONTROLLED LEAKAGE, UNIDENTIFIED LEAKAGE, and PRESSURE BOUNDARY LEAKAGE.

QUESTION O.12 (2.50)

In technical specifications, section 2, there are two (2) specific SAFETY LIMITS imposed.

a. What are these 2 safety limits? (1.5)

b. If a safety limit is exceeded, what action must be taken by the operator? Include maximum time limits. Assume mode 1. (1.0) l l

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(oe****seeses* END OF EXAMINATION esees**eoesses )

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Dz..IdE98!.9E UBGLE98_E9 WEB _EbeUI_9EE59I190t_E691DDi 9NQ PAGE 21 THgRMQQyy@ mig 5 ANSWERS -- BRAIDWOOD 142 -87/12/14-DAMON, D.

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i ANSWER 5.01 (1.50)

I a. !NCREASE (will accept NO CHANGE if candidate states that the channel is inoperable.) ,

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b. MORE NEGATIVE ,

c. NO CHANGE .

l REFERENCE L T Braidwood R= Theory, Ch B, obj 7, 11 and pp B-17 to 0-22 t 015000A105 015000A202 015000K501 ...(KA'S)

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i ANSWER 5.02 (1.50)

I t N1=1500 rpm V1=250 gpm Hp1=15psig Pl= 40 KW L l I N2 = 1500 ser root (10.0/15) = 1224.7 rpm (0.53 ,

2 V2 = (1224.7/1500)(250 gom) = 204.1 gpm (0.53 3

4 P2 = (1224.7/1500) (40 KW) = 21.7 KW (0.53 ,

i REFERENCE Braidwood Fluid Flow, Ch 2, obj 4 and pp 2-26 to 2-33 OO3OOOA203 191004K105 ...(KA'S) i i I

ANSWER 5.03 (2.00) l' 0=m delta h !

SYSTEM ENTHALPY FW ENTHALPY ENTHALPY R!SE POWER !

(BTU /LBM) (BTU /LBM) (BTU /LBM) hfg x Total FWFlow -

hg hf hfg BTU /HR :

, 1193 418.5 774.5 11.695=10E9 l

l (1.0) '

i 11.695x10E9 BTU /HR X 1MW /3.413x10E6 BTU /HR = 3426.6 MW (0.5) l 3426.2 MW/3411 MW = 1 0 0 . 5 '/. (0.5) ;

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REFERENCE Braidwood Thermodynamics, Ch 3 obj 5 and pp 3-69 to 3-80, 3-109 to 3-111 j W Thermal-Hydraulte Principles and Applications to the PWR, Pg. 6-47.

193OO7K106 193OO7K108 ...(KA'S) 1 1

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Es. 3d5991.9E.Nyg6g@R,EgWgR,E6@NJ, GEER 9))QN 3 ,F69]QS3 ,9Ng PAGE 23 Ib550991N9DJgp

. ANSWERS -- BRAIDWOOD 1L2 -87/12/14-DAMON, D.

i ANSWER 5.04 (1.00) l I

1. Minimize the consequences of a rod ejection accident, OR potential effects of rod misalignment on associated accident analysis are limited.

2. Guarantee a sufficient shutdown margin from a given power level. i

3. Produce an axial flum distribution which prevents high local peak power ,

levels, or acceptable power distribution is maintained. (!f the control l rods are inserted to far into the core , the power production in the !

core is suppressed in the top of the core raising the power production i l the bottom of the core. The higher power in the bottom of the core could cause abnormally high fuel temperatures and melt the fuel.)

(.33 ea answer) t REFERENCE l Braidwood R= Theory, Ch 6, obj 9 and pp 6-23 to 6-26 l W Reactor Core Control for Large PWR's, pp. 6-29 L 6-30. '

192005K114 192005K115 192005K116 ...(KA'S)

ANSWER 5.05 (2.00)

a. Saturated ,

l B. Superheated -

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c. Superheated

d. Subcooled (0.5 each)

REFERENCE Braidwood Thermodynamics, Ch 3, obj 9 and pp 3-101 to 3-107 l Mollier Diagram i Steam Tables (

193004K115 ...(KA'S) ;

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ANSWER 5.06 (3.00)

a. (Since the amount of reactivity inserted is one-h:1f of the total amount needed to reach criticality.) the count rate should double, or about 100 cas. (1.03 OR For rho = K-1 (valid approximation) l t

CR1/CRO = (1-KO)/(1-K1) l

= (1-(rhoO + 1))/(1-(rhol + 1))

l = rhoO/rhol

= 2 CR1 = 2sCRO = 100 cps (actual is 98.54 cps) C+1.03 i

b. For rho = K-1 ;

CR1/CRO = rhoO/rhol OR rhoo = rhol:CR1/CRO C+0.53 Since the c"ange in reactivity was 750 pcm (one-half of the i total dilution): C+0.53 rhoO = tehoo + 750 pcm)*CR1/CRO '.

= (rhoO + 0.OO751s00/50

{

= 1.6 rhoO + 0.012 i -0.6 rhoo = 0.012 rhoO = -0.02

= -2000 pcm Therefore, the original ECC should have determined that ;

criticality would be achieved if 2000 pc.1 was dded to the core. C1.03 REFERENCE Braidwood R= Theory, Ch 5, obj 7 and pg 5-3 Drandwood Rm Fhysics, Ch 6, obj 13 and pp 6-21 to 6-24 Ch 7 obj 4 and op 7-37 to 7-45 W Fundamentals of Nuclear Reactor Physics, pp 5-22 to 5-29 B-39 to B-41 OO4000A508 ...(KA'S) i l

1 I

9t .IOE96Y_9E_Nyg6E@$,69WES,,669dI,QEEQQIlgNg ,E(WlQSt,$NQ PAGE 84 i IUE609QyN@ digs ANSWERS -- BRAIDWOOD 1&2 -87/12/14-DAMON, D.

ANSWER 5.07 (2.50) l

[

a. Rods will need to be withdrawn for about 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months (0.53 and then inserted for the next 35 hours4.050926e-4 days 0.00972 hours 5.787037e-5 weeks 1.33175e-5 months . CO.51 l I

b. After the power decrease, the production of xenon from fission (0.253 L and from the decay of todine (0.25) is greater than the removal by t decay of menon (0.253 and burnout by flux. CO.25) After five hours, [

the removal rate is greater than the production (0.253 and positive reactivity is being added until equilibrium at about 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months . CO.253 [

REFERENCE Braidwood R= Theory, Ch 4 ob) 1 and pp 4-14 to 4-29 i OOiOOOK533 ...(KA'S) i ANSWER 5.00 (1.50)

4. MORE NEGATIVE CO.253 because rods are inserted and push the flux to the ,

bottom of the core CO.25]

b. LESS NEGATIVE CO.253 because more reactivity is added to top of core l with delta T constant and Thot decreasing C.25)

c. LESS NEGATIVE CO.25] because Xe inserts MORE negative reactivity in the f bottom of the core than in the top of the core. CO.25) L REFERENCE j Braidwood Rx Theory, Ch 0, obj 3, 4 and pp 8-13 to 0-24 <

OO1000K506 OO1000K530 ...(KA'S) l i

ANSWER 5.09 (3.00)

!) Reactor power (0.5]. Increasing reactor power results in increased heat fluu and DNBR decreases. (0.51

2) Temperature ( 0. 5 ) . If Tsve is increased, subcooling will decrease.

Therefore the heat flum required to reach DNB will decrease and the DNBR ,

will decrease. f0.5) :

3) Pressu izer GCS) pressure (0.53. If pressurw increased, subcooling increases and DNBR increases. CO.5) i i

i 1

1 I

. Qu..IdEQJY.QE.UWGLE06.EQWEB.ELOUI.QEE6011QUt ELVIDSt.00Q PAGE 25

, IOE600010001G5

. ANSWEMS -- BRAIDWOOD 1&2 -87/12/14-DAMON, D.

REFERENCE Braidwood Heat Transfer, Ch 9, obj B and pp 9-22 to 9-20 193000K105 ...(KA'S)

ANSWER 5.10 (2.50)

a. Turbine power - stays constant at 33*/ power (0.50)

Coue to EHC being in auto)

b. Tavg (l oop 18) due to no heat sink, goes to Th = 554 F + 10/2 = 563 F (0.50)

c. Tavg (loop 1D) total reactor power has not changed; however, the power that ID S/G must produce has increased by a factor of 1/3 to compensate for 18 loop Grx = m Cp (Th - Tc) initial Delta T was 10 F, increase by 1/3 == > f i nal Delta T = 24 F final Tavo = Th - Delta T/2 = 563 - 24/2 = 551 F (0.50)

d. S/G Pressure (loop 18) saturation pressure for 563 F =1161 psia Cor 1146 psig3 (0.50) talso acceptable if assume that safeties will be lifting starting at 1065 psig)

e. S/G Pr essure (loop 1D) as with part c above, the appropriate Delta T will increase by 1/3 Osg = U A (Tavg - Tstm) initial Delta T = Tavg - Totm = 554 - 539 = 15 F final Tatm = Tavg -

Delta T/2 = 551 -

15(4/3) = 531 F final Pstm ==> saturation for 531 F = 893 psia Cor 878 psig) (0.50)

REFERENCE Braidwood Tnermodynamics, Ch 3 obj 6 and pp 3-66 to 3-76 000074A204 039000K305 ...(KA'S)

ANSWER 5.11 (1.00)

a. Falso

b. True REFERENCE Braidwood R= Theory. Ch 8, coj 1, 2 andpp 8-13 to 0-41 004000K500 ...(KA*S)

l -

5s. IVEg]y,gE,ygC(E@$,EgWEQ 66901 gEEQ911gyt [(gipsg,909 PAGE 26 1

j TH_E_R_M_O_D_Y_N_A_M__IC_S_

q ANSWERS -- BRAIDWOOD 1&2 -87/12/14-DAMON, D.

i 1 !

J ANSWER 5.12 (1.00) 3 a l

]

REFERENCE 4 Braidwood Rx Theory, Ch 0, obj 2 and pp O-13 to 0-41 i

{ OO4000K500 ...(KA'S) !

i o ANSWER 5.13 (1.00) a REFERENCE Braidwood Rw Theory. Ch 4 obj 1 and pp 4-14 to 4-29 Westinghouse Simulator Trng book, "Rx Theory and Core Physics", Fig I-5-54 l OO1000K538 ...(KA'S; ANSWER 5.14 (1.50)

Assumet boren worth = -12 pcm/ ppm (Allow full credit for Beta bar eff. = 0.007 any reasonable assumption lambda eff. = 0.00 set of these values)

The stable period is given by:

T = 26/SUR = 26/.5 = 52 See CO.53 l l

The reactivity associated with the stable periodt l r

p a beff/1+ lambda T = .007/ 1+(.00)(52) t

= 0.001357 dk/k = 135.7 PCM (0.53 l The change ln boron concentrations (

d CB = 135.7 pcm/-12 pcm/ ppm = 11.3 ppm (0.53 1

REFERENCE !

Braidwood Rm Theory, Ch 5, obj 7 and pg 5-13 i Braidwood Ra Physics, Ch 6, obj 13 and pp 6-21 to 6-24 Ch 7, obj 4 and pp 7-37 to 7-45 OO4000K507 OO4000K520 ...(KA'S)

- ks .EbeUI_SYSIEd5 QE5100t GQUIRQ(g_@yQ,10$1QQdgGIGIl@U PAGE 37 ANSWERS -- BRAIDWOOD 1&2 -87/88/14-DAMON, D. ;

ANSWER 6.01 (2.50)

1. 10% t.253 step decrease in load C.253 or 5'/. / m i n . C.253 load decrease C.253 for 2 minutes C.253

2. 4/4 C.253 turbine stop valves shut C.253 or 2/3 C.253 turbine emergency trip header pressure C.253 less than l 540 psig C.253 i REFERENCE !

Braidwood System Desertpt.on, Chapter 24 Objectives 4a. Ab, l pp. 24-13 to 24-14 041000 GOO 7 ...(KA'S)

ANSWER 6.02 (2.00)

1. Breaker racked-in and DC control power available

2. Pump control switch in standby (after-trip)

3. Low header pressure 4 Other pump on same bus in PULL-TO-LOCK (0.5 pts each) i REFERENCE Braidwood System Description, Chapter 19 Objective 7, pg. 19-12 OOOOOOK401 ...(KA'S)

ANSWER 6.03 (1.50) i (a) 81.4% (d) 50*/.

(b) 78.1% (e) 4 0. B'4 (c) 66*4 (f) 17'/.

(.25 pts each)

Note All answers will be allowed a tolerance of +/- 2 */.

REFERENCE Braidwood System Description, Chapter 22 Objective 4a. Table 22-3 0350000010 035010A301 035010K112 035010K401 ...(KA'S)

I

6s..E69NI,@y@lgd@,Q[@l@$g,QQN1696t,609,10@l6WD[Ul@Ilg@ PAGE 80 ANSWERS -- BRAIDWOOD 163 -07/12/14-DAMON, D.

ANSWER 6.04 (2.00) l

a. To insure that the RHR pumps do not overheat or vibrate (.5) when i the discharge line is shut. (.5) (

l

b. Maintain the total RHR system flow rate constant (.5) when the heat i exchanger flow control valves are adjusted. (.5) l REFERENCE Braidwood System Description, Chapter 10, Objective 41, pg. 10-14 and Objective 4h, pg. 10-20 ,

OO5000K403 OO5000K406 ...(KA'S) l l

I l

&NSWER 6.05 ( .50) j i

False.

REFERENCE !

Braidwood System Description, Chapter 12, Objective 2.h.7, pg. 12-15 l OO2OOOK109 ...(KA*S) i t

i

&NSWER 6.06 (1.50) l I

Ensures that number 1 seal differential pressure remains above 200 psi. l (1.0) This prevents the seal from "closing" and being damaged. (.5) j (Will accept discussion of NPSH requirements, backpressure and losses as long as the delta P requirement i s al so di scussed. )

REFERENCE Braidwood System Description. Chapter 13 Objective 9b, pg. 13-17 l OO3OOOK407 OO3OOOK602 ...(KA'S) l 1

i

&NSWER 6.07 (2,50) 5 minute timer is actuateo (will accept "after 5 minutes") (.5)

When timer times out, feeder breaker is sent a trip signal (.5)

All load breakers on bus are sent a trip signal (.5)

Associated DG starts on UV (.5)

DG breaker auto closes on bus (.5)

. et..ELOUI.SXSIEDS. DES 100t.609IQ96t_00D.1NSIDWDEhIGI199 PAGE 20 ANSWERS -- BRAIDWOOD tha -87/12/14-DAMON. D.

REFERENCE Braidwood System Description, Chapter 4, Objective loa, pg. 4-40 to 4-41 062000A216 064000A311 ...(KA'S)

ANSWER 6.08 (1.50)

Overspeed High differential current Emergency manual stop pushbutton

(.5 pts each)

REFERENCE Braidwood System Description, Chapter 9 Objective 5 pg. 9-54 064000K401 064000K402 ...(KA'S)

ANSWER 6.09 (2.50)

The le<el channel failing low causes orifice isolation valves to shut at 17% level (0.53. This level signal also causes charging flow to increase, beyond the capacity of the makeup system in this mode (0.53. At 5% level on both VCT channels (0.53, RWST suction valves open and VCT suction valves close (0.53 causing boration of the RCS from the RWST [0.53.

REFERENCE Braicnood System Description -

Chapter 14 Objective 21 and og. 14-43 to 14-45 Chapter 154, pg. 15a-31 004000A202 004000A206 004000A207 004000K101 004000K106 004000K123 ...(KA*S) l

- 6 1__P(@NI_SYSIEUS_ DESIGNt _CgNI@06t_@ND_lNSI6UDENI@IlgN PAGE 30 ANSWERS -- BRAIDWOOD 1&2 -87/12/14-DAMON, D.

ANSWER 6.10 (1.50)

Any 3 of the following (.5 ea)

1. Diesel generator up to rated speed.

l

2. Diesel generator up to rated voltage.

4

3. No lockout (f aul t) on Bus 242

4. Control switch for 2423 in after trip

5. Breakers 2421, 2422, 2424 open REFERENCE Braidwood System Description, Chapter 4, Objective 11c and pg. 4-101 Chapter 9, pp 9-61 to 9-62 4

062OOOK401 064000A401 064000K401 ...(KA'S)

ANSWER 6.11 (1.50)

1. RCP undervoltage (due to undervoltage on UAT) (0,5)

Setpoint - 5269 volts (.25)

2. Turbine trip above P-7 (10%) (due to low ET system pressure) (0.5)

Set p oi rit - less than 540 psig ET pressure (.25)

CNote to graders deduct .5 for any incorrect trip given]

l REFERENCE Braidwood System Description Chapter 60b, Objective 4, pp 60b-8 to 60b-20 012OOOG012 012OOOK402 045000A304 045000K411 ...(KA'S) n 0

4 i

t i

i i

i L_

6:__Eb6SI_SYSIED@_DE@lGNt_CQNI606t_QN_lN@I6ydENI@IlON_ PAGE 31 ANSWERS -- BRAfDWOOD 1&2 -87/12/14-DAMON, De ANSWER 6.12 (1.50)

Since testing of the impulse channel may give P-13 which feeds P-7 with the turbine tripped, causing a reactor trip, you must do one of the followings

(.75) (Either answer accepted for .75)

a. Restrict testing of the impul se channel to less than 10%

b. Insert shutdown banks and open trip breakers prior to testing REFERENCE Braidwood System Description, Chapter 60b, Objective 4c and pg. 606-22 012OOOK401 012OOOK402 012OOOK610 ...(KA'S)

ANSWER 6.13 (1.50)

1. Turbine first stage pressure less than 15% (or C-5) (.75)

2. Control bank D greator than 223 steps (or C-11) (.75)

REFERENCE Braidwood System Descr;. .on, Chapter 28, Objective 14, and pp 28-72 to 28-73 OO1000K407 ...(KA'S)

ANSWER 6.14 (2.00)

The concern is with making up logic for the OT delta T trip.t.75) Since tripping the bistables associated with the pressure channel will generate 1 the coincidence necessary to cause a reactor trip, ( . 75) the operator should l not trip bistables associated with OT del ta T. ( . 5) i REFERENCE Braidwood System Description, Ch 12, pp 12-32 to 12-33 Ch 60b, figures 60b-5 and 60b-8 BwCA-INST-2, attachment 8, pg 13 caution 012OOOK401 012OOOK405 012OOOK601 ...(KA'S) l 1

[

- ~ Zz__EBgCEgyBES_;_NgBM862,@BNgBd@63_[d[B@[NQy,@NQ PAGE 32 689196991c86_C9 BIB 96 ANSWERS -- BRAIDWOOD 1&2 -87/12/14-DAMON, D. I i

ANSWER 7.01 (3.00)

a. No [

b. Yes

c. Yes

d. No (

e. Yes i

f. No

g. No

h. No i

(.375 pts each) {

REFERENCE BwOA-PRI-2, Entry Conditions i OOOO24A205 OOOO24K301 OOOO24K302 ...(KA'S) i

l ANSWER 7.02 (3.00) !

Operator #1 Rejected C.253 since he has no history on file and will exesed 1.25 REM /QTR whole body exposure C.503 Operator #2 Accepted C.253 since she will not exceed 500 mrem whole body ;

exposure during the term of her pregnancy C.253 or the weekly / quarterly l limits C.253 Operator #3 Accepted C.253 since he will not exceed 300 mrem weekly admin !

limit C.253 or the 1.25 R/Qtr limit. C.253 I Operator #4 Accepted C.253 since she will not exceed 300 meem weekly admin. t l limit C.253 and will not exceed 1.25 REM /QTR whole body C.253 l (5Cn-183 criteria does not apply since the operator will not exceed the l allowable quarterly limit of 1.25 REM /QTR whole body.)

REFERENCE BwRP 1000-A1, pp. 24 to 25 l 10 CFR 20.101 l USNRC Regulatory Guide 8.13 !

194001K103 194001K104 ...(KA'S) !

j 1 I i

I J

? l l l

e

. Zi__E69GEQUBgS_:_NQBd@(t_8BNQBd@Lt_EdgBQgNQy_9NQ PAGE 33 B99196991986_GQUIBQL

, ANSWERS -- BRAIDWOOD 1&2 -87/12/14-DAMON, D.

ANSWER 7.03 (1.50)

1. Entered based on operator judgement when: (0.5) -

22. 51 is actuated or required (0.5) ;

, and !

3. BwEP-O has been in.plemented and a transition to another ;

BwEP has been made (0.5) l REFERENCE BwEP ES-0.0, pg. 1 ,

OOOOO7G011 ...(KA'S) ;

ANSWER 7.04 (1.50)

a. False

b. False i c. False REFERENCE i ERG Executive Volume, Users Guide, pp 5, 20-25 BwCA-0.0 Entry Conditions i OOOOO7G011 OOOOO7G012 OOOOS6G011 000056G012 ...(kA'S)

ANSWER 7.05 (1.00)

Perform the next step or substep in the left hand column. (1.0) l REFERENCE i BwAP 340-1 pg 5 l ERG Executive Volume, Users Guide, pg. 5 000009G012 0000110012 ...(KA'S) 4

[

i l

l t

i

' _ . - - _ . -.. - ,-.. _. _..._ , __. - .. - _ . _ _ _ ,m._ . . - . _ _ , ,__,,,,__._.__,3._,... . . _ _ _ _ _

-- Zt__P8QCEDQ6ES_ _NQBd@bt_6BNQBd@(t_EDEBGENCy_6ND PAGE 34

. 68Dlg69QlC6(_CQNIQQ6 ANSWERS -- BRAIDWOOD 1&2 -87/12/14-DAMON, D.

ANSWER 7.06 (1.50)

1. Containment pressure less than 5 psig and (.75)

2. Containment radiation l evel remained less than IES R/hr. (.75)

Note: Will accept for Item 2: Containment rad level less than 1E5 R/hr.

and integrated dose less than 1E6 R.

Will also accept a stated assumption that containment rad levels L

never exceeded 1ES R/hr.

REFERENCE BwEP-0, pg. 3 note ,

ERG Executive Volume, Generic Instrumentation, pg. 21 !

OOOO30G011 000038G012 103000G015 ...(KA'S) .

ANSWER 7.07 (1.00) ,

No. CO.53 do not meet criteria f or tripping RCP's of no RCS cooldown (

in progress CO.53. (

REFERENCE ,

BwEP-F.1, RCP trip criteria l 003000G010 003000G015 ...(KA'S) (

ANSWER 7.08 (1.50) l Any 2 of the following (.75 pts each)

1. During performance of BwEP-O pri or to step 33 (will accept "prior to :

the step requiring monitoring of status trees") !

2. During performance of BwCA-0.0 (will accept "during loss of all AC")

3. During performance of BwEP ES-1.3 steps 1-5 (will accept "while changing RHR lineups")

4. During BwCA O.1 steps 1-9

5. During BwCA O.2 steps 1-7 I

1

Zs__E89GEDW6EE_:_NQ80@(t_@BNQ80@6t_[dgBQgNQy_@ND PAGE 35 ;

BSD196991G06_G9 NIB 96 1

, ANSWERS -- BRAIDWOOD 1&2 -87/12/1--DAMON, D.

I REFERENCE BwEP ES-1.3, pg. 2 ERG Background E-O step 27 OOOOO7G012 OOOO55G012 ...(KA'S)

ANSWER 7.09 (4.00)

a. Site Emergency (9) e. None (22)

b. Alert (14) f. None or Unusual Event (25, 31)

c. Unusual Event (17) g. Site Emergency (1) ;

d. Alert (16) h. Unusual Event (7)

(numbers refer to the EAL classification used by the grader)

(0.5 pts each)

REFERENCE Bw2P 2OO-1A1, Items 9, 14, 17, 16, 22, 31, 1, 7 194001A116 ...(KA'S) i ANSWER 7.10 (2.25)

a. 1.03 C.25] C1.25 tota 13 (Credit .125 for each correct normalized detector current) ,

i

b. Calculate OPTR at least once per hour (.25)

Reduce power to less than 50% (.25) ,

Reduce PR Hi flux trip setpoint to 55% (.25) l Identify and correct cause of tilt (.25)

REFERENCE

19wCS 2.4.1.9-1

) TS 3.2.4.C 015000A104 015000 GOO 7 015000GOOO ...(KA'S) ;

ANSWER 7.11 ( .75)

!I Leave containment immediately C.253 and report to your supervisor C.253 and then report to Rad / Chem C.253.

]l !

l REFERENCE i BwRP 1000-A1, pg. 33 l 194001K104 ...(KA'S) i I

4 l

I

- 'Z:__BBgCggg6ES_ _Ng6d@(g,@BNg@d@6t_[dg@ggNCY_@Ng PAGE 36 i . 889196991C66_CgNI6g6 ANSWERS -- BRAIDWOOD 1&2 -87/12/14-DAMON, D.

ANSWER 7.12 (2.50)

a. Type 1 Type 2 (.5 each answer) i

1. Less than 50 mrem / day Greater than 50 mrem / day 4

2. Max. of 1 year Length of job 1

b. True REFERENCE

_ BwRP 1000-A1, pp. 11-17

?

194001K104 ...(KA'S)

ANSWER 7.13 (1.00)

1. Reinsert all contr ol banks (.5) 4 a

l 2. Recalculats ECC (.5)

J 4

REFERENCE BwGP 100-2, pg. 9 OO1010A207 ...(KA'S) l l

f i

i

! l l i 1

J l

1 j

i I 1

1 1

(-_ j

i Et__eDd1Ni@l@@Ilyg_E8Qg[QQB[@t_QQNQlIlQN@g_@NQ_(ldlI@IlQN@ PAGE 37 ANSWERS -- BRAIDWOOD 1h2 -87/12/14-DAMON, D.

i

)

ANSWER 8.01 (1.00) i

a. False l

b. False (0.5 pts each)

REFERENCE BAP 330-6, pp 2 to 3 194001K102 ...(KA'S) i ANSWER 8.02 (1.50)

"Closed bullet" requires all steps to be completed in any order t.753.

"Open bullet" requires only the steps that apply to be completed in any L order C.753.

REFERENCE BwAP 340-1, pg. 5 OOOOO7G012 ...(KA'S)

ANSWER 8.03 (5.00)

a. No f. No

b. No g. No ,

c. Yes h. Yes ,

d. No 1. Yes :

e. Yes J. No (.5 ea) j l

REFERENCE ;

Braidwood Technical Specifications 3.6.1.5, 3.5.4, 4.7.1.5, 3.9.9, 3.6.1.3, !

3.8.1.1, 3.1.1.1, 3.1.2.4, 3.1.2.6 OO4000G011 OO5000G011 022000G011 029000G011 039000G011 062OOOG011 103OOOG011 ...(KA'S)

ANSWER 9.04 (1.00)

1. False

2. False REFERENCE BwAP 300-1, pp. 12, 10 194001K105 194001K116 ...(KA*S)

8t__epd1Ni@I68IlyE_P6QCEQQBES t_CQNQlligNS _@NQ,61dlI@IlgN@

g PAGE 38 ANSWERS -- BRAIDWOOD 1&2 -87/12/14-DAMON, D.

ANSWER 8.05 (2.00)

Any 2 of the following (1.0 ea)

1. Maintain plant operation inside the FSAR described design envelope.

2. Make log entries describing the situation and resolution.

3. Return system to the as-found position if procedure to be terminated.

4. Place system in stable condition.

REFERENCE BwAP 340-1, pg. 2 194001A102 ...(KA'S)

ANSWER 8.06 (2.50)

Monitored in order (1.5) !

Suberiticality, core cooling, heat sink, integrity, containment, inventory

(.25 pts for each in correct order, - .125 if correct status tree in wrong order)

Color priority in order (1.0) red, orange, yellow, green

(.25 for each in correct order, - .125 if correct c ol or and out of order)

REFERENCE ,

BwAP 340-1, pg. 7 j OOOO29G010 000029G011 194001A102 ...(KA'S) '

l

r 9e _890}NJSIE@IJ2E_ESQQEQQBES _QQNQJIJQNS 3 _@NQ_QJDJI@l]QNp i PAGE 39 ANSWERS -- BRAIDWOOD 1&2 -87/12/14-DAMON, D.

e e

ANSWER B.07 (2.25)

1. No current procedure describes the proposed action.

2. There is no change in intent for any established procedure.

3. The proposed procedure does not involve an unreviewed safety question.

(.75 pts each)

REFERENCE SWAP 1300-3, pg. 1 194001A101 194001A102 ...(KA'S)

ANSWER 8.08 (1.00) 14 days f rom the implementation date.

REFERENCE BwAP 1300-3 194001A101 194001A102 ...(KA'S)

ANSWER B.09 (1.75)

Limitations ensure that the resulting 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months dose at the site boundary C.5] will not exceed a small fraction of 10 CFR 100 guidelines C.53 following a SGTR C.53 in conjunction with a 1 gpm steady-state primary to secondary leak C.25].

REFERENCE Braidwood TS Bases 3/4.4.8 002000G006 OO4000 GOO 6 073OOOGOO6 ...(KA'S)

I ANSWER 8.10 (1.50)

OPERABLE means that the item being addressed is capable of performing its specified function (s) C.53 and all necessary attendant auxiliary equipment and instrumentation that is required for this item to perform its function C.52 are also capable of performing their related support functions C.53.

l

1

- 9e.__0901Ni@l6@llyE_E69CEQyBE@t_CQNpillgN@t_@hp_61DlI@IlgN@ PAGE 40 l

ANSWERS -- BRAIDWOOD 1&2 -87/12/14-DAMON, D.

)

REFERENCE Braidwood Tech Spec 1.19 061000 GOO 5 061000 GOO 6 061000G011 ...(KA'S)

ANSWER 8.11 (3.00) l Controlled leakage is the seal water flow supplied to the RCP seals.

(.75)

Pressure boundary leakage is through a nonisolable fault in an RCS component (.75)

Identified is leakage (except controlled) into closed systems [.25] or into containment atmosphere from specifically known sources (not pressure boundary) C.25] or into a steam generator t.253.

Unidentified is all leakage which is not identified or controlled.

(.75)

REFERENCE Braidwood Tech Spec 1.8, 1.15, 1.22, 1.37 002000A301 OO2OOOGOO5 002000G015 OO2OOOK405 ...(KA'S)

ANSWER 8.12 (2.50) 1

a. 1. Combination of thermal power t.253, pressurizer pressure t.25], I and highest operating loop Tave t.253 shall not exceed limit i 3

for four loop operation [.253.

I

2. RCS pressure t.253 shall not exceed 2735 psig. (.25)

)

b. Be in hot standby C.53 within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months t.53.

REFERENCE I Braidwood Tech Spec 2.1 003000G005 010000G005 015000 GOO 5 016000 GOO 5 ...(KA'S) l

e ,-m m.

k,A /4 (m ev gi.i /s y< P4 % cm;. *

,., 7 l';tf-R Q 'd w 'i .a s u: %,4 L1 . '.b

+ U. S. NUCLEAR REGULATORY COMMISSION i REACTOR OPERATOR LICENSE EXAMINATION FACILITY: _BB6IDWOOD 1&2 REACTOR TYPE: _EWB-WEG4 -

DATE ADMINISTERED: _eZZ12/11 __

EXAMINER: _LEUU6BIZt_J.

CANDIDATE: _______ - _____ ______

186IBUCIlDNS In- 96HDIDAIE1 Use separate papar for the answers. Write answers on one side only.

Staple question sheet on top of the answer sheets. Foints for each question are indicated in parentheses after the question. The passing crade 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

__YALUE_ _ICI6L SCOBE___ _YaLUE__ ___________ CAIEGOBX __ _ _

25.00 25.00 _ _ _ _ _ _ _ _ _ _ _ ________ 1. FRINCIPLES OF NUCLEAR FOWER PLANT OPERATION, THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW 25.00 25.00 _______ 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS

_2h tGQ__ _25.J1Q ___________ ___ ___3.

INSTRUMENTS AND CONTROLS

_2h&0G__ _2L.on _ 4. FROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL 100.00 % Totals Final Grade All work done on this examination is my own. I have neither given nor received aid.

Candidate's Signature o ,.5 ,. .u y , y n, v, e (k

n .hk . j f /ym.,, g-.. ,\.

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\..,4 b# L L L.? ';'

l,,y.d hJ s k~. {. N.

$ i NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS h

,During the administration of this examination tae following rules apply:

2. Cheating on the examination means an automat.ic 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 2nly to facilitate legible reproductions.

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

5. Fil) 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 sach section of the answer sheet.

8. Consecutively number each answer sheet, write "End of Category __" as appropriate, start each category on a Dfw page, write QDly QD 202 Eldt 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 Ibrge 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 1119r319r2

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 GUESTION AND DO NOT LEAVE ANY ANGWER BLANK.

16. If parts of the examination are not clear as to intent, ask questions of the exam 1 Der enly. ;

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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 completing the examination. This must be done after the examination hat ,

been completed. '

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13. When you complete your examination, you shall:

a. Assemble your examination as follows:

(1) Exam questions on top.

(2) Exam aids - 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 e.nswer 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.

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EQUATION SHEET c f = ma v = s/t Cycle efficiency = (Net work out)/(Energy in) 2 w = og s = V,t + 1/2 at 2

E = sc

KE = 1/2 av a=(Vf - V,)/t A = AM A = A,e **

PE = agn Yf = Y, + a t w = e/t A = an2/t.1/2 = 0.693/t1/2 w . , ap.

A= n0 2 t

1/2*N

S U M O

, [(g/2I

II b)3 1

t.E = 931 ta -

m = Y,yAo ,

-T.x Q = aCpat Q = UA A T I=Ien Pwr = Wgah I = 1, 10-* N '

TVL = 1.3/u P = P,10 sur(t) HYL = -0.693/u P = Po et /T SUR = 26.06/T SCR = S/(1 - K,ff)

CR, = S/(1 - K,ffx)

SUR = 26s/t= + (s - s)T CRj (1 - K,ffj) = CR2 II ~ Ieff2)

T = (t*/c) + ((s - oV Io] M = 1/(1 - K,ff) = CR /CR j ,

T = t/(o - s) M = (1 - K ,ffg)/(1 - K ,ff))

T = (s - o)/(Io) SDM = (d1 - K,ff)/K,ff ,

o = (K ,ff-1)/K ,ff = aK,ff/K,ff tw = 10 seconds i I = 0.1 seconds"I !

o = ((t*/(T X,ff)] + [a,ff /(1 + IT)]-

Idl1*Id 2 ,2 gd 2

P = (t4V)/(3 x 1010) Idjj 22 2 I = eN R/hr=(0.5CE)/d(meters)

R/hr = 6 CE/d2 (feet)

Water Parameters Miscellaneous Conversions 1

. 1 1 gal. = 8.345 lbm. 1 curie = 3.7 x 1010ep, j 1 ga: . = 3.78 liters 1 kg = 2.21 lbm 1 ft* = 7.48 gal. I hp = 2.54 x 103 8tu/hr Density = 62.4 1 /ft3 1 nw = 3.41 x 106 Stu/hr Oensity = 1 ge/c.. lin = 2.54 cm Heat of vaoorization = 970 Stu/lem 'F = 9/5'C + 32 Hest of fusion = 144 Btu /lem 'C = 5/9 ('F-32) 1 Atm = 14.7 psi = 29.9 in. Hg. 1 BTU = 778 ft-lbf 1 ft. H 2O = 0.4335 lef/in.

' 1. PBlECIPhES OF NUCLE 68_EQWEB_PL&BI_QEEB&TlQtjt PAGE 2 IHEBM9DYU801916._HE AI_IB&NS EEB_AUD_EL L11D_EkRW QUESTION 1.01 (2.00)

Indicate whether EACH of the following parameters would INCREASE, DECREASE' or remain UNCHANGED for the conditions listed in a. through h.

on the t.ible below: (Consider each condition separately.)

Conc ition Local CHF DNBR RCS Average Temperature Decreases a b RCS Pressure Decreases e d RCS Flow Decreases e f Reactor Power Level Decreases g h QUESTION 1.02 (1,00)

During a reactor startup, WHAT are TWO reasons that 10E-8 amps is the power level at which critical data is taken?

QUESTION 1.03 (2.00)

The thermal rated power of the reactor is 3411 Mw, Assume C-p is 1.3 '

BTU /lbm-F,

a. WHAT flow rate (1bm/hr) is required to keep the temperature rise across the reactor vessel less than 60 degrees F7 (Show all work)

(.75)

b. Using the flow rate in part a., WHAT is the enthalpy rise (BTU /lbm) acrose the reactor? (Show all work) (.75)

c. HOW does a decrease in mass flow rate affect the enthalpy rise?

(0.5) i I

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

' l&_JE81601ELES_QE_EUCLE8B_EQEEB_EL6EI_Q2EBAIlOHi PAGE 3

, IBEBUQDXE6d1C6&_BE6I_IB86 SEER _6UD_ELUID_ELQH QUESTION 1.04 (1.50)

The plant is operating at 50% power with control rods in manual. IF power range channel N-44 LOWER detector fails HIGH, how would it affect the ,

following indications? (Limit your answer to INCREASE, DECREASE, MORE NEGATIVE, LESS NEGATIVE, or NO CHANGE.)

a. Lower Quadrant Power Tilt Ratio !

b. Delta Flux indication (Channel 4)

c. OP delta T setpoint (Channel 4)

QUESTION 1.05 (1.50)

Indicate whether EACH of the following situations result in SUBCOOLED, SATURATED, or SUPERHEATED fluid conditions. (Assume RCS Tave at 588 degrees F and RCS pressure at 2235 psig, and reactor power at 100% )

a. Pressuriser PORY relieving to the PRT

b. S/G Safety Valve relieving to the atmosphere.

c. Steam from a Moisture Separator Reheater entering a low pressure turbine,

d. Condensate exiting the condenser hotwell.

QUESTION 1.06 (1.50)

Indicate whether EACH of the following will cause shutdown margin to INCREASE, DECREASE, or REMAIN THE SAME. (Consider each independently.)

1. Control rods withdrawn 10 steps with no change in turbine power or boron concentration.

2. Turbine power decreased 10 percent with no change in boron concentration or rod position.

3. Normal power increase from 50 to 60 percent with no change in boron l concentration and rods in automatic.

4. Boron concentration is increased 10 ppm with rods in automatic.

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

'1 'EBIUClELES OF NUGLE6B_EQHER_ELaDI_QEEBAIlOH1 PAGE 4 IEEBdQDYBAMIG_SmHEAT IB8HSEEB_bHD_ELMID_ELQH

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QUESTION 1.07 (1.50) !

How will EACH of the following affect a calorimetric power calculation?

Limit your answer to CALCULATED LOWER THAN ACTUAL, CALCULATED HIGHER THAN ACTUAL, or CALCULATED SAME AS ACTUAL. (Consider each case separately.)

a. Measured feedwater temperature is 10 degrees higher than actual feedwater temperature.

b. Measured steam generator pressure is 30 psig lower than actual steam generator pressure.

c. Measured feedwater flow is 1E5 lbm/hr higher than actual feedwater flow.

QUESTION 1.08 (1.00)

Which ONE of the following statements concerning TOTAL POWER DEFECT is correct?

a. The Total Power Defect is the difference between the measured power coefficient and the predicted power coefficient,

b. The Total Power Defect increases the rod worth requirements necessary to maintain the desired shutdown margin following a reactor trip.

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c. The Total Power Dc! tt is more negative at beginning of core life because of the higher boron concentration.

d. The Total Power Defect necessitates the use of a ramped Tavg program to maintain an adequate reactor coolant system subcooling margin. ;

l QUESTION 1.09 (1.50) l l

Assuming a Xenon-free reactor startup, while critical with power leveled off at 10-8 amps for critical data, Tave : 546 degrees F and RCS pressure 2235 psig. rod D-4 (control bank D) drops to the bottom. Describe reactor power, RCS temperature, and RCS pressure transients caused by the dropped rod. (End discussion at stable plant conditions.)

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

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A. 'EBIUglELES OF UUQLEAB_E9EEB_PLABI_QEEB4TIOU1 PAGE 5 ;

IHEBM22YEbd19L _BEAI_IB3USEEB AND_ELUlD_EL9E l QUESTION 1.10 (2.00)

After operation at 100% power for several weeks near the end of cycle, it is decided to reduce power to 75% using rods only.

a. After reaching 75% power, what rod motion would be required to maintain the plant at 75% power, with Tavg and Tref matched, over the next 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months assuming no change in boron concentrations? Include any applicable time periods. (0.5)

b. Explain how the Xenon production and removal mechanisms cause a l reactivity transient after a power reduction from 75% to 50% power. :

Include time periods for the various reactivity effects up to equilibrium. (1.5)

QUESTION 1.11 (1.50)

Mould the Axial Flux Difference become MORE NEGATIVE or LESS NEGATIVE for ,

the following conditions? (STATE THE REASONING FOR YOUR CHOICE) (0.5 '

each)

a. OT Delta-T runback from 100% to 50% power with rods in automatic,

b. Feed flow increases to the steam generators with rods in manual. '

c. Xenon is building into the bottom of the core more than in the top of the core.

QUESTION 1.12 (1.00)

When performing a reactor S/U to full power that commenced five hours after a trip from full power equilibrium conditions, a 0.5% per min ramp was used. How would the resulting xenon transient vary if instead a 2%

per min ramp was used? (Choose one)

a. The xenon dip for the 2% per min ramp would occur socner and the magnitude of the dip would be smaller.

b. The xenon dip for the 2% per min ramp would occur later and the magnitude of the dip would be smaller.

c. The xenon dip for the 2% per min ramp would occur sooner and the magnitude of the dip would be larger.

d. The xenon dip for the 2% per min ramp would occur later and the magnitude of the dip would be 1.arger.

(***** CATEGORY 01 CONTINUED ON NEXT PAGE ***+4)

'4. 'EBIECIELEE_QE_EMQLE6B P0"EB_EL6EI_QEEB6ILOU1 PAGE 6

- IBEEMODX86MICS, HE6I_IB6ESEEB_6ND_FL91D FLOM QUESTION 1.13 (1.50)

A cooling water pump is operating at 1500 rpm. Its capacity is 250 gpm at a discharge pressure of 15 psig which requires 40 KW of 1)ower.

Determine the pump capacity, speed, and power requirement if the pump discharge pressure drops to 10.0 psig due to reduced speed.

QUESTION 1.14 (1.00)

What effect will EACH of the following have on a 1/M plot? Limit your answer to UNDER-PREDICT criticality (conservative), OVER-PREDICT criticality (non-conservative), or NO CHANGE. (Assume you go cri'". cal in source range. Consider each case separately.)

a. Time interval between rod pulls on a startup is changed from 1 minute to 10 seconds.

b. Intermediate range nuclear instruments are over-compensated.

c. Source strength immediately prior to the startup in changed from 4 cps to 10 cps.

QUESTION 1.15 (2.50)

The plant is operating at 33% power when the IB S/G Main Steam Isolation Valve fails shut. Using the below initial conditions, calculate the new steady state values for the listed parameters.

I Assume no operator action, rod control system in manual, all other control cystems in automatic, no reactor trip and no SI actuation. l State all 1 assumptions and show all work.

Initial Conditions: Tavg = 554 F Tstm = 539 F Core Delta T = 18 F

a. Turbine power

b. Tavg (loop 1B)

c. Tavg (loop 1D) i

d. S/G pressure (loop 1B) i

e. S/G pressure (loop 1D)

)

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

, 1&_2EBlHGlELES_QE_EHCLE6R POMEB_EL&MI_QEEBAllOEt PAGE 7 IDEBdQDYEAUIGS. HE8I_IBAESEER AED FLULD_ELQE

. r QUESTION 1.16 (2.00)

A questionable ECC calculation shows that criticality should be achieved when 3000 pcm has been added to the core. A boron dilution of 150 ppm (1500 pcm) is planned, followed by control rod withdrawal to criticality.

The initial count rate is 50 cps.

a. WHAT is the expected count rate after the 150 ppm boron dilution? ,

(0.75)

b. Following the first 75 ppm dilution, the source ranges indicate 80 cps. WHAT amount of reactivity in pcm should the original ECCS calculation have derived as sufficient to reach criticality? (Show all work) (1.25) i l

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

1

2. EL6BI_DESIGB_lEGLUD1HG_E6EEI1_6ED_EUESQENC1_EXEIEUS PAGE 8 QUESTION 2.01 (1.50)

Answer the following questions concerning the 120 Volt Instrument Bus:

a. WHAT design feature allows the Instrument Bus to automatically remain energized if the 480 volt ESF Bus Power supply to the Inverter is lost? (Include a brief explanation of how this design feature functions.) (1.0)

b. WHAT is the BACKUP source of power to the Instrument Bus if the Inverter is out of service? (0.5)

QUESTION 2.02 (1.00)

When the Pressuriser PORV's are in the ARM Low Temp mode, what signals are used as inputs to the PORV's to provide for overpressure protection?

(1.0)

QUESTION 2.03 (1.50)

Piping connections between the RCS and Auxiliary Systems are normally made above the horizontal centerline of the RCS. An exception to this is the RHR pump suction connection with the RCS. WHERE (in relation to the RCS piping horizontal centerline) is the RHR pump suction connection, and WHY is it designed this way?

QUESTION 2.04 (2.00)

If EMERGENCY BORATION of the RCS is required, the preferred source and flowpath is from the Boric Acid Storage Tank through the Boric Acid Transfer Pump and the Emergency Boration Valve (8104). If the Boric Acid Transfer Pumps are not available, WHAT source and flowpath would be utilized to Emergency Borate the RCS7 (Include in your answer, what the flow rate would be, and the reason for the flowrate.)

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

2&__tL6NT DEElGU_1EGhMDING_E6EEIY_6MB_EUESGEUGY_SYEIEdS PAGE 9 QUESTION 2.05 (1.50)

Answer the following questions concerning the 250 VDC Power System:

a. WHAT are FOUR conditions that will cause the "250 VDC BATT CHGR 123 TROUBLE" annunciator to alarm? (Annunciator test is not considered a valid condition.) (1.0)

b. WHAT is the 1/2 hour minimum time requirement that the 250 VDC i battery must supply power to the Turbine #1 D.C. Emergency Bearing 011 Pump based on? (0.5) i QUESTION 2.06 (1.00)

UHAT are TWO reasons WHY you are limited to approximately 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months time limit when using the Reactor Makeup System in the ALTERNATE DILUTE mode?

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QUESTION 2.07 (2.00)

State how EACH of the following valves will fail if Instrument Air is lost. (Limit your answer to OPEN, CLOSED, or THROTTLED)

1. TCV 381B (Boron Thermal Regeneration System Temperature Control Valve)

2. CV-8389A (Letdown Inlet to A Regenerative Heat Exchanger)

3. PVC-131 (Letdown Pressure Control Valve)

4. FCV-121 (Centrifugal Charging Flow Control Valve) i

! OUESTION 2.08 (2.50) ,

Answer the following questions concerning the Residual Heat Removal System:

a. WHAT INTERLOCN conditions must be tisfied in order to OPEN 8804B '

(Charging pump suction crossover isc.1ation valve from RHR)? (1.5) '

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b. WHAT are the reasons for the interlocks in part a? (1,0) l

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

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2. PL8NT DESIGU_XWCLUDIEG_6bEEIX_68D_EUESQE8QY SYSIEUS PAGE 10 t

QUESTION 2.09 (2.00)

Answer the following questions concerning the Component Cooling Water {

System:

[

a. WHAT are TWO signals / conditions that will AUTOMATICALLY start the standby CCW pump? (Assume CCW pump 1A is running and CCW pump 1B is in standby with power available.) (1.0)

b. CCW pump "O" is being powered from 4.16 KV ESF Bus 141, and in i

STANDBY, CCW Pump 1A is RUNNING, and CCW pump 1B is in ~

PULL-TO-LOCK. 1 If CCW Pump 1A's shaft locks up. (tripping the motor breaker) will CCW pump "0" automatically start? (Explain WHY or WHY NOT) l QUESTION 2.10 (2.00) i Answer the following questions concerning the Emergency Diesel Generator:

i a. WHAT is the 500 gallon capacity of the Diesel Oil Day Tank based on?

(.75)

b. WHAT is the function of the Emergency Mode Speed / Voltage Control Switch on the MCB, when it is in the MANUAL EMERGENCY MODE position?

(1.25)

QUESTION 2.11 (2.50)

Answer the following questions concerning the Auxiliary Feedwater System:

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a. If 1B AFW pump is running during a loss of all AC power, WHAT ;

! indication do you have in the Control Roon, if any, of how much AFW flow you have to S/G's. (Assume AFW flow meters to the S/G's are inoperable. Include any applicable setpoints.) (1.0)

b. HOW will the AFW Pump 1B starting circuit respond if AFW Pump 1B received an AUTOMATIC start signal and the engino does not reach 350 rpm within the 5 seconds erank time? (Include any applicable ;

setpoints. Assume engine will not start.) (1.5) !

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

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1 2 tL6HI_ DESIGN IEELUDING_SAEEIY_6HD-= EMERGENCY.SYSIEds PAGE 11 QUESTION 2.12 (1.75)

WHAT are SEVEN RCP system parameters and/or indications that can be monitored on the Main Control Board? (Do not include annunciators.

Redundant instrumontation will be credited as a single response.)

QUESTION 2.13 ( .75)

WHAT are THREE conditions / signals that will generate a Containment Ventilation Isolation Signal? (Coincidence and setpoints not required)

QUESTION 2.14 (2.00) ,

WHAT are TWO safety related reasons for the generator trip time delay on a turbine trip? (Give explanation of each)

GUESTION 2.15 (1.00)

If a STATION BLACKOUT occurs, WHAT are FIVE loads that would be startad by the Engineered Safety Features SAFE SHUTDOWN sequencer, once the Emergency D/G's cutput breaker is closed? (Assume no Safety Injection Signal present. Redundant equipment will be credited as a single response.)

(***** END OF CATEGORY 02 *****)

3. INSTRUMEHIE_6ND GOUIROLS PAGE 12 i

QUESTION 3.01 (1.00)

Which ONE of the following provides a signal to the Rod Insertion Limit computers?

a. Slave Cyclers

b. Bank Overlap Unit

c. P-A Converter

d. Master Cycler r

QUESTION 3,02 (1.50)

Will the indicated PRZR level INCRFASE, DECREASE. or REMAIN THE SAME for the following conditions? Give a brief explanation for each answer.

(Consider each case separately) !

a. Steam break inside containment I

b. Bellows rupture

c. Reference leg leak / break Q'1ESTION 3.03 (1.50)

Braidwood Unit 2 has been operating at 92% power for sixty-three days when the Load Dispatcher requeste a reduction in power to 70%. After starting the power reduction, a Tave/ Tref mismatch is generated that demands rod movement (Rod Control is in Automatic). Describe what happens to Rod HS (Control Bank D) if the moveable gripper coil CANNOT be energised in the rod movement sequence. Include any final results.

1 QUESTION 3.04 (1.50) ;

Prior to a plant startup, the START-UP RESET SWITCH is operated. What SIX resetc are accomplished by this switch?

QUESTION 3.06 (1.50)

What TWO CONTROL Systems receive an input signal from Auctioneered 1

nuclear power? (Describe how and why these inputs are used)

(***** CATEG0hY 03 CONTINUED ON NEXT PAGE *****) ;

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3. $USIRudEHIE_6HD_C08IBQLE PAGt- 13 QUESTION 3.06 (1.50)

If PT-507 (Main Steam Header) fails LOW, HOW and WHY would this effect Main Feed Pump speed? (Assume plant at 100% power)

QUESTION 3.07 (1.50)

Braidwood Unit 1 is at 96% power at steady-state when the reactor trips.

Concurrently, Thot fails high for loop 3. Describe how the Steam Dump System will operate under these conditions assuming all other equipment functions normally with no operator action concerning the failed Thot instrument.

QUESTION 3.08 (2.00)

Braidwood Unit 1 is at 86% power at steady-state when PRZR Pressure Channel 455 (controlling) fails HIGH. Assuming no operator action, describe the sequence of events that follow.

QUESTION 3.09 (1.50)

a. How is the P-4 (Reactor Trip) permissive generated? (0.5)

b. What FOUR functions are provided by P-47 (1.0)

QUESTION 3.10 (1.50)

The plant is operating at 100% steady state power with containment pressure channel IV (PB 934A) failed high. A technician troubleshooting the trip bistables inadvertently de-energizes the instrument power for containment pressure channel II. Will a Containment Spray Actuation occur? Explain why or why not.

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

g, .IssIBudEGIE_AUD CQHIBQLQ PAGE 14 QUESTION 3.11 (1.50)

Answer the following questions concerning the Subcooling Margin Monitor with respect to the following given plant conditions: RCS pressure is 1200 peig, RCS Tavg 350 degrees F, and the plant is currently being cooled down for a refueling outage, i a. List THREE inputs to the Subcooling Marcin Monitor. (0.75)

b. What THREE displays are available on the Subcooling Margin Monitor !

I primary displayY (0.75) r 2

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. QUESTION 3.12 (1.50) i The plant is operating at full power when a General Warning occure on one [

train of the Solid State Protection System (SSPS).

a. List FOUR possible causes of the General Warning on SSPS. (1.0)

b. How is plant operation affected if a General Warning occurs on the other train of SSPS? (0,5)

QUESTION 3.13 (1.00)

Answer the following questions TRUE or FALSE concerning the Remote Shutdown Panel (SSP),

a. To operate a pump from its switchgear, the LOCAL / REMOTE switch must

! be in REMOTE.

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b. If a pump on the ESP ic in Pull-to-Lock on the MCB, then it may NOT

! be operated from the RSP even if the LOCAL / REMOTE switch is in LOCAL.

\

{ QUESTION 3.14 (2.00)

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a. List FOUR conditions thst actuate a STEAMLINE ISOLATION. Include I setpoints and coincidences where applicable. (1.0) l

! b. What does steamline isolation provent? (1.0)

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l ' 22__iUSIBUdEHIS._6UQ_COMIEQLS PAGE 15

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1 QUESTION 3.15 (1.75) i Answer the following concerning radiation monitors,

a. What THREE monitors are used to indicate a S/G tube rupture? (0.75)

b. During refueling operations, the Fuel Handling Building Crane area monitor (ORE-AR039) alarms. What automatic action occurs? (0.5)

J c. Welding causes the Component Cooling Heat Exchanger 0 Water Outlet Monitor (ORE-PR009) to alarm. How is the CCW system affected? (0.5) 1 l l l

QUESTION 3.16 (2.25) '

a. List FOUR conditions that will automatically start a motor driven Auxiliary Feedwater pump (AFW). (1,0) (Include coincidences, i

where applicable) i

b. To manually start a motor driven AFW pump, what one other condition ;

must be present? (0.26)

c. What FOUR conditions will trip the motor driven AFW pump? (* 0) i i i t

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(***** END OF CATEGORY 03 *****)

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4. =fBQREDMBES - NOBMALi_6BH9BMAL&_EMEBRE801_AND PAGE 16 BAD 10LQ0198L 00NTB9L l

QUESTION 4.01 (3.00) '

I Indicate whether or not EACH of the following parameters / situations while l'

in Mode 1 will require corrective action as dictated by TECHNICAL I SPECIFICATIONS. (Consider each case independently. Assume all other I

]

operability requirements are met. Limit answer to YES or NO.) l

a. RCS Accumulator C level of 58% l

b. RCS to B S/G tube leakage at 0.5 gpm

c. Condensate Storage Tank Level of 35%

d. Containment internal pressure of 0.5 psig

e. PT 506 (HP Turbine First stage impulse pressure) failed HIGH

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f. Boric Acid Storage Tank level of 44%

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QUESTION 4.02 (1.00) '

Answer each of the following questions concerning BwAP 330-1, "Station Equipment Out-of-Service Procedure"

1. When hanging DOS cards for the 1B CCW pump, indicate the order (1-4)

] in which the cards would be hung on the following components: (0.5)

a. 1B CCW Pump Supply Breaker on Bus 142 L

b. 1CC 9460B (1B CCW Pump Manual Discharge Isolation Valve) l l l i c, 1B CCW Pump Control Switch on the MCB l d. ICC6B (1B CCW Pump Manual Suction Isolation Valve)

2. TRUE o. FALSE a

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Placement of CAUTION CARDS requires the permission of the Shift .

Engineer (or designee). (0,5) i I i 0

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(***** CATEGORY 04 CONTINUED ON NEXT PAGE *****) r 1 i I

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1 EBQCEDUBE.3_:_NOBd6L&_6EEQBd6L&_EMEBGEEGY_6ND PAGE 17 i BAD 19LQ9196L_H9EIB9L QUESTION 4.03 (1.00)

In accordance with BwAP 900-3, "Escort Duties," the NOMINAL number of visitors an Escort can have at a single time is: (Choose the ONE correct answer) i

a. 3 in a Vital Area and 5 in other areas

b. 5 in a Vital Area and 5 in other areas

c. 3 in a Vital Area and 10 in other areas i d. 5 in a Vital Area and 10 in other areas 1

i QUESTION 4.04 (1.00)

BwAP 300-1, "Conduct of Operations", allows an Operator to place a controller in the MANUAL mode from the AUTOMATIC mode whenever, in the Operators judgement, continued automatic operation is unsafe or whenever it may cause unnecessary transients. This SHOULD only be done under WHAT TWO conditions / situations?

QUESTION 4.05 (1.50) i 1 a. In accordance with BwhP 1000-A1, "Radiation Protection Standards",

describe the differences between a Type 1 RWP and a Type 2 RWP concerning the following items: (1.0)

1. Dose Rate '

i 2. Length of time that the RWP is valid

b. TRUE or FALSE A worker may be allowed to enter an airborne radioactivity area under a Type 1 RWP. (0.5) i QUESTION 4.06 (1.00)

A CAUTION in BwCA RCP-2, "Loss of Seal Injection,' states that if seal 4

injection flow is lost with RCS temperatures greater than 150 degrees F.

4 CC flow to the RCP Thermal Barriers must be maintained. WHAT is the reason for this? (Briefly Explain) i i

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

I

'i&__tBQCEDMBES - UQBdAkt_6BUQBd6Lt_EMEBGENCY_68Q PAGE 18 88D19LQGIG&L_GQUIBRL QUESTION 4.07 (2.50) l BwFR-S.1, "Response to Nuclear Power Generation /ATWS," immediate action Step 2, has you verify that the tubine has tripped. WHAT actions should be carried out by the operator if the turbine has NOT tripped? (Include all contingency substeps contained in the response not cbtained column in i your answer.)

GUESTION 4.08 (2.25)

A precaution in BwOP RC-1, "Startup of a Peactor Coolant Pump " states l that RCP #1 soal bypass should not be opened unless certain conditione are l

met. One of the conditions is that ROS pressure must be greater than 100 ;

psig but less than 1000 psig.

l

a. WHAT are the bases for these 2 pressure limits for opening the #1 seal bypass valve? (i.25)

b. WHAT is the reason for opening the #1 seal bypass valve? (1,0) l GUESTION 4.09 (1,50) l In accordance with BwOA FRI-2, "Emergency Boration " WHAT are SIX conditions that would require you to EMERGENCY BORATE 7 ,

l 1

QUESTION 4.10 (1.50) '

In BwCA Rod-4, "Dropped Rod Recovery," the procedure has you maintain ,

power less than the MAXIMUM FUEL PRECONDITIONED LIMIT. WHAT is this limit l defined as? (Aesume that this is NOT the initial power ascension I following a refueling outage.)

GUESTION 4.11 (1.50)

In accordance with BwRP 1110-1, "Radiation and Contamination Limits, WHAT are the Emergency Dose Limits you are allowed to receive if you need to !

enter an area to prevent conditions that would injure other people?

1

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

L_EBQ9EDUBES - NQBMALdBN.QBdhkEMEB9ENCY AHD PAGE 19 ,

BADlDLQ91 GAL CONTB9L I .

QUESTION 4.12 (2.00)

Immediate Action Step 4 of BwCA-0.0, "Loss of All AC Power," has you verify that the RCS is isolated. WHAT are FOUR indications / components that you have to verify to complete this step? (Include in your answer the required condition / position of each component / indication.) !

l QUESTION 4.13 (1.00)

There is a NOTE in BwAP 1450-1, "Access To Containment", that states for Modes 1,2,3, or 4, the MAXIMUM number of personnel that are allowed to enter containment is 30. WHAT is the reason for this restriction? (Briefly explain) l GUESTION 4.14 (2.00)

Answer the following questions concerning BwoA ELEC-3, "Local Emergency Start of a Diesel Generator": :

i

a. Step 2.C of this procedure has you place isolation switches 43I5-1, !

4315-2, 431S-3, and 43IS-4 on the D/G Control Panel in the ISOL l position. WHAT is the reason for placing bhese switches in the ISOL '

position? (Include the plant event when this would be done.) (1.25) i

b. i The CAUTION just before step 2.c tells you to place DG Isolation !

Switch 43IS-4 in the ISOL position ONLY AFTER the other 3 switches i have been placed in the ISOL position. WHAT is the reason for :

following that order when placing the switches in the ISOL position? !

(0.75) '

I l

QUESTION 4.15 (2.25) l l

BwFR-C.1, "Response to Inadequste Core Cooling,' Step 9, has you l depressuri:e all intact S/G's to 160 psig,

a. WHAT is the reason for depressuri=ing all intact S/G's? (1,0)

b. WHAT is the bases for stopping the S/G depressurization at 100 psig?

(Explain) (1.25)

(***** END OF CATEGORY 04 *****)

(...........*. END OF EXAMINATION ***************I

3. ' EBZ8CZELES_DE_8UCLEAB_EQUEE_ELABI_9EEBAIXQN. PAGE 20 IBEBd9DXU6Ml E _BEAI_IBANMEB_AND_ELH19_ELDH ANSWERS -- BRAIDWOOD 1&2 -87/12/14-LENNARTZ, J.

ANSWER 1.01 (2.00)

(0.25 pts each)

a. Increases b. Increases

c. Decreases d. Decreases

e. Decreases f. Decreases

g. Unchanged h. Increases REFERENCE Heat Transfer, Chapter 9, Figure HT-9-12 Terminal Performance objective #8 193008K105 ..,(KA'S)

ANSWER 1.02 (1.00)

1. Source neutrons are negligible.

2. It is below the POAH (or, Doppler and MTC effects are not present).

(0.5 pts each)

REFERENCE Reactor Theory. Chapter 9, pg. 14 Terminal Performance Objective #4 192008K112 ...(KA*S) l

L_._ EBIElELES_0LUELE AB_ECHEB_ EL 6EI_9EEBAI1081 PAGE 21 IBEBdQDYU6M19EA_HE61_IBAUSEEB_AUD_ELUlD_fb9F ANSWERS -- BRAIDWOOD 1&2 -87/12/14-LENNARTZ, J.

ANSWER 1.03 (2.00)

a. Q-dot (M-dot) (C-p) (delta-1)

M-dot : Q-Dot /(C-p)(Delta-T) (0.25) 3411x10E3 KW/(1.3 BTU /lbm-F) (60 F) X 3413 BTU /hr/kw

(1.49)(10E8 lbm/hr) (0.5)

b. (Note: Grader must use M-dot from a, that candidate calculates.

Answer in b. can be correct for date.)

Q-dot = (m-dot)(delta-h)

Delta-h : Q-dot /m-dot (0.25) 3411 x 10E3 KW/1.49 x 10E8 lbm/hr x 3413 BTU /hr/kw

78 BTU /lbn (0,5)

c. A decreasing macs flow rate increases the enthalpy riso. (0,5)

REFERENCE Thermodynamics, Chapter 3, pg. 153 193007K108 ...(KA'S)

ANSWER 1.04 (1.50)

a. Increare

b. More Negative (Decrease)

c. No Change ,

(0.5 pte each) l REFERENCE Braidwood Reactor Theory. Chapter 6. Objectives #7, 11, and ,

pgs. 17-22 l

015000A105 015000A202 016000K501 ...(KA*G) l

)

1___EBluCIELEE_0E_ERCLE68_EQMEB_ELAUI_DEEBAIl08s

- PAGE 22 IBEBdQD1HadlCS. HE6I_IBAUSEEB_AND_ELUID_EL9H ANSWERS -- BRAIDWOOD 1&2 -87/12/14-LENNARTZ, J.

1 AN5WER 1.05 (1.50)

e. Saturated

b. Superheated

c. Superheated

d. Subcooled i (0.375 pts ecch) I REFERENCE i Braidwood Thermodynamics, Chapter 3. Objective #9 and pgs. 101-107 -

Steam Tables 4 193004K115 ..,(KA'S)

ANSWER 1.06 (1.50) 1

! 1. Remain the Same

2. Remain the Same

3. Remain the Same l

4 Increase l

(0.375 pts each) i j REFERENCE Braidwood Reactor Theory Chap.7 pp. 7-13 192002K114 ...(KA'S)

, ANSWER 1.07 (1.50) 1 t I a. Calculated lower than actual t

b. Calculated higher than actual I j c. Calculated higher than actual i i

(0.5 pts each)

REFERENCE

} Braidwood Thermodynamics Chap. 4 pp. 64-91 l EwCS 3.1.1-2 i l 002000K505 015000A101 015000K504 ...(KA'S) 1 l

\ l I

)

I l

1

)

I 1

1. PBIUQlELES_QE_EMCLEAB_EREER_ELAHI_QEEBAIXQHz PAGE 23

, IBEBURDYHadlGEt_BEAI_IBAHSEEB_AED_ELillD_ELQH

. ANSWERS -- BRAIDWOOD 1&2 -87/12/14-LENNARTZ, J.

ANSWER 1.08 (1.00)

b. (1,0)

REFERENCE Braidwood Reactor Theory Chap. 3 pp. 24-32 192004K113 ...(KA'S)

ANSWER 1.09 (1.50)

RCS temperature and RCS pressure unaffected by the dropped rod. (.25 each) ,

Reactor power will have initial prompt drop [.25), then will decrease

[0.5), and level out at a lower power level in the source range (as supported by suberitical multiplication [.25).

REFERENCE i

Braidwood Reactor Theory Chap. 9 pp. 13-15 i Braidwood Reactor Nuclear Theory Chap. 8 pp. 13-19

Braidwood Nuclear Reactor Theory Chap. 7 pp. 53-57 000003K103 102005K103 192008K114 ...(KA'S)

ANSWER 1.10 (2.00) i I

! a. :

Rods will need to be withdrawn for about 4-7 hours [.25) and then 1

inserted for the next 35 hours4.050926e-4 days 0.00972 hours 5.787037e-5 weeks 1.33175e-5 months [.25). l l b. After the power decrease, the production of xenon from fission [0.25) 2 and from the decay of iodine [0.25) is greater than the renoval by l decay of xenon [0.25) and burnout by flux l0.25). After 4-7 hours, ,

the removal rate is greater than the production [0.25) and positive I I

I reactivity is being added until equilibrium at about 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months [0.25). i 1

i REFERENCE

)' Braidwood Reactor Theory, Chapter 4, Objective #1, and pgs. 14-29 001000K533 .. (KA'S) i j

i

! I' i

1

A2__EB18CIELEE_QE_SUGLE8B_E0 WEB _ELABI_GEEBAIIQU1 PAGE 24 l IBEBdQDXU8d1GS2_BSAI_IBANSEER_.6HD_ELUID_ELOW

' ANSWERS -- BRAIDWOOD 1&2 -87/12/14-LENNARTZ, J. '

1 ANSWER 1.11 (1.50)

a. MORE NEGATIVE [0.25] because rods are inserted and push the flux to !

the bottom of the core (0.25). '

b. LESS NEGATIVE [0.25] because more moderation will occur in the top 4

i of the core since there is a greater change in density with a change l in temperature at higher temperatures (top of core). [0.25). ;

I c. LESS NEGATIVE [0.25] because Xe inserts MORE negative reactivity in 1

the bottom of the core than in the top of the core (0.25),

i REFERENCE Braidwood Reactor Theory, Chapter 6, Objectives #3, 4, and pgs. 13-24 001000K506 001000K538 ...(KA*S) t ANSWER 1.12 (1.00) l

a. (1.0) ,

i REFERENCE I Braidwood Reactor Theory, Chapter 4, Objective si and pgs. 14-29 Westinghouse Simulator Training Book, "Rx Theory and Core Physics,' i l Figure I-5-54 '

001000K538 ...(KA'S) i i !

l ANSWER 1.13 (1.50)

N1 : 1500 rpm V1 : 250 gpm Hpi : 15 psig P1 : 40KW i f

N2 1500 sqr. root (10/15) : 1224.7 rpm (1225 acceptable) (0.5) l

!l i V2 : (1224.7/1500)(250 rpm) = 204.1 gpm (204 acceptable) (0.5) f

3 l P2: (1224.7/1500) (40 KW) = 21.7 KW (22 acceptable) (0.5) i 1

)

! REFERENCE I Braidwood Fluid flow, Chapter 2, Gbjective #4 and pgs. 26-33 l I

191004K105 ...(KA's) l i

l l

l I

i

LEBX t!GAEL ES_0LtGGLEA B_ E9MEB_ELAtiL9EEBAI19112 PAGE 25 IBEBUQDXU6019&uBEAT TRA11 SEER AND FLVID_ELQg ANSWERS -- BRAIDWOOD 1&2 -87/12/14-LENNARTZ, J.

l ANSWER 1.14 (1.00)

, t

a. Over predict (non-conservative)

b. No Change

c. No Change

(0.33 pts each, 1.0 all three)

REFERENCE ,

j Braidwood Nuclear Reactor Theory Chap. 8 pp. 20-30

., 015000A202 015000K506 192008K104 ...(KA'S) l -

i ANSWER 1.15 (2.50)

a. Turbine power - stays constant at 33% power (due to EHC being in auto). (0.5)

! b. Tavg (loop 1B) due to no heat sink, goes to Th = 554 F + 18/2 : 563 F (0,5)

{ c. Tavg (loop 1D) total reactor power has not changed; however, the power that 1D S/G i

must loop produce has increased by a factor of 1/3 to compensate for 1B j

i .

QRX = m Cp (Th - Tc) !

i initial Delta T was 18 F, increase by 1/3 ::> final Delta T : 24 F ;

final Tavs : Th - Delta T/2 : 563 - 24/2 = 551 F (0,5) i I d. S/G Pressure (loop 1B) i saturation pressure for 563 F - 1161 psia (or 1146 psig) (0,5) l j

l [also acceptable if assume that safeties wil be lifting starting at 1065 psig) l

i

e. S/G Pressure (loop 1D) :

j j

as with part c. above, the appropriate Delta T will increase by 1/3 QSG : U A (Tavg - Tstm) i initial Delta T : Tavg - Tstm = 554 - 539 : 15 F j final Pstm ::) saturation for $31 F : 893 psia (or 878 psig) (0.5)

REFERENCE Braidwood Thermodynamics, Chapter 3 Objective #6, and pgs, 66-76 j 002000K511 039000K104 039000K305 ...(KA'S)

I i

)

i i

LEB2892ELES_0LN!JCLEAB_E9EB_EL6HLOREBAIlgHo FAGE 26 IBEBM99Y Uedl&_HE8I_IB6HSEEB_ AND_EL!MD_ELQW

' ANSWERS -- BRAIDWOOD 1&2 -87/12/14-LENNARTZ, J.

ANSWER 1.16 (2.00)

a. (Since the amount of reactivity inserted is one-half of the total amount needed to reach criticality.) the count rate should double, or about 100 cps. (.75)

OR For rho = K-1 (valid approximation)

CR1/CR0 : (1-KO)/1-K1)

(1-(rho 0 + 1)/(rhol + 1))

rho /rhol

2 CR1 : 2*CRO : 100 eps (actual is 98.54 eps) (.75)

b. For rho : K-1 CR1/CR0 : rho 0/rhol OR rhoo = rho 1*CR1/CR0 (.25)

Since the change in reactivity was 750 pcm (one-half of the total dilution): (.25) rhoo : (rho 0 + 750 pcm)*CR1/CR0 (rhoO + 0.0075)*80/50

1.6 rhoO + 0.012

-0.6 rhoO : 0.012 rhoO : -0.02

-2000 pcm Therefore, the original ECC should have determined that criticality would be achieved if 2000 pcm was added to the core. (.75) i REFERENCE Braidwood Rx Theory. Chapter 5, Objective #7 and pg. 3 Braidwood Rx Physics, Chapter 5, Objective #13, and pgs. 21-24 Chapter 7 Objective 84, and pgs. 37-45 Westinghouse Fundamentale of Nuclear Rx Physics, pgs. 5-22 to 5-29, 6-39 to 8-41 001010A207 004000K520 192006K103 ...(KA'S)

I

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

2&__ELABI DEB 198 lEChuBIEG_BAEEIY_AND_EMEBGEEGY_SYSTEME PAGE 27 l ANSUERS -- BRAIDdOOD 1&2 -87/12/14-LENNARTZ, J.

l ANSWER 2.01 (1.50)

a. The Inverter is supplied with power from the 125 VDC Bus also, through a blocking diode (0,5). If the AC power supply fails or drops below a certain value, then the 125 VDC Bus will take over l automatically [0.5). (1.0)

b. Self Regulating Transformer (480/120 volt). (0,5)

REFERENCE Braidwood AC Electrical Power System, pgs. 49, 50 Terminal Performance Objective #14 062000K410 ...(KA'S) i ANSWER 2.02 (1.00)

1. Wide Range RCS Pressure :

2. Function Generator (inputs from W.R. Hot Leg and W.R. Cold Leg '

temperature)

(0.5 pts each)

REFERENCE Braidwood Pressurizer Pressure a.ad Level Control. pg. 14 .

002000K410 010000K403 ...(KA'S)

ANSWER 2.03 (1.50) 46 degrees down from hori: ental centerline (0,5), which enables water to be lowered in the RCS piping if required for maintenance (0.5) and ;

continue to operate the RHR loop [0,5).

REFERENCE Braidwood Reactor Coolant System, pg. 12 '

005000K109 ...(KA'S) !

{

1 i

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

1 8 ELANT DESIGU_ZU9LUDING_BAEEIY_AND_EMEBGEUCY_SXSIEd5 PAGE 28 i

ANSUERS -- BRAIDWOOD 1&2 -87/12/14-LENNARTZ, J. !

J 1

ANSWER 2.04 (2.00)

Use the RWST through CV-112 D/E and a Contrifugal Charging Pump (0.5) with

at least 10b gpm charging flow (0,5).

Charging flow of 105 gpm with 2000 ppm boron (as contained in the RWST)

[0.5), is equivalent to adding 7000 ppm boron as required by Technical Specifications (0.5).

l REFERENCE 1 Braidwood Reactor Makeup Control, pg. 27, and Terminal Performance j Objective #10 !

004000G010 004010A207 004010K609 ...(KA'S) '

1 l

ANSWER 2.05 (1.50)

a. 1. Low DC Output Voltage (Charger Output Voltage Low)

2. High DC Output Voltage

3. Low output Amps i 4. Low AC Input Voltage (AC Input Breaker Trip)

5. High AC Input Amps ;

6. AC Power Failure

7. Charger Feeder Breaker Trip !'

8. Blown Fuses (Any 4 @ .25 pts each) i

b. The minimum time period is based on Main Turbine Coast-Down time.

(0.5) '

l REFERENCE Braidwood 250 VDC Fwr Distribution, pgs. 5, 13 i

BWAR 1-20-CID 000055K301 063000G008 ...(KA'S) .

! ANSWER 2.06 (1.00) i I

l a

Since some of the water is not directed to the inlet of the VCT:

j 1. The water is not desassed. (0,5)

2. The water is not exposed to hydrogen. (0.5) i i

i i

1

i

a. TL6HLDEB1GH_lHCLUD&HG_EAEEILAUD EMEBGEURLEYEIEMS PAGE 20 l ANSWERS -- BRAfDWOOD 1&2 -87/12/14-LENNARTZ, J.

l l

REFERENCE Braidwood Reactor Makeup Control, pg. 26 l Terminal Performance Objective #7.d 004000G010 004000K106 004000K40'. ...(KA'S)

ANSWER 2.07 (2.00) ,

i

1. Open !

2. Closed

3. Open

4. Open i (0.5 pts each)

REFERENCE

Braidwood Chem.ical and Volume Control, pgs. 13, 17, 19, 36 i 004010A204 ...(KA'S) i ANSWER 2.08 (2,50) I rce % cal G

a. 1. SI pump miniflow line valves (8614 and 6920) closed or SI pump !

common header miniflow valve (8813) closed. ,

j 4 2. RHR outlet isolation valve (8;02A) or RHR inner isolation valve (6702B) closed, 1

1 1

3. Recirculation Sump Isolation Valve (8811B) open. '

, (0.5 pts each) (

j L. EGev G

b. l

1. Prevents overpressurication of the SI pumps. '

2. Prevents radioactive recirculation water from being pumped to RWST. i (0,5 each) ;

! REFERENCE Braidwood Residual Heat Removal System, pg. 24 !

iorminal Performance Objective #6.e.

)

) 005000K407 ...(KA'S}

4. For 6ecn A

( t. 3r p.f e'. .]Ls tus Me s ( ttj4 asa 99L.) cloud or st ps-f ce =" H 4 - m . ,)te s p\p v tve (9m) ema

\ 1. iNA c.1% & vou da ev* (svo d) . f M oku- w& u t,e (s ten a) clost.

->< f s W..n . a- w.e x.. r sun (,, , , m , , ,p,, .

y pa eten A l s. pue-h cas ef er u < . i cf ev p-ts i t. p r.ir +>

r s4 . **,< h e s resarcut h4 a k# f.*~ k n y p q ed k s fy > T~

)

AuML68I_.DESIGU_ZE LHD181.S AEEIL6 HD_EMERG EN GLSXSIEtjS PAGE 30

, ANSWERS -- BRAIDWOOD 1&2 -87/12/14-LENNARTZ, J.

ANSWER 2.09 (2.00)

a. Low discharge pressure (85 psig)

Return of power after station blackout Safety Injection (Any 2 @ 0.5 pts each)

b. No (0.5), it will not autostart on low pressure unless CCW pump 1A (the CCW pump on the same bus) is in PULL-TO-LOCK (0,5). (1.0)

REFERENCE Braidwood Component Cooling Water, pg. 12 Terminal Performance Objective #7.

008000K201 008000K401 ...(KA'S)

ANSWER 2.10 (2.00)

a. Provides enough fuel to allow the diesel to operate fully loaded (0,5) for 72 minutes (.25).

b. This position functions to permit speed and voltage control after an emergency start (0.5] with only the emergency trips enabled (generator differential, overspeed, and manual emergency). (.75)

REFERENCE Braidwood Diesel Generator and Auxiliaries, pgs. 47, 68 064000G007 064000K608 ...(KA'S)

ANSWER 2.11 (2,50)

a. As flow incrases to greater than 80 gpm to each S/G (0,5), a DC powered status light will energize (0.5).

b. A reset time delay relay is energized for (10 seconds) (.25), and attempt to restart engine by cranking for 5 seconds (.25). Four (4) attempted . starts will be allowed (0.5), and then an "overcrank" alarm will energize in the Control Room [.25) and the engine will lock-out in (55 seconds) (.25).

REFERENCE Braidwood Auxiliary Feedwater System, pgs. 23, 26 Terminal Performance Objective #13 000055A204 061000A204 061000G008 061000K406 ...(KA'S)

2t: EL6BI_DESIGH_1EGLHDIEQ_BAEEII_AUD EMEBGEUQY_EYEIEdB PAGE 31 ANSWERS -- BRAIDWOOD R&2 -87/12/14-LENNARTZ, J.

1 ANSWER 2.12 (1.75)

1. RCP Seal Injection Flow 1

2. RCP Seal Leak-off flow

3. RCP Seal Delta P

4. RCP Lower Radial Bearing Temperature

] r

5. RCP si Seal Outlet Temperature !

j 6. RCP Amps (current meter)

7. RCP Status Lights (running and trip)

> 8. RCP Oil Lift Pump Status Lights (running and trip) <

9. Loop Stop Valve Fermissive Lights

10. RCS Loop Flow (Any 7 @ .25 pts each) i 1 REFERENCE -

i Braidwood Reactor Coolant Pump, pgs. 25, 26

! 003000G008 ...(KA'S) i j ANSWER 2.13 ( .75)

J 1. Containment Atmosphere Area Radiation Monitor High Alarm

! 2, Manual Phase A Isolation i

j 3. Safety Injection (AUTO or MANUAL) '

(

] 4. Manual Containment Spray Actuation l I

(Any 3 @ .25 pts each) l REFERENCE

Braidwood Containment Ventilation and Purge System, pg. 57 4

Braidwood Engineered Safety Features, pg. 30 013000K101 103000K406 ...(KA'S) i I

i l

l 1

E. ELABI_DEElGU_1EGLUDIE2_Q6EEIY_AUD_EUEBGEN91_EYEIEUS PAGE 32 i

ANSUERS -- BRAIDWOOD 1&2 -87/12/14-LENNARTZ, J.

t i

i i ANSWER 2.14 (2.00) i i

1. Allows BCS forced flow to continue for the duration of the time delay l l (0.b) which would reduce the consequences if a loss of RCS flow i j occurs, since the reactor has been shut down for some time (0,5). '

) 2. Minimises RCP overspeed by locking RCP's at bus frequency (60 Hs) '

[0.5) which could prevent flywheel destruction forming missiles !

j which could damage the containment liner (or ECCS components within containment) [0.5). '

3. Prevents turbine overspeed (0.5] as a result of steam within the j turbine shell expanding to the condenser (0,5).

1 l (Any 2 @ 1.0 each) :

1 REFERENCE !

j Braidwood Reactor Coolant Pump, pr. 45 l i*

045050K301 045050K408 ...(KA'S) l 1

i ANSWER 2.15 (1.00) i j 1. 4160V/480V Transformer 4

2. Centrifugal Charging Pump l i

i i j

l 3. Control Room Refrigeration unit :

i l l 4. Component Cooling Pumps .

j

}

j 5. Essential Service Water Pumps I i

) 6. Auxiliary Feedwster Pumps {

3 (Any 5 6 0.2 pts each)

REFERENCE

} Brridwood Engineered Safety Features, pgs. 60, 61 i Br '

od Diesel Generator and Auxiliary Equipment, pgs. 62, 63 Te c. t1 Performance Objective 87 013000K112 064000K410 ...(KA S) 1 1 l 1

-i . - - - _ _

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

3. 'IUSIEUdENIS_AHD_COMISQLS PAGE 33 ANSWERS -- BRAIDWOOD 1&2 -87/12/14-LENNARTZ, J.

i ANSWER 3.01 (1.00) 4 c.

I i REFERENCE I

System Descriptions. Rod Control, Chapter 28, Figure 28-25 l

) Terminal Performance Objective #10 '

001000K403 ...(KA'S) i ;

ANSWER 3.02 (1.50)

I

a. Increases [.25) due to reference leg heating. Reference leg becomes l less dense and delta-P decreases across the detector (.25).

t

b. Remains the Same [.25) because the PRZR uses a double bellows (.25).

6

c. Increases (.25] because the height of the reference leg decreases ;

j and so delta p across the detector decreases (.25).

]

REFERENCE >

' System Description. PRZR. Chapter 14. Appendix B, Review Question 39 Terminal Performance Objective #21 011000A101 ...(KA'S) i '

]

ANSWER 3.03 (1.50)

At the point in the sequence when the stationary gripper deenergizes the i rod will fall into the core until the stationary gripper reenergizes !

j (1.0). This will generate into a series of short rod drops until the rod is fully inserted or the rod motion is stopped (by placing rods in manual i j or by termination of demand) [0,5).

REFERENCE i System Description. Rod Control. Chapter 26, pg. 22

) Braidwood Simulator Malfunctions. CRF-4 J 001000K103 ...(KA'S)

.I I

i i

}

t i

l

S m _ f.IUSIBUdEUIS_AND_gQBIBQLS PAGE 34 '

{ ,

ANSWERS -- BRA 3DMOOD 1&2 -87/12/14-LENNARTZ, J.

l I

ANSWER 3.04 (1.50) ;

(0.25 pts each)

1. Group Step Counters I

2. Master Cycler

3. Slave Cyclers

4. Bank Overlap Unit ;

5. All internal memory and alarm circuits

6. P to A converter '

REFERENCE System Description, Rod Control, Chapter 28, pg. 55 !

Terminal Performance Objective s17 001010K402 ...(KA'S) l l

l ANSWER 3.05 (1.50) l

a. The signal is used in the Rod Control System (0.25] to quicken the reactor control units response during a transient (0.25] by comparing rate of change of nuclear power to turbine power (0.25).

b. The signal is used in the SGWLC system [0,25) to provide an anticipating signal for power changes [0.253 by adjusting the level error signal in the feed bypass valve controller (0.25).

(Note: Equivalent wording accepted)

REFERENCE System Description, Pwr Rng NIS, Chapter 33, p. 33 Figure 33-1 Terminal Performance objective s7c System Description, SGWLC, Chapter 27, pg. 22 Terminal Performance Objective 85 System Description, Rod Control, Chapter 26, pg. 26 j 016000K103 035010K401 ...(KA'S) {

ANSWER 3.06 (1.50)

The delta-P between steam and feed increases beyond the program (0.75).

To reduce this delta-P MFP speed will decrease (0.75).

REFERENCE System Description, SGWLC, Chapter 27, pgs. 29-30 Terminal Performanco Objective 515e 1 j

035010A203 ...(KA'S) '

l l

l

3. '3USIBUdEUIS_AUD_CQUTROLS PAGE 35 !

ANSWERS -- BRAIDWOOD 1&2 -87/12/14-LENNARTZ, J. I l '

l i !

i 5

ANSWER 3.07 (1.50) '

I i The Tavg vs Tno-load mismatch will trip the high-high bistable (30 i degrees) and cause all dump valves to snap open (0.5]. All dump valves will remain full open until a Lo-Lo Tave signal is received (0.5). Then !

j all dump valves will shut (0,5). (The hi-hi bistable will not clear.) !,

! REFERENCE '

l System Description, Steam Dumps, Chapter 24, Figure 24-1 j Terminal Performance Objective #3d4 l

l 041020K105 041020K411 041020K414 ...(KA'S) i i

i l

i i

ANSWER 3.08 (2.00)

The controlling circuits sense a high pressure (0.25) which will turn the l l sprays on full (0.25), open 455A-PORY (0.25) (and generate high pressure !

, alert alarms). Actual pressure will decrease (0.25) and 455A-PORV closes !

when channel IV pressure drops below 2185 psig (0.25). The sprays continue to lower pressure (0.25) until a low pressure Reactor Trip (0.25]

j and Safety Injection (0.25] are actuated.

\

REFERENCE t l System Description, FRZR Chapter 14, pg. 54 i l Terminal Performance Objective #21 !

) 010000A302 010000K601 ...(KA'S)

I i 1 ANSWER 3.09 (1.50) f L

I a. A reactor trip and bypass breaker open in the same train, (0.5) j!

i b. (0.25 pts each) i

1. Trips Main Turbine j

2. Feedline isolation with Lo Tave (504 degrees F)

3. Prevents reactuation of SI after a manual reset

4. Frevents opening feedwater valves when closed by SI or F-14 (S/G Hi-Hi Level).

l REFERENCE System Description, RFS, Chapter 60b. pg. 21 and Appendix B Terminal Performance Objective 84 System Description. ECF, Chapter 61, pg. 32-33 I

l

3. ld&IBUMEUIS_680_QQUIBQLE PAGE 36

, ANSWERS -- BRAIDWOOD 1&2 -87/12/14-LENNAP.TZ, J.

012000K610 ...(KA'S)

ANSWER 3.10 (1.50)

No (0.5). Channel II must energi=e to actuate for an unsafe condition (1.0) (to avoid insdvertent spray actuation in the event of a loss of instrument power).

REFERENCE System Description. ESF, Chapter 61. pg. 31. Figure 63-15 013000K101 013000K407 ...(KA'S)

I ANSWER 3.11 (1.50) ;

a. (any three at 0.25 pts each)

I

1. RCS W.R. Pressure

2. Average of 10 highest CETs ,

3. Containment Pressure i

4. Containment Radiation '

b. (0.25 pts each) t

1. Precsure margin to ssturation

2. Temperature msrgin to saturation

(

3. Trends i

REFERENCE System Description, ICCM, Chapter 34b, Appendix A Terninal Performance Objectives #6 and #7 000074A113 002000K603 017020K401 ...(KA'S) i

1&__&BSIBudSSIS_AUD_GQEIB9LE PAGE 37 ANSUERS -- BRAIDWOOD 1&2 -87/12/14-LENNARTZ, J.

ANSWER 3.12 (1.50)

a. (Any 4 @ 0.25 pts each)

1. Loss of power supply

2. Removal of printed circuit card

3. Placement of switches (in a train) to testing positions

4. Bypass breaker closed

5. Loss of continuity through the ground return fuse

b. The reactor trips. (0.5)

REFERENCE System Description, SSFS, Chapter 60A, pg. 15 Terminal Performance Objective 86 012000A303 012000A307 012000A402 012000A404 ...(KA'B)

ANSWER 3.13 (1.00)

(0.5 pts each)

a. False

b. False REFERENCE System Description, RSF, Chapter 62, pg. 8 and Appendix A Terminal Performance Objective 84 000068A121 ...(KA'S)

I

. ' ai_228SIBVMEUIB_ABB.GQUIBQLS PAGE 38 ANSWERS -- BRAIDMOOD 2&2 -87/12/14-LENNARTZ, J.

[.

l ANSWER 3.14 (2.00)

a. (0.25 pts each, 0.05 pts for setpoints and coincidences)

1. Lo Steamline Pressure, 640 psig, 2/3 channels on 1/4 S/G'c

2. Hi Steam Rate, 100 psig/50 sec. 2/3 channels on 1/4 S/G's

3. Hi-2 Containment Pressure, 8.2 peig, 2/3

4. Manual

b. Prevents continuous, uncontrolled blowdown of more than one S/G in tha event of a rupture (0,5) preventing an uncontrolled RCS cooldown (0.5).

REFERENCE System Description, ESF, Chapter 61, pgs. 27 and Appendix B Terminal Performance Objective #7A 013000K403 039000K405 ...(KA'S)

ANSWER 3.15 (1.75)

a. (0.25 pts each)

1. Steam Jet Air Ejectors (RE-PR027)

2. S/G dlowdown (RE-PR008)

3. Msin Steamlines (RE-AR022-23)

b. Upward movement of the crane hoist is inhibited. (0.5)

c. Both unite surge tank vent valves close. (0.5)

REFERENCE System Description, RMS, Chapter 49, pgs. 42, 44, 49 Terminal Performance Objectives #4a3, 84b2, #14b 000036K202 000037A104 000037A100 000037A113 008000A204

...(KA'S) l l

1

' 3. ?NSTBUUEUIS_AUD_C9 BIB 9LS PAGE 39 1 .

, AtlSUERS -- BRAIDMOOD 1&2 -87/12/14-LENNARTZ, J.

]

4 .

I 1 l l

1 ANSWER 3.16 (2.25) ,

s. (0.25 pts each, coincidences worth 0.05 if applicable)

I

1. SI I

2. S/G Lo-Lo Level, 2/4 channels on 1/4 S/G's \

' i

! 3. Undervoltage on 2/4 RCP busser

^

4. UV on but 141 j b. Pump oil pressure greater than or equal to 8 psig (0.25) {

i q

c. (0.25 pts each) !

1. Control switch trip !

{

i

Overcurrent I

j 3. Lo-Lo suction pressure i 1 ,

i 4. Undervoltage 1

~

REFERENCE System Description, AFW, Chapter 26, pg. 53 and Figure 26-10 Torninal Performance Objectives #3, #5, and 87 !

061000A204 061000K402 061000K406 ...(KA'S) '

f i

I 1

l t

i I i l l !

i l

)

1 J

i I

i

'iu_lEBOCEDl! BEE _ _UQBd6Lt_6BUQBd6L&_EMEBGENCY_3UD PAGE 40 '

B6D10L99196L_CQHIBQL ,

ANSWERS -- BRAIDWOOD 1&2 -87/12/14-LENNART2, J. ;

l l

l ANSWER 4.01 (3.00) ,

a. No

b. Yes i

c. Yes I

d. No

(

e. Yes +

f. No !

(0.5 pts each)

REFERENCE Braidwood Technical Specifications l

002000G011 004000G011 012000G011 061000G011 ...(KA'S) l ANSWER 4.02 (1.00) 3,

1. a. 2

b. 3 C. 1

d. 4 (0.5 for correct order) l l

2. True. (0.5) !

I REFERENCE SWAP 330-1, pgs. 5, 8 194001K102 ...(KA'S) l l

[

ANSWER 4.03 (1.00) !

d. (1.0)

REFERENCE l EwAP 900-3, pg. I !

194001K105 ...(KA's) l l

' d _1E89CEDUBES - UDBMALt_ABUGBMALt_EMZB9EUGY_AUD PAGE 41 ;

BAD 19LR91 CAL _CDUIBOL ANSWERS -- BRAIDWOOD 1&2 -87/12/14-LENNARTZ, J. !

l

)

.I ANSWER 4.04 (1.00)

1. Conditions are stable and under control !

j 2. Continued operation would aggravate or worsen plant conditionc

] (0.5 each)

I

. REFERENCE '

BwAP 300-1 p. 4

191003K111 ...(KA*S)

)

{

I ANSWER 4.05 (1.50) !

a. Type 1 Type 2 l

2. Less than 50 mrem / day 1. Greater than 50 mrem / day !

2. Maximum of 1 year 2. Length of job

{ (0.25 each)

b. TRUE (0.5) i REFERENCE t

Bwh? 1000-A1, pts. 11-17 t

l 194001K104 .

.(KA'S) i ,

i i

ANSWER 4.06 (1.00) -

1 To prevent seal damage from overheating. (1.0) !

i

! REFERENCE BwCA RCP"2, pg 2 al 0040000010 ..,(KA'S) r i

l l l t I \

\

l I 1

I l'

i l

1

'4[_iEB09EDUEES__U0EMeLi_ABUQSMALt_EMEh0EUCY_AUD PAGE 42 BAD 19L901. CAL _EQ1!Ih0L ANSWERS -- BRAIDWOOD 1&2 -87/12/14-LENNART2, J.

ANSWER 4.07 (2.50)

1. Manually trip turbine. (0.5)

2. Manually runback turbine. (0.5)

3. EH pumps to pull out. (0,5) l

4. Initiate steanline isolation (0,5) and verify MSIV (0.25] and MSIV bypass valves. closed (0.25).

REFERENCE t BwFh-S.1, pg. 3 000029K306 000029K312 ...(KA'S) 1 ANSWER 4.08 (2.25) ,

a. 1. ) 100 psig prevent backflow of dirty water frem VCT. (0.625)

2. < 1000 psig - prevents cocking #1 seal (prevent thernal shock to pump shaft, seal, and pump bearing during a loss of seal ,

injection).(0.625) i

b. Orening the bypass allows more flow through the RCP lower radial be a rir.g [0.5] which increases the cooling of tl.e bearing (0.5). ;

REFERENCE l BwCP RC-1 l EwCP RC-1. Iessen Plan, pg. 9 1 003000G010 ...(EA'S) 1 L

1 l

l l

l i

'4. LEBQJEDDBES - H9BMAL1_ABSOBdbL1_EMEB9EUGY_AND PAGE 43 BALIDL9GI9AL_CDUI _ROL

' ANSWERS -- BRAIDWOOD 1&2 -87/12/14-LENNARTZ, J.

ANSWER 4.09 (1.50)

1. Rodo below rod insertion limit.

2. Failure of more than one RCCA to fully insert following a reactor trip or shutdown.

3. Unexplained or uncontrolled reactivity increase.

4. Failure of Reactor Makeup Control System.

5. Uncontrolled cooldown.

6. Inadequate shutdown margin.

7. The more restrictive of Keff less than .95 or boron concentration greater than or equal to 2000 ppm during refueling.

(Any S C 0.25 pts each)

REFERENCE EwCA PRI-2, pg. 1 0000240011 .. (KA'S)

ANSWER 4.10 (1.50)

The maximun l'el preconditioned limit is defined as the maximum power level achieved [0.5] for a cumulative 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months (0.5) during the previous 4 30 dayc of power operation [0.5]. '

REFERENCE EwCA ROD-4, pg. 6 0010000010 ...(KA'S)

ANSWER 4.11 (1.50) ,

1, l 75 rems - whole body

2. 200 rems extremities (0.75 pts each)

REFERENCE BwRP 1110-1, pg. 6 194001M103 ...(KA'S)

d. 'EBQREDHEES_- NOBdAL1_ABEDEM6L&_EMEBGEEGY_AED AGE 44 BAD 19LQ9196L_CREIB9L

ANSWERS -- BRAIDWOOD 1&2 -87/12/14-LENNARTZ, J.

ANSWER 4.12 (2.00)

1. Pressuriser PORV's - closed.

2. Letdown orifice isolation valves - closed. (8149 A,B,C)

3. Letdown line isolation valves - closed. (CV-459, 460)

4. Excess letdown isolation valves closed. (CV-123, 8153 A,B)

(0.5 pts, each)

REFERENCE BwCA 0.0, pg. 4 000055G010 ...(KA'S)

ANSWER 4.13 (1.00)

This ensures that all personnel will be able to leave containment in one cycling of the personnel airlock (0.5) if containment evacuation would be necessary. (0,5)

REFERENCE BwAP 1450-1, pg. 3 103000A204 103000G010 ...(KA'S)

ANSWER 4.14 (2.00)

a. It isolates the D/G controls [0.25] and indicators (0.25] from the Main Control Room (0.25) in the event that damage has occured to any DG control circuitry (or control room has been evacuated due to a fire). [0.5)

b. This prevents blowing backup fuses (0.75).

REFERENCE BwoA ELEC-3, pg. 4, 5 Braidwood D/G and Auxiliaries, pg. 60 000068K207 064000G007 064000G010 ...(KA'S) l l

I

i _'_EBOCEEEBES - NOBd8L&_6BE0Bd6L&_EbEBGEURY_8HD PAGE 45 B8010 LOGICAL _CONIRQL

' ANSWERS -- BRAIDWOOD 1&2 -87/12/14-LENNARTZ, J.

ANSWER 4.15 (2.25)

a. Depressurize all intact S/G's to cooldown and depressurice the RCS

[0.5] which will increase ECCS injection flow into the RCS [0.25] and allow the SI Accumulators to inject. [0.25]

b. Prevent nitrogen from accumulators from being injected into RCS [0.5) which could collect in Rx Vessel Head and create a hard bubble

[0.375] or can collect in the S/G tubes and reduce heat transfer (0.375].

REFERENCE BwFR-C.1, pg. 11 BwFR-C.1, Lesson Plan, pgs. 60, 61 000074G007 000074K310 000074K311 ...(KA'S) i i

4

ML20148R734

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