ML20207G827

Exam Rept 50-305/OL-86-01 Administered During Wk of 860623. Exam Results:All Reactor Operators Passed Exams.Examiner Comments,Exam & Answer Key Encl

ML20207G827
Person / Time
Site:	Kewaunee
Issue date:	07/17/1986
From:	Burdick T, Isaksen P, Reidinger T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20207G815	List: ML20207G810 ML20207G827
References
50-305-OL-86-01, 50-305-OL-86-1, NUDOCS 8607230189
Download: ML20207G827 (44)

Text

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U.S. NUCLEAR REGULATORY COMMISSION i

l REGION III 1

l Report No. 50-305/0L-86-01 Docket No. 50-305 License No DPR-43 Licensee: Wisconsin Public Service Corporation ATTN: Mr. D. C. Hintz Manager, Nuclear Power Post office Box 19002 Green Bay, WI 54307-9002 Facility Narre: Kewaunee Nuclear Power Plant Examination Administered At: Kewaunee Nuclear Power Plant Examination Conducted: Week of June 23, 1986

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Examiners:

T.

eidinger 4

Date

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Date l

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.b Approved By.

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l Examination Summary Examination admini s tered the_ wee _k_p_f__Jun_e_23,_ i_9_86_,(R,eppr_t_ Np_,5,0__3_05/_0_L__8_6 _011 3

Examinations tiara admlnistered to seven reactor operators, j

_Resul ts : All seector operators passed.

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8607230189 e60717 ADOCK 0500 5

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REPORT DETAILS 1.

Examiners T. D. Reidinger, Region III P. Isaksen, INEL 2.

Examination Review M_eet_ing A copy of the examination and answer key was given to the facility personnel for review at the conclusion of the written examination.

Facility personnel mailed their coments to the Chief Examiner after their review. Their consr.ents and the resolution of these coments are contained in the attachment to this report.

3.

Exit Meeting a.

On June 27, 1986, an exit meeting was held. The following personnel were present at this meeting:

R. Zube, Facility Simulator Supervisor J. Brown, Facility Training Instructor D. Braun, Operation Supervisor s

b.

The chief examiner discussed the following points with the utility:

(1) The caution plate on the reactor operator's console in the simulator and Kewaunee control room is in disagreement with the Kowaunee Operating Procedure N-0-03 (Plant Operation Greater than 15% Power). This has led the candidates to consistently violate their procedure which states that rod control must "be manual if control bank 'D' is below 215 steps when reactor power is between 90% and 100%."

(2) The major generic weakness noted was the consistent inability of the candidates to basically relate to any of the electrical annunciators and alarms and associate their significance during normal power operations and abnormal evolutions.

2

ATTACHMENT Exam Comment Resolution for Kewaunee R0 Exam Given on 6/24/86 Facility Comment:

1.01a Answer key item "and there must be fuel in the vicinity of the source" could be answered "and a subcritical reactor with Xeff <1.0".

Reference:

KNPP, OTM, P. I-4.2 NRC Resolution:

1.01a The "suberitical reactor was given in the question. A reiteration of the question information is not an acceptable answer. No changes to answer key.

Facility Comment:

1.01b Regarding when is 1/M plot used:

Answer could be "when requested by the Reactor Supervisor"

Reference:

KNPP, Procedure, N-CRD-49B item 2.4 NRC Resolution:

1.01b This answer will be accepted, but not required, for credit.

Facility Comment:

Allowances should be made for being within some % of specific values 1.02c given in key.

NRC Resolution:

l 1.02c Answer key changed to 2600 2 60 pcm l

l Facility Comment:

2.02 Answer key reference should read "Kewaunee, SD 2,3, P. 1" Additional answer of "some removal of iodine from the containment vessel atmosphere is provided" should be allowed.

Reference:

KNPP, FSAR P. 6.4-1 r

l l

ARC Resolution:

2.02 The facility stated referen::e was not supplied to the examiner with these connents and the additional infonnation is not included in the previously supplied training material. The additional infonnation is, however, regarded as correct. The answer will be accepted, but not required, for credit.

Reference:

Modified as recommended Facility Comment:

2.03 1.

Answer key #2 should be deleted -- System Description error.

2.

Additional answers:

a.

SW-1300A and B (SW to CC heat exchangers) open.

b.

SW-903A, B, C, & D (SW returns on containment fan coil units) open.

c.

SW-301A and B (diesel generator SW heat exchanger outlet valves) open.

Reference:

1.

KNPP, Logic E1632 2.

a.

KNPP, Logic E1632 b.

KNPP, Logic E1632 c.

KNPP, Logic E1621 NRC Resolution:

2.03 1.

Agree; item #2 will be deleted.

2.

Agree; additional answers added to answer key as possible responses to the question (Three required).

Facility Comment:

2.04 Question did not require setpoints in either part a or b -- delete set-points from answer key.

NRC Resolution:

2.04 Setpoints were included in the answer key in parenthesis, indicating not required for credit. No change required to answer key.

2

o Facility Comment:

2.06e Delete "... bus 1-1" in answer key. Answer should be "4160V bus 1-2".

Reference:

KNPP, Schematic E240 NRC Resolution:

2.06e Agree; answer key changed to reflect correct power supply.

Facility Comment:

2.07a Question wording may only solicit " transfer (BAST to RWST) will not occur".

NRC Resolution:

l 2.07a Agree; " BAST to RWST transfer will not occur" is added to the answer key as possible correct response for full credit.

Facility Comment:

2.08 Question wording may solicit answer associated with secondary plant chemistry vice primary plant chemistry.

If secondary chemistry is assumed, then answer would be "with hydrazine" or "same method".

NRC Resolution:

2.08 Agree.

If assumption is stated, the question will be graded accordingly. Question wording will be changed for subsequent exams.

Facility Comment:

2.09 Answer key should be modified as follows:

Pump Auto Start Auto Stcp i

I 1.

Jockey Fire Pump 128 2 1.5 psig 143 ! 1.5 psig 2.

Fire Pump 1A 110 + 4/-3 psig None i

3.

Fire Pump 18 100 + 6/-0 psig None l

References:

1.

KNPP, ICP-8.4 2.

KNPP, SP-08-081, Step 6.4.2.a. P. 4 of 9 3.

KNPP, SP-08-081, Step 6.5.2.a. P. 5 of 9 3

NRC Resolution:

2.09 The above listed references were not provided the examiner either before the exam or with those comments. The tolerances on the setpoints appear to be instrument tolerances. The tolerances for full credit are +/-5 psig on the setpoints. Answer key changed accordingly.

Facility Comment:

2.11.a Additional answer could be "provides hydrogen entrainment (intimate contact)."

Reference:

KNPP, 50-35, P. 35-8 NRC Resolution:

2.11.a Agree, answer key changed to accept either correct answer to part a.

Facility Comment:

3.01.c Delete answer key item "..1.5'F.

Answer should be "1.0*F".

Reference:

KNPP, OTM IV-3.18 NRC Resolution:

l 3.01.c Agree, answer key changed to reflect correct answer.

Facility Comment:

3.02.c Answer "DSP (Dedicated Shutdown Panel)" should be acceptable associated with " Aux feed pump station".

Reference:

KNPP nomenclature usage NRC Resolution:

3.02.c Agree, additional correct answer is added to the answer key, either accepted for full credit.

Facility Comment:

3.03.c Assumption in question part c "(assume turbine feed pump speed control is in manual)" not applicable at KNPP.

4

NRC Resolution:

3.03.c Comment noted. Assumption will be removed from subsequent exams.

Facility Comment:

3.04.b Additional answers (RPS signals) should be allowed based on an operational perspective (i.e., low low S/G 1evel, OPdeltaT).

NRC Resolution:

3.04.b Disagree, comment is to general and with no supporting documentation, additional answers cannot be supported.

1 Fact 11ty Comment:

3.05 Question parts a and b are extremely confusing.

It is our contention that these two question parts be deleted.

NRC Resolution:

3.05 Upon further investigation, it is determined that the answers to both question parts, (a and b) are incorrect - a. False; b. True.

With sufficient knowledge of the trip circuit, the correct answer can be obtained. Answer key changed to a. False, b. True.

Facility Comment:

3.07 Answer should read:

1.

(New Subcooling Margin Monitor) a.

Tmar = Tsat - Thot b.

Thot = Highest of all core exit thermocouple temperature inputs for that train, i

Tsat = Saturation temperature based upon a pressurizer pressure j

or RCS pressure channel which ever is lower.

(From the hatest core exit thermocouple and the lowest pressure of either pressurizer or RCS.)

(

b.

Pmar = Pmin - Psat l

Pmin = Lowest of either a pressurizer or a RCS pres:ure detector Psat = Pressure based upon hotest core exit thermocouple l

(From the hotest core exit thermocouple and the lowest pressure of either pressurizer or RCS.)

l 5

If any system or input error occurs, both Spel and CETC displays c.

will flash.

(That a system or input error has occurred) 2.

(Old Subcooling Margin Monitor 0 a.

From four incore thermocouple RCS Wide Range Pressures (419)

Pressurization Range Pressures (429) b.

From four incore thermocouple RCS Wide Range Pressures (419)

Pressurization Range Pressures (429) c.

System or input failure

References:

1.

KNPP, ICCM Tech Manual, P. 5-13 and ICCM training notes 2.

KNPP, Logic E-2036 NRC Resolution:

3.07 1.

Above stated references not supplied to the examiner, however, answer key modified to accept this answer for the new system.

2.

Additional answers added to answer key and required for full credit.

Facility Comment:

3.08.a Answer key item a could read:

"R Scintillation R GM R Scintillation" i

Reference:

KNPP, OTM, P. V-2.3 NRC Resolution:

3.08.a Agree, the answer key modified and indicated response wfil be accepted for full credit.

3.08.b Answer should read:

1.

Automatic actions for R-11 and R-12 l

6 1

Containment Vent Isolation Signal Substeps include:

Containment Purge Supply and Exhaust Dempers close, Post LOCA Containment Isolation Valves close.

2.

Automatic actions for R-21 Containment Vent Isolation Signal Substeps include:

Containment Purge Supply and Exhaust Danpers close, Post LOCA Containment Isolation Valves close.

Reference:

1.

KNPP, Procedure, A-RM-45, P. 4 of 18 2.

KNPP, Procedure A-RM-45, P. 9 of 18 NRC Resolution:

3.08.b Agree, answer key changed to add " Post LOCA Containment Isolation Valves Close", for all three monitors as required response.

Facility Comment:

3.09.a Answer key item 4 should read " Turbine trip".

Reference:

KNPP, Logic E1621 NRC Resolution:

3.09.a Agree, answer key modified as indicated.

Facility Comment:

4.01.b Statement item #3 in question is worded in a fashion which we contend is paramount to a trick question

" Penalty points vice penalty minutes".

NRC Resolution:

4.01.b Coment noted, based on further investigation it was discovered that response 3 is also correct. Answer key chagned to accept 2 or 3 as l

correct response.

Facility Comment:

4.05.a 1.

Delete answer key item #4 - not in isolation step of reference.

l 2.

Additional answer should read "Close MSIV bypass valve".

Reference:

1.

KNPP, E-3, P. 4 2.

KNPP, E-3, P. 4 i

l 7

1

NRC Resolution:

4.05.a Agree, answer key modified to reflect both comments.

Facility Comment:

4.07.a 1.

Change answer key item #1 to read " Failure of two cg more control rods to....".

2.

Additional answer could include "during a ATWAS condition".

Reference:

1.

KNPP, Procedure E-CVC-35 2.

KNPP, Procedure, FR-S.1 NRC Resolution:

4.07.a Agree, answer key changed to reflect both of the above comments.

Facility Comment:

4.10 Rote memorization (committing specific numbers to memory) of Normal Operating Procedure steps is not encouraged at KNPP. We believe it is more in-keeping with a '.afe operating philosophy to train our operators to utilize procedures. This is especially true of in-frequently perforned normal operating evolutions such as 1/M startups.

NRC Resolution:

4.10 Parts a and c of this question refer to information found in the Precautions and Limitations section of the referenced procedure.

Knowledge of these items is essential for safe operation.

I Part b refers to information found within the steps of the procedure and is, therefore, not required knowledge.

Part b is deleted and the point value of 4.10 reduced to 1.5, the point valve for the section reduced to 24.0, and the point value of the exam reduced to 99.0.

8

W-s f

,g U. S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION FACILITY:

KEWAUNEE REACTOR TYPE:

PWR-WEC2 DATE ADMINISTERED: 86/06/24 EXAMINER:

JAGGAR. F.

M KT:) ("

V APPLICANT:

l'U4JI t V V I

INSTRUCTIONS TO APPLICANT:

Use separate paper for the answers.

Write answers on one side only.

Staple question sheet on top of the answer sheets.

Points for each question are indicated in parentheses after the question. The passing 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 APPLICANT'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY 25.00 25.00 1.

PRINCIPLES OF NUCLEAR POhTR PLANT OPERATION, THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW 25.00 25.00 2.

PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS 1

25400

_25.00 3.

INSTRUMENTS AND CONTROLS 0

- V00 4.

PROCEDURES - NORMAL, ABNORMAL, i

/

EMERGENCY AND RADIOLOGICAL CONTROL 0.0n 0.00 TOTALS

/

z FINAL GRADE 4

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

NAS..9,03PY APPLICAYT S SIGtTAfD'RE -

I l

l

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NRC RULES Ale GUIDELINES FOR LICENSE EXAMINATIONS During the administratten of this exanteaties the following rules apply:

1.

Cheating en the enemination seems an automatic dental of your application and could result in eers severe penalties.

2.

Restroom trips are to be lietted and only one candidata at a time may t

leave. You must avoid all contacts with anyone outside the examination roes to avoid even the appearance or possibility of cheating.

(

Use' black ink or dark pencil o_nly to facilitate legible reproductions.

3.

l 4.

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

5.

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

6.

Use only the paper provided for answers.

7.

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

8.

Consecutively nuber each answer sheet, write "End of Category

" as appropriate, start each category on a new page, write Joni og sTde of the paper, and write "Last Page" on th 7 east answer sheet.

9.

Ikauber each answer as to category and neber, for example,1.4, 6.3.

10. Skip at least three lines between each answer.

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

12. Use a;,breviations only if they are commonly used in facility literature.

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

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

I

15. Partial credit say be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AN0 00 NOT LEAVE ANY ANSWER BLANK.

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

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

18. When you complete your examination, you shall:

l a.

Assemble your examination as follows:

(1) Exam questions on top.

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

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

b.

Turn in your cocy of the examination and all pages used to answer the examination questions.

c.

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

d.

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

d 1:

PR.INCIPMR OF NUCLEAR POWER PLANT OPERATION.

PAGE 2

THERMODYNAMICS. HEAT TRANSnut AND FLUID FLOW l

1 l

QUESTION 1.01 (2.00) l a.

What two conditions must exist for subcritical multiplication to l

occur?

l b.

What is a 1/M plot and when is it used?

QUESTION 1.02 (3.00) l l

a.

Provide TWO removal and TWO production schemes for Xenon 135 in a critical reactor.

(Equation form is acceptable, t

but not required.)

(1.5) b.

Approximately how many hours does it take for Xenon to reach equilibrium concentration after the reactor is brought to full power from a Xenon free condition?

(0,5) c.

What is the approximate reactivity, in PCM, for:

I 1.

100% equilibrium Xenon concentration?

(0.5) 2.

100% peak Xenon concentration?

(0.5)

QUESTION 1.03 (3.00)

Explain the terms beta bar and beta bar effective.

Your answer a.

should include which term is smaller in magnitude AND why.

l l

b.

Explain BOW and WHY the above mentioned terms will vary, AND how they will affect reactor response throughout cycle life.

QUESTION 1.04 (2.00)

With a stable positive period of 80 seconds, at a power level of 10 MW :

a.

What is the startup rate ?

b.

What is power level after 1 minute ?

NOTE: Show all calculations

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

1.' PRINCIPMS OF NUCLEAR POWER PLANT OPERATION..

PAGE 3

THERMODYNAMICS. HKAT TRANSFER AND FLUID FLOW QUESTION 1.05 (1.50)

How will changing the following factors affect the Moderator Temperature Coefficient? (Limit your answer to becomes MORE NEGATIVE, LESS NEGATIVE or DOES NOT CHANGE.the MTC.)

O M T~

c.

The JMMF is inadvertently injected into the RCS.

b.

The core ages from BOL to EOL.

c.

The RCS is cooled down from 550 F to 450 F.

QUESTION 1.06 (3.00)

During a startup the reactor is suberitical at 3000 CPS on the Source Range Instruments when a steam dump valve fails open.

a.

EXPLAIN what happens to reactor power and Tave. Continue your explanation until stable conditions are reached with no operator action. (Assume the reactor is undermoderated, at BOL and no reactor trip occurs.)

b.

Assume the same transient as above occurs at EOL.

EXPLAIN any differences in the power /Tave response and final stable conditions as a renult of the increased burnup.

QUESTION 1.07 (2.00)

How is the margin to DNB affected by a DECREASE in each of the following.

Consider each independently. (Limit your answer to increase, decrease, remain the same.)

a.

Reactor power.

b.

RCS flow.

c.

Tcold.

d.

Pressurizer pressure

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

l

1*.

PitINCIP N OF NUCLEAR POWER PLANT OPERATION.

PAGE 4

THERMODYNAMICS. HEAT TRANSnx AND FLUID FLOW QUESTION 1.08 (2.50)

a. List the 3 conditions necessary for brittle fracture to occur in metal.

(1.5)

b. BRIEFLY EXPLAIN why the exposure of the reactor vessel to fast neutron flux increases the value of the Nil-Ductility Temperature (NDT).

(1.0)

QUESTION 1.09 (1.50)

A variable speed centrifugal pump is operating at 1/4 rated speed in a closed system with the following parameters:

Power : 300 Kw Famp delta P = 50 psig Flow = 800 gpm What are the new values for these parameters when the pump speed is increased to full rated speed?

j l

QUESTION 1.10 (3.00) a.

If steam goes thraugn a throttling process, specifically as in a leak from the main steam high pressure header to atmosphere, will the rollowing parameters Increase, Decrease OR Remain the same? (No explanation is required)

(2.5) i

1. Enthalpy (h)

2. Pressure l

3. Entropy (s) i 4.

Specific volume (v)

5. Temperature l

b.

State whether the steam will be subcooled, saturated or i

superheated as it leaks out?

(0.5) l l

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

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1 PEINCIPT.RR OF NUCfRAR POWER PLANT OPRRATION.

PAGE 5

THERMODYNAMICS. REAT TRANSFER AND FLUID FLOW QUESTION 1.11 (1.50) a.

Define "Available NPSH."

b.

The faster a centrifugal pump rotates, the its i

required NPSH.

1 c.

What is the term used to describe a centrifugal pump when it is pumping at maximum capacity?

l 4

7

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

2:

P ANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 6

QUESTION 2.01 (2.50)

The following concern the Auxiliary Building Special Ventilation (ASV) system:

a.

What THREE conditions automatically actuate the ASV system?

(Setpoints not required.)

(1.5) b.

How are the ASV exhaust charcoal filters protected from fire?

(0.5) c.

How are personnel protected from being trapped between two airlock doors in the event of a power failure, during which the door interlocks fail in the locked position?

(0.5)

QUESTION 2.02 (1.00)

What is the purpose of the sodium hydroxide (NaOH) which is injected into the containment by the containment spray system upon automatic actuation?

QUESTION 2.03 (1.50)

State THREE automatic actions which occur within the service water system upon receipt of a safety injection signal.

QUESTION 2.04 (3.50) a.

State FIVE conditions which will cause an automatic trip of a feedwater pump.

(Setpoints not required.)

(2.5) b.

Why is the feedwater piping equipped with a recirculation path from each feedwater pump to the main condenser?

(1.0)

QUESTION 2.05 (2.00)

State FOUR separate safety-related loads (pumps or heat exchangers serving different functions) which are cooled by the component cooling water system.

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

2*

PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 7

QUESTION 2.06 (2.00)

State the electrical bus or motor control center which DIRECTLY supplies power to each of the following components:

Example:

Service water pump 1B1--->4160V bus 1-6 a.

Residual heat removal pump 1A b.

Condensate pump 1A c.

Auxiliary feedwater pump 1B d.

Centainment spray pump 1B e.

Feedwater pump 1B f.

Normal supply to inverter BRA-112 (preferred source to instrument bus IV.)

g.

Fire pump 1B h.

Component cooling pump 1A QUESTION 2.07 (2.00) l a.

During normal operation, why should the position (1A or 1B) of the i

boric acid tank level transmitter selector switch l

in the control room match the open boric acid tank to SI pumps suction isolation valve (SI-1A or SI-1B)?

(1.25) b.

How does an operator in the control room know that the selector switch position is NOT compatible with the positions of the manual isolation valves (SI-1A and SI-1B)?

(0.75)

QUESTION 2.08 (2.00)

(

During plant startup from the cold condition, hydrazine is used as an j

oxygen scavenging agent.

How is oxygen controlled during normal power operations?

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

2:

PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 8

l QUESTION 2.09 (2.50)

What is the fire water header pressure at which each of the fire pumps and the jockey pump should automatical..y START on pressure decrease, AND automatically STOP on subsequent pressttre increase?

NOTE:

If no automatic start or stop feature is pro'rided, then so state.

QUESTION 2.10 (3.00)

State TWO reasons that bypass flow is provided around the pressurizer spray valves PS-1A and PS-1B.

QUESTION 2.11 (3.00) a.

When the Chemical and Volume Control System (CVCS) is operating in the DILUTE mode, primary water is injected into the VCT inlet line.

Why is it advantageous to inject at this location rather than at the VCT outlet?

b.

At what point (s) is primary water injected when CVCS is operating in the ALTERNATE DILUTE mode?

c.

When operating in the BORATE mode, why is boric acid NOT injected into the VCT inlet line?

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

3',

INaTRUMENTS AND CONTROLS PAGE 9

QUESTION 3.01 (3.00)

The reactor is at 80% power with rod control in automatic.

Assume a rapid 10% load rejection occurs:

Briefly EXPLAIN how a rod insertion signal is generated by the rod a.

control system:

1.

power mismatch circuit?

(1.0) 2.

temperature mismatch circuit?

(1.0) b.

What determines the rod insertion rate?

(0.5) c.

When will inward rod motion automatically cease?

(0.5)

QUESTION 3.02 (3.00) a.

A break in the reference leg in the pressurizer level indicator will cause the indicated level to be higher than the actual level.

TRUE or FALSE?

(0.5) b.

What would a low temperature alarm on TE-421 (surge line) indicate?

Assume that the plant is at steady state and the instrument has not failed.

(1.0) c.

List the location (s) that has/have indication for LT-433 Pressurizer Level t cold calibrated).

(1.5)

QUESTION 3.03 (3.50) a.

What are the three plant parameter input signals used by the three element Steam Generator Level Control System?

(Do not include turbine impulse pressure or steam pressure.)

(1.5) b.

What is the purpose of the turbine impulse pressure signal used in the S/G Level Control System?

(0.5) c.

Considering only the Steam Generator Level Control System, indicate whether feedwater flow would initialy INCREASE, DECREASE, or NOT CHANGE if the controlling S/G pressure transmitter failed high during 50% power operation.

Briefly

^

--- " -^-'-^'

explain your answer.

(1.5)

._ __.,munu.7

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

l

3.

I STRUMENTS AND CONTROLS PAGE 10 QUESTION 3.04 (2.50)

The Reactor Protection System is designed so that a Turbine Trip will cause a Reactor Trip above 10% power.

a.

Why is the system designed to do this?

(1.0) b.

Provide two Reactor Protection signals that would actuate to give protection in the event that the Turbine Trip / Reactor Trip did not operate on a turbine trip from full power.

(0.5) c.

State the TWO ways that the Reactor Protection System senses that a turbine trip has occured?

(1.0)

QUESTION 3.05 (1.50)

Indicate whether the following statements concerning operation of the Reactor Trip (RT) and Bypass (BY) breakers are TRUE or FALSE.

a.

If one train is placed in test while the other train's bypass breaker is closed, then both reactor trip breakers and both i

bypass breakers will trip.

b.

If it is attempted to close both bypass breakers at the same time, then both bypass breakers will trip but the reactor trip breakers will remain closed.

c.

A train A reactor trip signal will trip RTA and BYA breakers.

t 1

l QUESTION 3.06 (2.25) 1 a.

State the THREE reasons for establishing a Rod Insertion Limit (RIL).

(1.5) b.

In addition to the RIL and indication, state THREE other uses for Auctioneered High Tavg.

(0.75)

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

3*

INSYRt4fIENTS AND CONTROLS PAGE 11 QUESTION 3.07 (2.00) g yk gQ.g e The following concern the Subcooled Margin Monitor. perv ns 4Luo RvL n

• e 6 M

• o.

From where do the inputs to the Temperature Margin originate?

(0.5) b.

From where do the inputs to the Pressure Margin originate?

(1.0) c.

What is indicated by a flashing meter display?

(0,5)

QUESTION 3.08 (2.75)

State the type of detector used in the following Radiation Monitoring a.

Channels.

1.

R-11 Containment Vessel or Vent Air Particulate Monitor 2.

R-12 Containment Vessel or Vent Radioactive Gas Monitor 3.

R-21 Containment System Vent Activity Mo.11 tor (0.75) b.

State the Automatic actions associated with a. high radiation signal from the above listed radiation monitors.

(1.0)

List the places the R11/R12 samples can be (.irected after c.

being counteu.

(1.0)

QUESTION 3.09 (2.00)

State the emergency conditions that will automatically start the a.

Emergency Diesel Generators.

b.

State the engine malfunctions that will trip the Emergency Diesel automatically.

J

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

3/

INSTRUMENTS AND CONTROLS PAGE 12 QUESTION 3.10 (2.50)

Two loading sequences, Blackout and Safety Injection, are provided for loading of the Emergency Diesel Generators.

The following pertain to the interaction between the two sequences.

c.

How is the SI sequence affected when a blackout occurs in the middle of the SI sequence?

(1.0) b.

How are the Blackout sequence and loads alrea.dy started affected when an SI sequence occurs in the middle of the Blackout sequence?

(1.5) l I

l l

l l

l l

l

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

4:

PROCEDURES - NORMAL. ABNORMAL. EMERGENCY AND PAGE 13 RADIOLOGICAL CONTROL QUESTION 4.01 (1.50) c.

The indicated AFD shall be considered outside of its target band when or more operable excore channels are indicating the AFD outside the target band.

(0,5) eneL b.

Whichdof the following statements concerning the AFD requirements is correct, according to Technical Specifications?

(1.0) 1.

Above 90%, within 30 minutes of going outside the target band; either restore indicated AFD to within the target band or reduce power to less than 90%.

2.

If the axial flux difference alarms are out of service, the axial flux difference shall be logged every hour for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and half-hourly thereafter until the alarms are returned to operable.

3.

Below 15% power, penalty points are accumulated at one half point for every minute outside the target band.

4.

Power level shall not be increased above 15% unless the AFD is within the target band.

QUESTION 4.02 (2.00)

What are the FOUR conditions required by Technical Specifications to be observed that ensure the hot channel limits will be met during full power operation?

QUESTION 4.03 (3.50)

The following concern E-0, Reactor Trip or Safety Injection procedure.

a.

How is a reactor trip verified?

(1.0) b.

List the THREE conditions that will result in automatic main steamline isolation, include setpoints.

(1.5) c.

Define ADVERSE containment.

(1.0)

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

PROCEDkJWR - NORMAL. ABNORMAL. EMERGENCY AND PAGE 14 4.

RADIOLOGICAL CONTROL QUESTION 4.04 (2.00)

The following concern E-0 Quick Reference Foldout information.

a.

State the RXCP trip criteria, b.

State the SI actuation criteria.

QUESTION 4.05 (2.00)

The following concern E-3.

Steam Generator Tube Rupture procedure, m.E),bJo a.

How is the ruptured steam generator isolated, +the. th;a closing the affected MSIV?

b.

If the MSIV on the ruptured steam generator cannot be fully closed, how is radioactive release minimized while cooling down the RCS?

QUESTION 4.06 (2.00)

List the Critical Safety Function Status Trees ip order of priority (use number 1 as highest priority).

C-d4ma. ~+ MW QUESTION 4.07 (4.00) a.

State the FOUR separate conditions which require emergency boration.

(Indications of the condition not required.)

b.

What are the FOUR immediate operator actions required by the emergency boration procedure E-CVC-35?

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

4.

PitOCEDUPM - NORMAL. ABNORMAL. EMERGENCY AND PAGE 15 RADIOLOGICAL CONTROL QUESTION 4.08 (3.00)

Normally the RCP #1 Seal Bypass line shall remain closed unless either of two alarms are approached.

The bypass line should then be opened if FOUR conditions are satisfied.

According to N-RC-36A, Reactor Coolant Pump Operation procedure What are the TWO alarm conditions that would require opening the a.

bypass?

(1.0) b.

What are the FOUR conditions that must be met prior to opening the bypass valve?

(2.0)

QUESTION 4.09 (2.50)

Match the following radiation terms in Column A to the correct a.

definition in Column B (for example 5. F)

(2.0)

Column A Column B 1.

Chronic a.

Physical effects of radiation on the human body.

2.

Acute b.

Dose of radiation received over a short 3.

Genetic period of time.

4.

Somatic c.

Dose of radiation received over a extended period of time, d.

Internal exposure of radiation.

e.

Effects of radiation exposure which affect offspring.

b.

TRUE or FALSE 7 For the same amount of radiation (dose) received, the biological effects are greater if it is received in a relatively short (0.5) period of time.

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

4.

PROCEDURRE - NORMAL. ABNORMAL. EMERGENCY AND PAGE 16 RADIOLOGICAL CONTROL QUESTION 4.10 (2.50)

The following concern N-CRD-49B, Reactor Startup procedure.

a.

What is the maximum allowable startup rate?

(0.5) b.

What are the intervals required to stop rod motion for an inverse count rate plot?

Include WHEN these intervals are reduced, and WHAT the new interval is.

(1.0)

What operator action is required if criticality is NOT attained c.

at the calculated ECP plus 400 PCM position?

(1.0)

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

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

EQUATION SHEET Cycle efficiency = (Net wik f = ma v = s/t out)/(Energy in) 2 s = V,

• 1/2 at w = ag 2

& =.X A = 114 A=Ae I

KE = 1/2 av a = (Vf - l )/t g

3 PE = agn

• = e/t i = &n2/t;jg = 0.693/t1/2 Vf = V,

• at 1/2*" " U

• m 1

2 4,y j A=

((c/2I * ( *bIl t0 1

4

-Ex c.E = 931 ma m=V Ao u

Q = mCa st I = I = "*

~

3 Q = UA4 7 I = I,10~* O '

Pwr = W d y

TVL = 1.J/u HVL = -0.593/n P = 7 10,8""IE) o..

?=Pe

SG = 5/(1 - X,ff) o SUR = 25.06/7 G = 5/(1 - K,ffx) x SUR = ZSo/t + (s - o)T G;(1 - K,ff3) = G II ~ *eff2) 2 T = (L*/s) + ((3 - oY ia]

M = 1/(1 - X,ff) = G;/G, M = (1 - X,ff,)/(1 - X,ff))

T = 1/(s - 3)

SOM = ( - X,ff)/K,ff T = (3 - o)/(Is) tr = 10 sec:ncs a = (K,ff-1)/K,f=

• X,fdK,ff

-I I = 0.1 seconds

= ((t*/(T X,ff)] + (I,ff (I + IT)]

/

Idlt"I#

P = (aV)/(3 x 1010)

I;d) 2,2 2 7#

22 2

R/hr = (0.5 CI)/c (,,g,73)

R/hr = 6 CI/c2 (f,,g)

= :N Miscallaneous C:nverstens Water Par weters 10 I curie = 3.7 x 10 gas 1 gal. = 8.345 lem.

1 29 = 2.21 lem 1 gal. = 3.78 lt:ars Ino=2.54x103Stu/hr 1 f9 = 7.18 gal.

1 a = 3.41 x Ico Stu/hr 3

Oensity = 62.4 10m/f lin = 2.54 cm Density = 1 gm/c9 Y = 9/5*C + 32 j

Heat of vacorizat, ion = 970 Stu/lem

• C = 5/9 (**-32) seat of fusion = 144 Scu/lem I STU = 778 ft-lbf i

I 1 sca = 14.7 psi = 29.9 in. Hg.

l I ft. H O = 0.4335 luf/in.

2

1.

PRINCIPf2R OF NUCTRAR POWER PLANT OPERATION.

PAGE 17 THERMODYNAMICS. HEAT TRANSFER AND FLUID FLOW ANSWERS -- KEWAUNEE

-86/06/24-JAGGAR, F.

MASTERCOPY ANSWER 1.01 (2.00) a.

Source neutrons must be present [0.5] and there must be fuel in the vicinity of the source. [0.5]

b.

The 1/M plot is a plot of rod position or fuel assemblies loaded vs.

1/M (1-Keff). [0.5] It is used to predict when criticality will occur during fuel loading and during approaches to criticality using control rods or boron dilution.t-[ OR Aw eegusled b EencJk'" Qervuor.

l 0.5]

3 t

REFERENCE l

KNPP Tng Manual pI-4.5 - I-4.11.

ANSWER 1.02 (3.00) a.

PRODUCTION Iodine decay.

Direct yield from fission.

REMOVAL Neutron absorption (burnout)

Xenon decay

[0.375 ea)

[ Correct equation also acceptable]

b.

50 +/- 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.

[0.5]

c.

1.

-2555 t: -2EED ;; ? M H b b*P'**

2.

1.8 times value in C.1 (-4599 to -4788 pcm)

[0.5 ea]

REFERENCE W.C. NPS-229, Chapter 3, pp. 3-50, 3-51.

Core Physics, figures A.27 & A.29.

CNTO Core Control, p 4-14, -17; Kewaunee Rx Data Book fig 9.2, 9.1.2.

MASTBCOPY

1 l

1.

PR'INCIPr.un OF NUCf.uAR POWER PLANT OPERATION.

PAGE 18 l

THERMODYNAMICS. MAT TRANSFER AND FLUID FLOW ANSWERS -- KEWAUNEE

-86/06/24-JAGGAR, F.

I l

I ANSWER 1.03 (3.00) c.

Beta bar is the average delayed neutron fraction or the weighted average fraction for the different fissionable materials present.

[0.25]

Beta bar effective is the effective fraction [0.25] and is smaller [0.5] as it is the product of beta bar and an importance fac-tor.

The importance factor is less than one as delayed neutrons are less likely to cause fission. [0.5]

(Will accept an explanation of how the importance factor is affected by Fast Fission and Non-leakage factors) b.

Esta bar and Beta bar effective will decrease in value over cy-cle life [0.5] due to the changing concentrations of the differ-ent fissionable isotopes in the core. [0.5]

Smaller values of the effective fraction means that the reactor period will be smaller or the reactor will respond quicker for a given react-ivity change, as the core ages.

[0.5]

REFERENCE KNPP Tng Manual, pI-58.

ANSWER 1.04 (2.00)

a. SUR = 26/T = 26/80 =.325 DPM

[1.0)

b. Pf = Pi*10E(1 min.* 0.325) = 10 (2.1) = 21.1MW

[1.0]

l REFERENCE KNPP pI-5.9 - I-5.13.

ANSWER 1.05 (1.50) a.

LESS NEGATIVE b.

MORE NEGATIVE c.

LESS NEGATIVE

[0.5 each]

REFERENCE CNTO Core Control, p3 3-21.

1.

PRINCIPhER OF NUC MAR POWER PLANT OPERATION.

PAGE 19 THERMODYNAMICS. HEAT TRANSnx AND FLUID FLOW ANSWERS -- KEWAUNEE

-86/06/24-JAGGAR, F.

ANSWER 1.06 (3.00)

The excess steam flow causes Tave to decrease and insert a.

positive reactivity. Power increases [0.5].

At the POAH, negative reactivity is inserted from FTC [0.5] and Tave decrease slows (0.2].

Power rise and cooldown continues until reactor power equals steam demand [0.3].

b.

Power rise rate higher and time to reach POAH shorter [0.5] due to smaller beta-bar and more negative MTC [0.5].

Final power is the same but temperature will be higher (still below no-load Tave) [0.5]

REFERENCE CNTO Core Control, p3 3-23.

ANSWER 1.07 (2.00) a.

Increase b.

Decrease c.

Increase d.

Decrease

[0.5 ea.]

REFEREFCE CNTO TIArmal Bydraulic Principles, pl3-23,

-24.

ANSWER 1.08 (2.50) a.

1. Tensile Stress

[0.5]

2. Temperature below NDT

[0.5]

3. Sufficient sized surface defect [0.5]

b. The collision of fast neutrons with the metal of the reactor vessel changes the structural placement of the metal atoms, causing a change in the physical properties of the metal.

[i.0]

REFERENCE CNTO Thermal Hydraulic Principles, pl3-60,

-61.

1.

PRINCIPMR OF NUCTRAR POWER PLANT OPERATION.

PAGE 20 TERMODYNAMICS. MAT TRANSFER AND FLUID FLOW ANSWERS -- KIWAUNEE

-86/06/24-JAGGAR, F.

ANSWER 1.09 (1.50) 3

=

19.2 Mw

[0.5)

Power (2) = Power (1)(N2/N1) cubed = 300x(4) 2 2

800 psig

[0.5]

Delta P(2) = Delta P(1) (N2/N1)

= 50x(4)

=

3200 gpm

[0.5]

Flow (2) = Flow (1) (N2/N1)

= 800x(4)

=

REFERENCE CNTO Thermal Eydraulic Principles, p10-37.

ANSWER 1.10 (3.00) a.

1. Same

2. Decrease 3.

Increase 4.

Increase

5. Decrease b.

Superheated

[0.5 ea.]

REFERENCE CNTO Thermal Hydraulic Principles, p8 8-28; Steam Tables.

ANSWER 1.11 (1.50) a.

The difference between the pump suction pressure and the saturation pressure of the fluid being pumped.

b.

Greater c.

Pump runout

[0.5 ea.]

REFERENCE CNTO Thermal Hydraulic Principles, p10-43,

-44,

-54.

2.

PL' ANT DESIGN INCLUDING SAFETY AND EMERn1ENCY SYSTEMS PAGE 21 ANSWERS -- KEWAUNEE

-86/06/24-JAGGAR, F.

ANSWER 2.01 (2.50) 0 R St h M e m 4 *I-o.

1.

Safety Injection 7

2.

High temperature in a steam exclusion area.

3.

High radiation in the Aux. Building vent stack (R-13 or R-14).

[3 4 0.5 each)

(1.5) b.

Water deluge system provided for each filter assembly,

[ automatically actuated by high temperature of 200F sensed by a heat detector (1 out of 2) located above the charcoal filters.

Individual fog nozzles are heat actuated.)

(0.5) c.

Interlock may be overridden by use of a key located within each set of doors.

(0.5)

J REFERENCE i

Kewaunee, SD 14, PP. 5-15 ANSWER 2.02 (1.00)

To protect austenitic stainless steel components within containment from the possibility of stress corrosion cracking during the period following a LOCA.

OR --- To maintain the solution used during the recirculation phase (Either answer accepted for full credit.

^OR.-- - Re~va.4 roam a. %,m %@ 6)A< < is rad 1'J-at a pH of >/= 7.0.

REFERENCE Kewaunee,SDp,P.

1 ANSWER 2.03 (1.50) 1.

System isolates into two headers (separation valves SW-3A and -3B shut).

2.

P~414 r; buildi..

1 lati. c;1 cc;

'L -10a and -Auma open, 22

revie"-1

closcd.

3.

All four service water pumps start.

4.

All four rotating strainers start.

[3 required @ 0.5 ea.]

REFERENCE Kewaunee, SD 2, P.

2 J' S W 4. CC. he=+ <AH.e s eg.cn C w 11W M (0

(,, S W M.b n o n C F C. % A s op.cn ( ss nog A -0)

~), 6tce.\\ (sen erd ~ DA) bak eYM1*-on4 led e9 en hW-3cl A

2.

PCANT DESIGN INCLUDING SAFETY AND EMERMNCY SYSTEMS PAGE 22 ANSWERS -- KEWAUNEE

-86/06/24-JAGGAR, F.

ANSWER 2.04 (3.50) a.

1.

Loss of condensate pump (if the number of condensate pumps running equals the number of feedwater pumps running).

2.

Low lube oil pressure.

3.

Low suction pressure (after two minute timer times out).

4.

HI-HI level in either steam generator (2/3 9 60% on 1/2 detectors).

5.

Safety injection 6.

Respective bus (1-1 or 1-2) undervoltage.

7.

Bus lockout.

[5 required 9 0.5 each]

b.

Prevent feedwater pump overheating and cavitation during conditions of low flow (by assuring a minimum flow through the pump.

Valve opens at 2200 gpm v and closes at 2600 rpm ^.)

[1.0)

REFERENCE Kewaunee, SD SA, PP. 7-10 ANSWER 2.05 (2.00) 1.

Safety injection pumps.

2.

Residual heat removal pumps.

3.

Residual heat exchangers.

4.

Containment spray pumps.

[0.5 ea.]

REFERENCE Kewaunee, SD 31, 1 & 2; OP-XK100-19 & -20 ANSWER 2.06 (2.00) a.

4160V bus 1-5 b.

4160V bus 1-3 c.

4160V bus 1-6 d.

480V bus 1-61 e.

4160V bus h l-1 f.

480V MCC 1-52C g.

480V bus 1-62 h.

480V bus 1-51

[0.25 each]

REFERENCE Kewaunee, Dwgs E244, E233, E235

2.

P[lNT DESIGN INCLUDING BAFETY AND EMERCRNCY SYSTEMS PAGE 23 ANSWERS -- KEWAUNEE

-86/06/24-JAGGAR, F.

h OW E u,0 a\\se n u.ep gy yp,,,,g) wi occ=r.

ANSWER 2.07 (2.00) a.

This interlocks the level channels of the sol noted boric acid tank with the valves required to transfer thy suction of the SI pumps from the boric acid tank to the RWST.

(1.25) b.

A window on the safeguards ready status board will light.

(0.75)

REFERENCE Kewaunee, SD 33, P. 2 and checklist N-SI-33-CL, PP. 1 and 11 ANSWER 2.08 (2.00)

A hydrogen overpressure is established in the VGT which maintains a high hydrogenequilibriumconcentrat(oninthereactorcoolantCkceudi If asswphon a sMA A 9s<sim.

o c 4,a s Sau J4, REFERENCE

'"'O *W* M'5Un# M CA' N d O*A i

Kewaunee, SD 35 P.

3 i

ANSWER 2.09 (2.50) 128 psig - Jockey pump starts 110 psig - Fire pump 1A starts 102 psig - Fire pump 1B starts

[3 @ 0.5 cach]

Fire pumps 1A and 1B - No automatic or remote shutdown capabilities

[0.5].

Jockey pump - Auto shutdown at 143 psig

[0.5].

MM 4

• h4 presawm are 1 sps b REFERENCE Kewaunee, Dwg. E1619 Sheet 1 of 3 ANSWER 2.10 (3.00) 1.

To reduce thermal shock and thermal stresses when the spray valves open.

2.

To help maintain uniform chemistry in the pressurizer.

3.

To help maintain uniform temperature in the pressurizer.

[2 required @ 1.5 each]

REFERENCE Kewaunee, SD 36, P. 7

2.

PLANT DESIGN INCLUDING SAFETY AND EMERMNCY SYSTEMS PAGE 24 ANSWERS -- KEWAUNEE

-86/06/24-JAGGAR, F.

i w,n ghoeu<p+8 preund4 h of et ANSWER 2.11 (3.00) 4,,3 g.,

a.

Provides desassing of primary water added to system prior to actually entering reactor coolant system.

[1.0]

b.

VCT inlet line, and VCT outlet (charging pumps suction).

[1.0) c.

The boron would eventually clog the VCT inlet spray nozzle; OR boric acid is more quickly introduced into the RCS when injected at the charging pumps' suction.

[Either response worth 1.0]

REFERENCE Kewaunce, Dwg. X-K100-35; CAF l

i l

3.

INnTRUMENTS AND CONTROLS PAGE 25 ANSWERS -- KEWAUNEE

-86/06/24-JAGGAR, F.

ANSWER 3.01 (3.00) a.

1.

Turbine impulse pressure decreases [0.5] in respect to N-44, causing a rate of change signal which drives rods in. [0.5]

2.

Turbine impulse pressure decreases (Tref) [0.5] below Tavg causing a temperature mismatch error which drives rod in. [0.5]

b.

The magnitude of the power mismatch rate signal PLUS the temperature mismatch signal.

(0,5) c.

When Tavg and Tref are within,

'F.

(0.5)

REFERENCE KNP OTM IV-3.4, 3.5 ANSWER 3.02 (3.00) a.

True (0.5) b.

A low temperature would indicate insufficient spray flow r

(1.0)

(through the bypass valves),f c.

Control Room [0.5]

OR. bbMd SMe I

Aux feed pump station [0.5]

Charging pump station [0.5]

REFERENCE KNP Annunciator Response Book 47021-21 ANSWER 3.03 (3.50) a.

1.

Feedwater Flow.

2.

Steam Flow.

3.

S/G Water Level. (Error signal)

[3 @ 0.5]

b.

To provide a programmed level setpoint.

[0.5]

c.

Increase.

[C.75]

The failed high steam pressure transmitter causes the steam flow input to SGWLC to increase.

[0.75]

f

.n

3.

15ISTRUMENTS AND CONTROLS PAGE 26 ANSWERS -- KEWAUNEE

-86/06/24-JAGGAR, F.

REFERENCE KNP OTM IV-10.4, 10.5 ANSWER 3.04 (2.50)

(Because the turbine serves as the heat sink to the reactor),

a.

a reactor trip follows a turbine trip to minimize the RCS pressure transient (and/or resulting safety valve operation).

(1.0) b.

- High pzr pressure

- OT Delta T (0.5) c.

- All turbine stop valves shut

- Auto stop oil pressure low (< 45 psig)

[0.5 each]

REFERENCE KNP OTM IV-11.14 ANSWER 3.05 (1.50) a.

TREE EI*d2 C b.

fab 6E h 6 c.

FALSE

[0.5 ea.]

REFERENCE KNP OTM IV-11.2, 11.3, 11.21, W Logic Diagram ANSWER 3.06 (2.25) a.

1.

Provides adequate shutdown margin during a steam rupture accident.

2.

Limit consequences of an ejected rod.

3.

Limit the effect that radial flux mismatch has on hot channel factors.

[3 @ 0.5 each]

b.

1.

Rod control 2.

Steam dump 3.

Pressurizer level

[3 @ 0.25 each]

REFERENCE Kewaunee, KNP OTM IV-6.3; Figure IV-6.6

3.

INSTRUMENTS AND CONTROLS PAGE 27 ANSWERS -- KEWAUNEE

-86/06/24-JAGGAR, F.

ANSWER 3.07 (2.00)

• p.

P kss a j

a From our incore thermocouples '21 2?, ?1

?f f (0.5)

E RCS widerange) and Pressurizer Pressure (narrow range)

[2 0 0.5 each]

(1.0) c.

A (software) diagnostic failure (0.5)

See nw sst,~e.n ew one.ds REFERENCE Kewaunee, SD 36, PP. 13-15 ANSWER 3.08 (2.75)

R-11-(PhotoMultiplier)-scintillationcrystal a.

R GM Tube R-21 -(B, eta sensitive) scintillation detector p.22]

[0.25 ea.]

b.

All three monito g clos containment purge supply and r

exhaust valvesF8n a Tah ' diation signal.

(CV31125, r

CV31123, CD-3g06, and CD-34033).

(1.0)

c. /. Containment eitguxiliary Building Vent SystemCa.t)

(1.0)

- *\\s o d*1,3,

.,4-Loc A REFERENCE Kewaunee, SD 45, PP. 15-21 Crd hi m M L

% Wludi Co.33) l l

l ANSWER 3.09 (2.00) l a.

1.

Loss of voltage on the 4160V Bus.

2.

Low voltage for four minutes on the 4160V Bus.

l 3.

SI signal.

1:he=[ trip.

[4 @ 0.25 each]

4.

Turbine gu. a ts:

b.

1.

Overspeed 2.

Low Jacket Water Pressure c.13 C"-+

1. [+3 3.

Low lube oil pressure

@ <ih-G6-each]

4.

.'.ctu: tier ^f 02 d:

Fir: Protection 6 A 4 M*Ib M * * ""

• ba*"

REFERENCE M T"#d" Kewaunee, SD 42. PP. 31, 34 R -o /n, 76V-13.[/ c.o -st ra Sco-3M*13 ] p q

Rav-x gov 3,/ cv -stn4 % WJ gav -s/c o -Po*

R - 21 g rW-I fcMit 2.5" p y.Lpp y l

TA V -.(2. / c. o ~N8 33 gt h) L4 [ c N - 1 I @ 3 N., E N % f-A gV - y [ c.,0 - HooG 3

,--.-,e e.-

.. - - - - - -. ~

.---._,-n.,.,-,4.

w

\\

3.

ThisTRUMENTS AND CONTROLS PAGE 28 ANSWERS -- 10iMAUNEE

-86/06/24-JAGGAR, F.

ANSWER 3.10 (2.50) j a.

The SI sequence is stopped [0.5] and returned to zero [0.5].

The Blackout sequence in gr set [0.5] and the SI sequence is b.

initiated from Step zero.

Loads already started are shed and restarted on the SI sequence [1.0h c,S*

REFERENCE Kewaunee, SD 42, PP. 50-51 l

l t

l l

j 4.

Pit 0CEDUFM - NORMAL. ABNORMAL. EMERGENCY AND PAGE 29 RADIOLOGICAL CONTROL ANSWERS -- KEWAUNEE

-86/06/24-JAGGAR, F.

I AESWER 4.01 (1.50) n.

2 (0.5) b.

2 erJ (1.0) f REFERENCE Kewaunee, TS, P.

3.10-4,5 l

ANSWER 4.02 (2.00) l l

1.

Control rods in a single bank move together with no individual rod differing by more than 12 steps from demand position >/= 85% power.

2.

Control rods are sequenced with proper overlap.

3.

Control rod insertion limits met.

4.

Axial power distribution limits in specification.

[4 @ 0.5 each] (2.0)

REFERENCE Kewaunee, TS 3.10-13 j

ANSWER 4.03 (3.50) a.

1.

Reactor trip and bypass breakers-open 2.

Neutron flux - decreasing 3.

Rod position indicators - zero 4.

Rod bottom lights - lit

[4 @ 0.25 each] (1.0) b.

1.

HI-HI containment pressure at 17 psig 9'D SIS [*,g) g..Q l

1 4.47 x 10 E+6 lb/hr HI-HI steam flogd. 45 x 10 E+6 lb/'g,and Tavg < 540-F and 2.

HI steam flow >

3.

SIS.I.u]

g 343 tu)

[3 @ 0.5 each]

(1.5)

Containment pressure > 4 psig [0.5] or > 10 E+5 Rem /hr [0.5].

(1.0) c.

REFERENCE Kewaunee, E-0 and QRF, PP. 3, 6 l

l l

4.

PROCEDURES - NORMAL. ABNORMAL. EMERGENCY AND PAGE 30 RADIOLOGICAL CONTROL ANSWERS -- KEWAUNEE

-86/06/24-JAGGAR, F.

ANSWER 4.04 (2.00)

At least one SI pump running and RCS pressure less than 1240 psig a.

(1480 adverse containment).

(1.0) b.

RCS subcooling (leased on core exit TC's) < 30-F (120-F adverse containment).

OR PRZR level cannot be maintained > 2% (20% for adverse containment).

(1.0)

REFERENCE Kewaunee, E-P QRF ANSWER 4.05 (2.00) a.

1.

Set S/G PORY controller at 1050 psig.

2.

Close ruptured S/G steam supply to turbine driven AFW pump.

3.

Verify /close blowdown isolation valves

' ' - - - ' - - ' --^ '

Osmu m fc '

4.

Chue Mu\\/5.mm.394'5UAWE-

[0.25 each]

b.

Close remaining MSIV's and bypass valves and using intact S/G PORV f or steam dump Lo.d)

• d)

(1.0) l REFERENCE Kewaunee, E-3, P.4 ANSWER 4.06 (2.00) 1.

Subcriticality (S) 2.

Core cooling (C) 3.

Heat sink (H) 4.

Integrity (P) 5.

Containment (Z) 6.

Inventory (I)

[0.25 each, 0.5 correct priority]

(2.0) l l

REFERENCE Kewaunee, EOP, F-0.1 to -0.6

~-

4.

PROCEDURES - NORMAL. ABNORMAL. EMERGENCY AND PAGE 31 RADIOLOGICAL CONTROL ANSWERS -- KEWAUNEE

-86/06/24-JAGGAR, F.

ANSWER 4.07 (4.00) b ens-r.. a.

a.

1.

Failure of mAcontrol rod to drop following a trip.

2.

Control rods below the low-low insertion limit.

3.

Uncontrolled cooldown Unexplained or(Ft-51jrolled reactivity increase.

4.

uncon

%w s ca GAew C4regwelj0. 5 each]

(2.0) f.

b.

1.

Open the emergency boration valve (CVC-440/MV-32127).

2.

Start BOTH boric acid transfer pumps in FAST speed.

3.

Start a second charging pump (if not running) and adjust to maximum speed.

4.

Open an additional 40 rpm orifice isolation valve.

[0.5 each]

(2.0)

REFERENCE Kewaunee, E-CVC-35 ANSWER 4.08 (3.00) a.

- High RCP Bearing Water Temperataure I

- #1 seal leakoff tem ture high (1.0) b.

- Seal injection flo een 8 and 13 gpm [0.5]

- #1 seal leakoff flow 0 s than 1 gpm [0.5]

l

- RCS pressure,r,QOOO psig [0 J6]

- Plus either o the alarms above [0.5]

(2.0)

REFERENCE Kewaunee, Operating Procedure, N-RC-36A, P.

5 ANSWER 4.09 (2.50) a.

1.

c 2.

b 3.

e i

4.

a

[0.5 each]

(2.0) i b.

TRUE (0.5) l l

REFERENCE Kewaunee, Radiation Protection Training Manual, Theory, P. 0-37 to 0-48 l

l

~

~

f 4.

PROCEDURE - NORMAL. ABNORMAL. EPGtRGENCY AND PAGE 32 RADIOLOGICAL CONTROL ANSWERS -- KEWAUNEE

-86/06/24-JAGGAR, F.

ANSWER 4.10 (2.50) a.

2 DPM (0.5) b.

" 0., t e, uu.crvalo, 1.:n plet indic;tc; critic lit;- --it:.lu "

?

at-pa, :;2^a to

at;; a leau izt; :22:.

':.C ?

c.

Return rods to the ECP position [G.5] and recalculate the ECF [0.5] (if no error proceed to hot shutdown, if an error and new posi% ion is higher-continue startup).

(1.0) 9., + b. AdeAAL REFERENCE Kewaunee, N-CRD-49B, PP.

1, 4 i

l l

t l

l l

l

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