ML20210D191

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Exam Rept 50-298/OL-86-02 on 860602 & 03 & 0807.Exam Results:All Candidates Passed Retake Operating & Written Exams.Exam Answer Key Encl
ML20210D191
Person / Time
Site: Cooper Entergy icon.png
Issue date: 09/10/1986
From: Cooley R, Graves D
NRC
To:
Shared Package
ML20210D155 List:
References
50-298-OL-86-02, 50-298-OL-86-2, NUDOCS 8609190074
Download: ML20210D191 (43)
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EXAMINATION REPORT- 50-298/0L-86-02 Facility Licensee: Nebraska Pub 1fc Power District P. O. Box 499 Columbus, Nebraska 68601 Facility Docket No.: 50-298 Facility License No.: OPR-46 Operator License examinations administered at Cooper Nuclear Station (CNS)

Chief Examiner: Y/l. . , ~ S/s/]L D. N. Graves Da~te' Approved By: s 4e & /0/No R.'A. Cooley,Chyf,OperatorLicensirig D' ate ' '

Section v Summary Two Reactor Operator candidates, were administered retake operating examinations. One Reactor Operator candidate was administered a retake written examination. All three candidates passed.

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1. Persons Examined Pass Fail Total R0 Candidates 3 0 3.
2. Examiners D. N. Graves, (Chief Examiner), NRC R. A. Cooley, NRC E. A. Plattner (Proctor), NRC CNS Resident Inspector L 3. Examination Report Performance results for individual candidates are not included in this report.
a. Examination Review Comments and Resolution This section reflects the comments made by the facility during the examination review conducted following the written examination. The comments accepted by the NRC reviewer have been incorporated into the master copies of the examination included in this report. Comments and resolutions are listed by section and question number.

1.02 Part C.

Answer: This answer allows two possible approaches. The second option (GV's already at limit) would not be a normal condition at Cooper and, therefore, the assumption should be stated. (Answer Key reflects this.)

However, the first option (Load reference above 100%

load) is a normal situation. Procedure 2.2.14 (Turbine operating procedure) instructs the operator to enter a DEMAND of 800 MWE. The DEH student handout (p 27) states that a large bias signal is then applied so that the PRESSURE Control signal has priority. (The pressure control signal is compared to the load demand plus bias signal in a low Valve Gate.) The student may not state the assumption since this is the normal mode of operation. Therefore, we feel the student should not lose points (required by answer key) for not .

stating " . . . if load demand is set greater than 100%

load."

Resolution:- Agree. Answer key modified.

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1.04 Answer: The answer key uses a reactor pressure of 1060 psig for 100% reactor power. The Main Steam system student handout (P 15) states that reactor pressure will be about 1015 psig at 100% reactor power. Here at Cooper, we generally simplify this to "approximately 1000 psig."~

We feel that any reasonable pressure near 1000 psig should be accepted as correct and the student's calculations based on the assumed reactor pressure.

Resolution: Agree. Answer key modified to accept + or - 20 psi for 1% values and.+ or - 50 psi for 100% values.

1.05 Part A Answer: Operating Procedure 2.1.1 (Cold Startup) also discusses avoiding fast period scrams. It instructs the operator to adhere to the " Banked Position Withdrawal Method:"

for the third and fourth RSCS groups withdrawn. The student should receive credit (0.5 pts) for the " Banked Position Withdrawal Method:" as the second portion of the answer.

Resolution: Agree. " Banked Position Withdrawal Method" added as alternate wording for second portion of answer.

1.12 Answer: One of the things stressed during E0P training is adequate core cooling. The term " steam cooling" is used in discussing heat removal. The student could use the term " steam cooling" to answer this question. This should be considered an acceptable answer. NEDC-30873 (EOP Training Material) defines steam cooling.

Resolution: Agree. Steam cooling accepted. Answer key modified.

2.02 Answer: B. Question states list features, answer key requires a description of each feature. Should not require a description for full credit.

t Resolution: Agree. Answer key modified to exclude description in grading.

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4 2.04 Answer: A. Bearing spray is considered one area because when the.

spray is initiated, it' sprays'all three bearings.

Therefore, " bearing area" should be considered three correct answers.

Reference:

Fire Protection Lesson ~ Plan, Pages 4 and 14.

Resolution: Disagree. Bearing area counted as three only.if the three bearings specified; otherwise counted-as.one area.

Five other areas still available to complete the six:

areas required.

2.04 l Answer: B. There are (2) local pushbuttons for local actuation. .

The student may list each pushbutton as a method since

.they are approximately 30 feet apart. Each pushbutton should be considered separately.

Reference:

Fire Protection Lesson Plan, Page 14.

Resolution: Agree. Answer key modified.  : :

2.07

- Answer: A. SBGT lines up to take a suction on Primary Containment also. ADR-1A closers, ADR-1B opens. t

Reference:

SBGT Lesson Plan, Pages 5 and-7 (Attachment

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Resolution: ' Agree. Answer key modified.

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' 3 Answier: - C. Number 2 speed limiter is also called single limiter [

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, and should be accepted for full credit.

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Figure 14,-Recirc Lesson Plan j j -n ..

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s"-) Resolution: ' Agree.' Added as alternate acceptable wording.

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g B. . Level Signal is also sealed in. '

Should require both

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Reference:

Nuclear Pressure Relief Lesson Plan, Page 9 Resolution: Agree. Answer key modified.

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4.11 Answer: B. Recirc discharge valve has been improved to prevent hydraulically locking valve and causing it to stick in seat. A hole has been drilled.in reactor side disc to allow' pressure between discs to be relieved. Should accept cold water injection for full credit as per G.O.P. 2.1.15, Rev. 17, Page 1.

Reference:

Recirc Lesson Plan, Page 11 G.O.P. 2.1.15, Rev. 17, Page 1 Resolution: Agree. Hydraulic lock answer replaced with cold water injection.

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b. Examination Master Copies Enclosed are final copies of the examination and answer key.

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t U. S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION FACILITY: _GQQEEB__________________

REACTOR. TYPE: _RWB-QE4_________________

DATE ADMINISTERED: _RklDHZQZ________________

EXAMINER: _QB& Vent _Qz______________

CANDIDATE: _________________________

INSIBUGIl0NS_IQ_QaNQ106IE1 U3c separate paper for the answers. Write answers on.one side only.

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

% OF CATEGORY  % OF . CANDIDATE'S CATEGORY

__V8LUE_ _IQI8L ___SQQBE___ _V8LUE__ ______________QaIEQQBl_____________

_25tDQ__ _25tQQ ___________ ________ 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW

_25zQQ__ _25z09 ___________ ________ 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS 4

_25z00__ _25z99 ___________ .,_______ 3. INSTRUMENTS AND CONTROLS

_25tQQ__ _251QQ ___________ ________ 4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL 1DQzQQ__ ___________

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

Candidate's Signature

NRC RULES AND GUIDELINES FOR-LICENSE EXAMINATIONS ~

During the administration of this examination'the'following rules apply:

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

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

-room to avoid even the appearance or possibility of cheating.

3. Use black ink or dark ~ pencil SD1y to facilitate legible reproductions.

D4 . -Print your name in the blank provided on the cover sheet of the examination.

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

6. Use only the paper provided for answers.
7. . Print your name'in the. upper right-hand corner'of the first page of gggb cection of the answer sheet.
8. Consecutively number each' answer sheet, write "End of Category __" as-eppropriate, start.each category on a Ogg page, write 9DlY 2D 2DR fidt 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 ibras lines between each answer.

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1 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 111stgigtg.
13. The point.value for each question is indicated in parenth'ases 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 i to mathematical problems whether indicated in the question or not.
15. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE

-QUESTION AND 00 NOT LEAVE ANY ANSWER BLANK.

16. If parts?of the examination are not clear as to intent, ask questions of the gxam1Dat 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 after the examination has

! been completed.

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

c. Assemble your examination as follows:

(1) Exam questions on top.

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

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

b. Turn in your copy of.the examination and all pages used to answer the examination questions.
c. Turn in all scrap paper and the balance of the.psper 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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Iz-_EBXNGIELER_QE_NUGLE88_EQWEB_EL8BI_QEEB811QNi PAGE 2.

IBEBdQQ1NadIQ1&_BE81_IB881EEB_8NQ_ELUIQ_ELQW QUESTION 1.01 (2.00)

The reactor is operating at 80% power. Recirculation flow is increased to raise power. Describe how the various' reactivity coefficients function to cause and. terminate the power increase. Include in your cnswer each effect that.causes a reactivity change, and why that effect ccuses its associated reactivity change. (2.0)

QUESTION 1.02 (3.00)

Roactor power.has been at 50% for the past three days. Power is now

.rsised to 100%. Four hours later, how will each of the following com-pore with their initial values (at 100%), assuming no operator action?

-EXPLAIN why in each case. Values are not required. (3.0) ,

c. core flow
b. reactor power
c. megawatt output Celectrical)

QUESTION 1.03 (2.00)

During refueling, the reactor is subcritical with a stable countrate of 200 cps. Keff = 0.99. A new fuel bundle is added to the core and the countrate stabilizes at 400 cps.

a. What is the new Keff? SHOW ALL WORK. (1.0)
b. What effect does adding the same amount of reactivity again have on the condition of the reactor? JUSTIFY YOUR ANSWER. (1.0)

QUESTION 1.04 (2.00)

The reactor is critical at ~ 1% power. RPV pressure is 920 psig. How much reactivity will be added due to the moderator temperature coefficient ca. reactor power is increased to 100%. JUSTIFY your answer and SHOW ALL WORK. (2.0) l i

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lo__EBINCIELER_QE_NuGLE88_EQWEB_EL8NI_QEEB8Il0Ni PAGE 3 IBEBdQDINed101t_BE61_IB6NSEEB_8ND_ELMIQ_ELQW QUESTION 1.05 (2.00)

~e. Describe the control rod withdrawal method used that is meant to help eliminate fast period scrams caused by high notch worths. (1.5) b.. What scram is designed to. shut the reactor down in a short period situation during a reactor startup? (0.5)

-QUESTION 1.06 -(2.50)

The reactor is operating at 100% when one Safety / Relief Valve opens and ctays open. Indicate how each of the following parameters will change, oteady state to steady state, and briefly explain why each responds that way. Assume no operator action. (2.5)

e. Turbine steam flow
b. Reactor vessel level
c. . Reactor pressure

-QUESTION 1.07 (1.50)

A motor operated centrifugal pump is operating with a discharge pressure of 50 psig, flow of 150 gpm, and power consumption of 2 kw. If the cpeed of the pump is increased to raise the flow to 400 gpm, what is the new: (1.5)

a. discharge pressure?

-b. power consumption?

QUESTION 1.08 ( .50)

Why does decay heat NOT indicate on the nuclear instrumentation? (0.5)

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.11__EBINGIELE1_QE_NWGLEeB_EQWEB_EL8NI_QEEB8Il0Ni - PAGE 4 IHEBBQQ1NAMIGit_HE8I_IBeNSEEB_8NQ_ELMIQ_ELQW.

QUESTION. 1.09 (1.50) 4 -

LList six (6) energy factors used in the calculation of a reactor heat balance and indicate.whether each is a positive!or negative energy input to the calculation. (1.5)

QUESTION 1.10 (2.00)

c. State the mode of heat transfer for. each of the following items (assume BOL): (1.0)
1. fuel pellet to the clad
2. through the cladding
3. cladding to the coolant c'nannel it' b '. Is-the. fuel centerline temperature higher at the beginning of a fuel cycle or at'the end of a fuel cycle? JUSTIFY your answer. (1.0)

QUESTION 1.11 (1.00)

HOW-and WHY would removal of 100% of the inert and;noncondensible gases

.from the reactor coolant affect heat transfer in the reactor? (1.0)

( QUESTION 1.12 (1.00)

What is the mechanism or process by which a fuel rod is cooled following '

l the occurrence of transition boiling (NOT one of the three basic heat

transfer modes)? (1.0) l.

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

itu_EB4NGIELES_QE_NUGLEaB_EQWEB_EL'8NI_QEEB6I1QNi PAGE 5 IHEBdQQ1NedIGS&_BE61_IB8NSEEB_6NQ_ELU10..ELQW QUESTION 1.13 (2.50)

'Which BWR thermal limit (s) must tua maintained within design values to ensure adequate thermal margin during: (2.5)

e. normal steady state operations
b. transient conditions c.- accident conditions QUESTION 1.14 (1.50)

Concerning control rod worths during a reactor startup from 100% PEAK XENON versus a startup under XENON-FREE conditions, which statement to correct? JUSTIFY YOUR CHOICE. (1.5)

c. PERIPHERAL control rod worth will be LOWER during the PEAK XENON startup than during the XENON-FREE startup.

b.- CENTRAL control rod worth will be HIGHER during the PEAK. XENON startup than during the XENON-FREE startup.

c. BOTH control rod worths will be the SAME regardless of core Xenon conditions.
d. PERIPHERAL control rod worth will be HIGHER during the PEAK XENON startup than during the XENON-FREE startup.

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

'21,__EL6NI_ DESIGN _INGLUDINQ_H6EEIY_6ND_EMEBSENGX_SYSIEUS. PAGE' 6 QUESTION 2.01 (3.50)

c. From where does the RHR Service Water Booster system take its suction and to where does it discharge? (0.5)
b. HOW is an inadvertent admission of RHR Service Water into the RHR. system prevented (physically, not administrative 1y)? (0.5)
c. WHAT is the relationship between RHR Service Water system pressure and RHR system pressure and WHY? (1.0)
d. HOW is the relationship in "c" above~ controlled or varied? (0.5)
o. A RHR Service Water Booster Pump control switch is positioned

-to START and the switch stays in this position. Is this desirable? EXPLAIN. (1.0)

QUESTION 2.02 (3.00)

e. Describe the arrangement of components that ensures no portion of the primary containment exceeds the maximum design EXTERNAL pressure?

Include the maximum design EXTERNAL pressure. (1.5)

b. The secondary containment system utilizes four different features to mitigate the consequences of a postulated loss of coolant accident or refueling accident. LIST three (3) of these features.(1.5)

QUESTION 2.03 (3.50)

c. The reactor is at 400 psig. Describe how the Core Spray inj ect ion valves (MO-11 anc MO-12) must be operated to have them both open at the same time. (0.5)
b. The reactor is at 500 psig. Can the Core spray inj ect ion valves (MO-11 and MO-12) both be opened at the same time? If so, describe how they must be opened. If not, can EITHER of the two valves be opened with no inj ection signal present? EXPLAIN. (1.0)

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c. What is the meaning of the white light above the MO-11 and MO-12 control switches? Once illuminated, what THREE (3) conditions will cause the condition to clear? (2.0)

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

CATEGORY 02 CONTINUED ON NEXT PAGE

2i._EL4NI_QESIGN_INGLUDING_18EEll_eNQ_EMEBGENGl_SYSIEdS- PAGE 7 QUESTION ~ 2.04 (2.00) 0.. What are six (6) areas served by the Low Pressure CO2 System?

Indicate whether the area is covered AUTOMATICALLY or requires MANUAL actions. (1.5)

b. After the initial 50 second discharge of CO2, how are subsequent

. discharges initiated (2 methods or locations required)? C0.5)

QUESTION 2.05 (2.00)

For each of the following items (a - d), indicate whether it describes proper system response or not. If it does not, describe how the discussed event should occur.

's. With the RCIC system operating, a low level occurs in an ECST.

The pump suction from the ECST (RCIC-MO-18) closes and the pump suction from the suppression chamber (RCIC-MO-41) then opens. (0.5)

b. The RCIC system is operating with reactor level increasing.

When the high level setpoint is reached, the steam supply inboard and outboard isolation valves (RCIC-M0-15 and 16) close. (0.5)

c. The-RCIC system is operating in the TEST mode, discharging to the ECST. A valid low reactor level initiation signal is received. The test circuitry is automatically bypassed, the test bypass to ECST closes, and the flow controller. controls RCIC flow automatically. (0.5)
d. With the RCIC system operating, a high steam line space temperature isolation signal is generated. The following valves close as a result of the isolation: Steam supply inboard and outboard isolstion valves (RCIC-MO-15 and 16), the minimum flow valve (RCIC-MO-27), the RCIC pump discharge valve (RCIC-MO-20), and the injection valve (RCIC-M0-21). NOTE: The above listed valves are not the only valves that are affected by the isolation.

EVALUATE ONLY THE VALVES LISTED. DO NOT ATTEMPT TO COMPLETE THE LIST. (0.5) l

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

J2t-_EL4NI_QESIGN_INGLUQ1NE_16EEIX_6NQ_EMEBEENRY_11SIEd$ PAG'E 8 QUESTIONL 2.06 (1.50)

c. What two (2) mechanisms or methods are used in the Offges System to maintain or reduce hydrogen concentration of.the offges? (1.0)

Eb. Why is there a maximum power limit imposed on the use of the mechanical vacuum pumps? (0.5)

QUESTION 2.07 (1.50)

O. Where does the Standby Gas Treatment System line up to take a suction on an automatic initiation due to a refueling accident? (0.5)

b. Other than the normal automatic initiation supply and dilution air, what are two (2) additional areas or components that can provide a supply to the Standby Gas Treatment System? (1.0)

QUESTION 2.08 (3.00)

Explain for each system given below, the relationship or interface with the Control Rod' Drive Hydraulic system (CRDH). Be specific Ebout CRDH components which interface with each.

o. Demineralized Water System. (0.75)
b. Reactor ~ Equipment Cooling System. (0.75)
c. Reactor Building Equipment Drain System. (0.75)
d. 125 V DC. (0.75)

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

2&__EL4NI_DESIEN_INGLUQ1NE_18EEI1_6NQ_EMEBEENGl_SYSIEd1 PAGE 9 QUETION 2.09 (3.00)

Explain how AND why a complete loss of the plant air system, while operating at' full power, with no operator action, would affect the following plant parameters or components.

c. Main condenser vacuum. (0.75)
b. RWCU operation. (0.75)
c. Main-Steam Isolation Valves. (0.75)
d. Control Rod position. (0.75)

QUESTION 2.10 (2.00)

The blowdown flow centrol valve (FCV-55) in the Reactor Water Cleanup eystem is tripped closed when either of two abnormal conditions exist.

What are these two conditions and what do they prevent? (2.0)

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

-h 2&__IN4IBNMENIS_6NQ GQNIBQLSL PAGE 10 ,

QUESTION 3.01 (2.00)

'The reactor is operating at'100%_under steady state-conditions. An instrument technician mistakenly isolates and equalizes.the pressure

ccross one of the MAIN STEAM line flow transmitters. DESCRIBE the response of the Feedwater Control System until steady state conditions are again-established.- ASSUME 3-ELEMENT CONTROL. (2.0)  ;

QUESTION 3J02 (3.00) '

For each of_the situations listed below, describe how the '

roeirculation and-flow control _ systems will respond and why.

' include which component.is controlling speed and whether both or only one pump is affected.

a. 28% power, recirculation _ pumps et minimum speed with bath' I M/A transfer stations in manual. Recirculation pump "A" M/A transfer station is switched to AUTO. (1.0) ,
b. =75% power, recirculation flow control is in master manual .

when the MG set "A" tachometer output fails to s zero output.- (1.0)

c. 75% power, recirculation flow contro'l is in master manual when one reactor feed pump trips. (1.0)

QUESTION 3.03 (3.50)

c. All parameter inputs to the ADS are present for initiation and the timer is counting down. What are two (2) ways the operator can prevent the ADS valves from actuating? (1.0)  ;

-b. Which of the four initiation logic signals -is(are) sealed in? (0.5)

c. With NO ADS initiation signals present, what is the status of the red and blue lights on the 9-3 panel associated with the ADS valves? (0.5)
d. What do the red and blue lights on the 9-3 panel indicate about the state or status of the ADS valves? (1.0)
o. Experience nas shown that the SRV's can inadvertently open if what conoition occurs? Assume the logic is functioning properly and there are no breaks in the system. (0,5)

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

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. 'du__164IBVMENIS.6NQ_C9NIEDL3 PAGE 11 QUESTION 3.04~ ~(2.00)

'D0 scribe the response of the Main Turbine Control System (DEH) to osch of the eventa described below. Assume all control systems function normally and NO RPS TRIP is generated.

'o. One steam bypass valve partially opens while at 70% power (DEH in Mode 4) (1.0)

b. Reactor power _ is manually increased above the load reference

.setpoint (DEH in Mode 4) (1.0)

QUESTION 3.05 (3.50) ,

c. What provisions are made in the Offgas System to DETECT an explosion or burn-back? (1.0) b '. If an explosion or burn-back is detected, what automatic action takes place in the Offgas System? C0.5)
c. What are three ways that an Offgas System isolation can be accomplished (with the exception of individually closing each isolation valve)? Include any time delays that occur as appropriate. (2.0)

QUESTION 3.06 (1.50)

Following a reactor scram, the four rod display position goes blank, but the green f ull-in light on the f ull core display f or that control rod is lighted. Is this normal? If so, explain why it occurs. If not, describe the probable cause. (1.5)

QUESTION 3.07 ( .50)

Which of the following provides the signal _for a Turbine Control Volve (TCV) Fast Closure scram? (0.5)

1. TCV position limit switches
2. Rate of TCV position change
3. Power to the TCV fast acting solenoids
4. Turbine control fluid pressure

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

24__INSIBUMENI1_8NQ_QQNIBQL3 PAGE 12

. QUESTION. 3.08- (2.00)

A LOCA has occurred and HPCI initiated, operated, and tripped on high level. Leve1Lis now 37 inches and decreasing, How can the ,

cyntem be restarted? TWO METHODS REQUIRED. (2.0)

QUEST 10N 3.09 (3.00)

c. Other than alarm lights, what are three (3) instruments that utilire ,

the recirculation. flow converter output as an input? An instrument

.that has more then one channel counts en one inst r ume rit . (1.5)

b. What are three (3) indications that the operator will have on the control room front panels that the A flow converter unit output'is 15% higher then the 8 flow converter unit output? [1.5)

QUESTION' 3.10 C .50)

True or.Fa.lse. Flow-biased scrams'and rod blocks are not required, by d sign, to prevent exceeding the fuel thermal limits. (0.5) ,

QUESTION 3.11 (2.50)

c. What action must be taken to make the NMS RPS logic "noncoir.cident"

'(Any single NMS channel will cause a full RP3 trip)? (1.0)

b. What IRM/APRM conditions are necessary to ger.arate-e companion IRM/APRM scram? (1.0)
c. The companion IRM/APRM scram is automatically bypassed when the reactor mode switch is placed in any position other than ________.(0.5)

QUESTION 3.12 (1.00)

Describe how an equalizing valve leak on a reactor level transmitter effects the indicated level from that transmitter. (1.0)

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

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' : QUEST 10N 4.01 -(2.50) 10.1 --'Annu'nciator win' dows on panel 9-5-having a1 RED background are

,essociated.with'WHAT CONDITION? (0.5)

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b..'IndicateJthe color-of the annunciator-windows that denotes each of the following conditions:

~1. Priority 11 - A critical condition that-requires immediate (0.5) u operator' action

2. Priority II - An_off-normal condition which.could rapidly: (0. 5) .

develop into a' critical condition k 3. Priority III -'An'off-normal condition which requires (0.5).

operator followup i-I' c. WHO must'give his/her approval before any annunciatoricard

'- may.be1 removed (identify by minimum requirements, NOT.name)?-

. (0.5) y QUESTION '4.02 (2.00)

-What!are two {23' undesirable consequences of' a loss of both Control i Rod Drive Hydraulic pumps? Include WHY the consequences are jr undesirable.' (2.0)

{ QUESTION ;4.03 (2.50)

[ "o. What are three (3) areas'or locations that will be manned by 4- operations personnel following an evacuation of the control +

Lroom?- (1.5) ,

it b.; If the reactor was not scrammed prior to leaving the control

] room, whatJare two (2) alternate methods of scramming the 5 reactor, per EOP 5.2.1, Shutdown from Outside the Control Room? (1.0) 4.04 (2.G0)

{ QUESTION I A. loss of'the Service Water System has occurred and it is not oxpected that the system will-be restored within a short period

-of time. What are four (4) actions that must be performed? (2.0) 1 i J

          • )

.C***** CATEGORY 04 CONTINUED ON NEXT PAGE

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

s im__EBEGEQUB52_:_NQEd8LeieRUDEd6Lt_EdEBhENC1.6UQ. PAGE 14 B&DIQLQE198L_GQNIEQL y

~

QUESTION 4.05 (1.00) ,

< Boron injection into -the reactor is required per EOP1, RPV Control, .

cnd the~ Standby Liquid Control System is incapable of inj ect ing into the RPV. Describe basically how boron injection to the RPV'is cccomplished under the above circumstances. Specific procedural

-oteps ARE NOT. required.. (1.03-QUESTION. 4.06 'C2.00)

Answer the following questions concerning GOP 2.1.5, Emergency Shutdown from Power a.- After the manual scram buttons are depressed, what two (2) checks should the operator make to verify all control rods inserted? (1.0)

b. If it becomes necessary to shut the MSIV's after the scram, what are the two (2) methods stated in the procedure for accomplishing this? (1.0)

QUESTION 4.07 (2.00) c .- How long can artoperator stay in a 2S MREM /hr radiation field without exceeding a CNS administrative radiation exposure limit? (1.0)

b. What action (s) should be taken by an individual who finds his/her pocket chamber dosimeter is reading greater than full scale? (1.0) l

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

m is _EB $EQVBEl_:_UQBd&kA_6$$Q$dela_EME62ENQ1.600 PAGE IB E6LIQLQfl?6L_QQUIB2.L .

(

4

(

QUESTION 4.06 (2.5G)

A. lows'of all site AC powCI,hes occurf ed.. Anxver thy fc11owing

. questions concerning EQP;5.f.S.t, Lots of All AC #cV7e %tstion Dieckout. -

G. What reactor water level indicatical.s.1 a.ee sv0P.)stin le'the control room followtog this event? (l 91

b. What reactor veter level todicotton(s? sre eveitep}4 outside 1

the control room following 1910 event? 10 53

c. Why should reactor pressure 90T Je teo'uted i)41te 'Qs ha$urst,toit oressure cerresponding ts th.e cel teum dry =sti $H%eratare? (icG) '

~

i QUESTION 4.09 (7.80i MATCH each of the evwnia {.* - d) with MA4 pr 05 59*3 bi i61.sh tho >

ovent may be per f ormed MMg a cot s Mann StF f'H) id e Y1}P ? .1 # 1.

"Colo Startup P roceduc e"- *;teme .54/ te widt 400 3 't144 <nco er ,

not at all as approiristm. (2,0)

___._e. Begin placing VL(6 095p in 14tuttc k. 20 otip -

_____u. Open HPCI sta e .inelation w Alg.y.> E. Eh asyd '

_____c. Steam seals nf, peed t r. 44ts us sc (pb (*s tg

_____o Reset and unisolGte ACit 4 V!G pcts

% '. 4%D 93sg QUESTION 4 .1,0 (1.#0)

c. 'What pravision is made. tor ccM acitsq ytrta ngj bethe dsec1 I generator room from-tha ennte44 resa Aurins dasset ynnAretaf cperations. (1.8)
b. Describe how the diesel 066ciatot w o4 l0 L a *.M
  • 04 5. v l e d t o ty.

energized bus. Asdame the Aietal ge<4-etr> is 'a(17109, tb4 synchroscope is vn, a n d t h e v iv.h 4 N i wn.o ! .d c e 1.4 W wtom6 tic.

Your ' ariswer should includa i ndi.c 3.t s o ? 3 end cer?ca'w( used sav adj ustraente made during the parf6tA94c4 4? ths ;teclu' son, 12.0) r i

(***** CATE0'JRY 04 ..conigeNsp ON Ni;g ' 2'MF * * *wl

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

+m. - _.

b. t. is l ~

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>, , 1-s,p .. , u. .

TY ol r-l- Edik_kUhhbOV 3El_z_8S ed6Li_Aub? R5tki.m EdEBQENCY._8NQ PAGE 16 860;0k0GIGGk GUSIB0k c,' +

l ,

I

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. n

.'QUE6H ON A.1I (2.501 7tata 'the und6cirable censsqcance essociated with each of the following

coerotin,g' ncnditions or proceutions regarding the recirculation system
.

! a. -A recirctslott.tp pump is shutdown and I.solated, but the seal purge

-is not isoistads (1.0) {

b, .The estirculatsori come.1L left isolsted (suction and discharge valve '

shut) with 'the reahter at rated temperature and pressure. (0.5)

e. The reactoi is coarating et'ocwer with severely unbalanced _ jet pump .

flowc. (1.0) f QtJESIYC04 4/12 ({.00';

lodicit4 whigh of the f ollowing raatiiods of operating the recirculation '

l cptuos is 9 ore dextral 3e during extended outages (a or b)-ANO state why the other Math =4 $9 tan des i r ab le . 01.0)

[ o. %3,9 tha rae.i(celatten pumps continuously at low pressura. C 4

l ha. Snutdows th.e te6jecu19 tion pumps and restart them when desired.

f .

L i ,

l i

i, i

!^

l 1

?

B

(***** END Of CATEGORY 04 *****)

(*************.END 0F EXAMINATION

                              • )

NRC LICENSE EXAMINATION HANDOUT EQUATIONS. CON 5fANTS, N(D C0HVERSIONS t

6=5*C*deltaT p 6 = U*A*deltaT P = Po*10sur*(t) P = P *et /T SUR = 26/T T=1*/p+($-p)/Xp T=1/(p-p) T = ($-p)/Xp p = (Keff-1)/Kef f = deltaxe ff/Keff p = 1*/TKeff + yeff/(1+1T) .

A = in2/tg = 0.693/tg X = 0.1 seconds-I I a lo*e CR = S/(1-Kef f) 2 it/hr = 6*CE/d feet s

Wates Parameter _s, ,

1 gallcn = 8.345 l b = 3.87 liters 1 ft3 = 7.08 gallons Censity # STP = G2.4 ltg/ft3 = 1 gm/cm3 11 eat of vaporization = 970 Btu /lbs lieat of fusion = 144 Stu/lba 1 atmosphere = 14.7 psia = 29.9 inches Hg.

Miscellaneous Conversions 1 curie = 37TTOW disintegrations per second 1 kilogram = 2.21 lbm I horsepower = 2 54 x 103 Btu /hr 1 nw = 3.41 x 108 Btu /hr 1 inch = 2,54 centimeters degrees F = 9/5 degrees C + 32 degreet C = 5/9 (degr.ees F - 32) 1 Stu = 778 ft-lbf

- . - . . .___]

1x__EB1UCIELER_QE_UMGLEaB_EQWEB_ELeUI_QEEBaI19Ni PAGF 17 IBEBdQQ1N8dlQSt_BE61_IB8NSEEB_oND_EL910_EL9W ANSWERS -- COOPER -86/08/07-GRAVES, D.

ANSWER 1.01 (2.00)

A3 flow increases, the void content in the core decreases (0.25), causing c positive reactivity addition due to the void coefficient (0.25). As power starts to increase, the fuel temperature begins to. rise (0.25). As the fuel temperature increases, the fuel temperature coefficient adds negative reactivity (0.25) to slow the power rise. As the higher fuel tcmperature is transferred to the coolant (0.25), void generation increeses (0.25). which also adda negative reactivity. The power increese is terminated by the combined negative effects of the void cnd doppler coefficients (0.8).

REFERENCE R0 actor Physics Review, pg 52 ANSWER 1.02 (3.001

c. Core flow would be lower (0,5), As power increases, 2 phase ficw resistance increases (0.5), which would cause a decrease in core flow.
b. Reactor power would increase (0,5). Xenon would be burning out (0.5),

which adds positive reactivity.

c. Megawatt output would increase (0.5) if the load reference is set at greater than 100t rated load (0.5) OR due to pressure increaseing as a result of power increasing (0.5).

REFERENCE SOP 2.2.7, Turbine Generator, Rev 26, pg 24 GE Thermodynamics, Heat Transfer, and Fluid Flow,' Chapter 9, pgs 45-48 Roactor Physics R.eview, pg 45

.= _

li r EBINQ1ELEE_DE.GVGLE68_EQVEB_EL6NI_QEE86110Ni PAGF 18 IBEB000188019%t_BE61_IBedSEEB_6bD_ELVID.ELQW ANSWERS -- COOPER -86/08/07-GRAVES. b.

ANSWER 1.03 (2.00)

o. CR2/CR1 = (1 - Keff1)/(1 - Koff2) (0.5 points for correct method) 400/200 = (1 - 0.99)/(1 - Keff?)

Keff2 = 0.995 (0.5 points)

b. The reactor would be slightly supercritical (will accept critical).

(0.25 points) reactivity = p p1 = (Keffl - 1)/Keffi = (0.99 - 1.03/0.99 = .0101 (G.25 points) p2 = (0.995 - 1.03/0.995 = .00503 (0.25 ooints) p2 - p1 = .00507 (added by the fuel bundle) (0 25 points)

{

if .00507 was added again, the reactor would be slightly super-critical C.00507 > .00503).

REFERENCE Roactor Physics Review, pg 14, 18 ANSWER 1.04 (2.00)

MTC = -1 X 10E-4/deo F (accept .7 to -1.8 X 10E-4/deg F) (0.25 point) 920 psig 0 1% = 934.7 psia = 536.4 deg F (0,5) 1000 psig 8 100% (0.25) = 1014.7 psia = 546.3 deg F (0.5) 5C6.3 - 536.4 = 9.9 deg F change from 1% to 100% power 9.9 deg F X MTC = -9.9 X 10E-4 (0.5)

Accept + or - 20 psi for 1% pressure and + or - 50 psi for 100% pressure REFERENCE Roactor Physics Review, pg 26 Steam Tables

C'

,~

- it__EBINQ1ELES_QE_NuQLE68_EQWEB_EL6MI_QEEB8IIDNi PAGE 19 IBfBdQQINed10St_BE61_IB8NSEEB 8ND_ELulD_ELQW ANSWERS -- COOPER -86/08/07-GRAVES, D.

ANSWER 1.05 (2.06)

o. The first two groups are withdrawn completely (0.5). The next two groups are withdrawn in a banked configuration to the full out position (Banked Position Withdrawal Method) (0.5).

Beyond the 50% rod density pattern, the RSCS group notch control enforces the desired pattern or withdrawal sequence (0.5).

b. IRM high flux (0.51 REFERENCE CN3 Procecure 10.13, Control Rod Sequence and Movement Control,
Attacheent A, Cav 13, pg 2 of 6 Coactor '. Phys ics Review, pg 50 ANSWER 1.06 (2.50)
c. Decrease (0.33). The SRV opening causes a decresse'in pressure at the turbine inlet which causes DEH to close down on the turbine governor valves (0.5).
b. Decrease (0.33). RPV level stays low due '.o the steam flow / feed flow mismatch (0.5).
c. Decreese (0.33). With the OEH contr3111ng throttle pressure, the SRV bpen keeps reactor pressure less thGn r'armal 100% pressure (0.5).

REFERE:lCE GE BWR Simulator Reactor Physics Lasson Plan BWRe4 Transie3+.s .

P 1

I e

9

, . . _ . .m. , _ , _ - 4 .w_- , 4 , ._,,..._,,r _--e ,p.

'Itm_EBINQIELE1_QE_NVQLEaB_EQWEB_EL8NI_QEE86IIQNi~ PAGE 20

-IBEBUQQINedIQ1t_UE81_IB6NSEEB_8NQ_ELUID_ELQW ANSWERS -- COOPER -86/08/07-GRAVES, D.

ANSWER 1.07 (1.50)

c. -N is proportional to flow (0.25) 400 gpm/150 gpm = 2.7 (0.25) dp is proportional to N squared (0.25) dp e (2.7)(2.7)C50 psis) = 364.5 psig (0.25)
b. pwr to proportional 'to N cubed (0,25) pwr = (2.7)(2.7)(2.7)(2 kw) = 39.4 kw (0.25)

REFERENCE GE Thermodynamics, Heat Transfer, and Fluid Flow, pg 7-111 ANSWER 1.08 ( .50)

'Occay heat is the result of the decay of fission fragments, which are not neutron reactions, and thus are not detected (0.5).

REFERENCE Ocsic Reactor Theory ANSWER 1.09 (1.50)

Core thermal power = RWCU water out + reactot steam out + radiatise losses out - RWOU water )n - CRO water in - pump heat - feed-water in (5 reouired at .125 for each parameter and

.125 for each + or -)

REFERENCE CNS Procedure 10.3, Core Thermal Evaluation, Rev 6, pg 1 c - - ,_

I li__EBINQIELER_QE_NWQLE88_EQWEB_EL8HI_QEEBeIIQNt_ PAGE 21 E IHE8dQQ1N8dIQEt_bE61_IB8H1EEB_aNQ_ELUIQ_ELQW

, ANSWERS -- COOPER. -86/08/07-GRAVES,.D.

ANSWER 1.10 (2.00)

o. 1. convection (0.5) 2.--conduction-(0.5)
3. convection (0.5):
b. .New' fuel'CO.5). The heat transfer is more efficient later-in life.

due to the lack of fuel'to clad gap (0.5).

REFERENCE

'GE' Thermodynamics, Heat Transfer, and Fluid Flow, Problem 8-1 ANSWER 1.11 (1.00)

The removal of the gases would suppress nucleate boiling (0.5), thus reducing the rate of heat transfer from the fuel to the coolant (0.5).

Also accept increasing heat transfer (0.5) due to decreasing the corrosion rate (0.5).

REFERENCE GE1 Thermodynamics, Heat Transfer, and Fluid Flow, pg 9-4 ANSWER 1.12 (1.00) 1 Impingement of tiny moisture droplets travelling at high' velocity OR steam cooling-(1.0).

REFERENCE-

.GE Thermodynamics, Heat Transfer, and Fluid Flow, pg 9-19 i ANSWER 1.13 (2.50)

a. MCPR, LHGR b' , MCPR, LHGR i
c. MAPLHGR (0;5 each) -

REFERENCE GE-Thermodynamics, Heat Transfer, and Fluid Flow, Chapter 9, pgs 100-101 l

i 1&m_EBINQ1ELER_QE_NUQLE88_EQWEB_EL8NI_QEEB8IIQNt- PAGE 22 IBEBdQQ1Ned10ft_BE81_IRANSEEB_8ND_ELVIQ_ELQW ANSWERS -- COOPER .-86/08/07-GRAVES, D.

ANSWER 1.14 (1.50)

"d" is.the correct answer (0.5). The highest xenon concentration will be in the center of the core (0.5), the high flux region from the previous operating period. This will increase the flux in the cres of.the peripheral rods (0.5) thus increasing their worth.

REFERENCE.

GE Reactor Physics Review, pg 36-37 4

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

2tJ_EL4NI_DE11GN_INCLUDINH_18EEII_6HD_EMEBGENCY_111IEd3 PAGE 23

-ANSWERS -- COOPER -86/08/07-GRAVES, D.

ANSWER 2.01 (3.50)-

c. suction - Station Service Water headers (0.25) discharge - Circulating Water discharge canal (0.25)
b. Two manual, locked-closed valves are in the line (0.5).

Number not required.

c.- RHRSW pressure is maintained greater than RHR' system pressure (0.5) to prevent any radioactive leakage from the RHR system into the Service Water system (0.5).

d. The pressure relationship is maintained by varying the position of the RHR HX Service water outlet valve (0.5).
o. No.(0.25). The RHR HX Service Water outlet valve will continue to open and RHRSW pump runout could occur (0.75).

REFERENCE CNS Service Water System Description, pg SVW-5, 15, 16, 28 ANSWER 2.02 (3.00)

e. Suppression pool to drywell vacuum breakers (0.6) and reactor building to suppression pool vacuum breakers (0.6) prevent exceeding the maximum design external pressure limit of 2 psi (0.3).
b. - negative pressure barrier (which minimizes the ground level release by exfiltration)

- low leakage containment volume (which provides a holdup time for fission product decay prior to release)

- (removal of particulates and iodines by) filtration (prior to release)

- (exhausting of the secondary containment atmosphere through) an elevated release point (3 required at 0.5 each, parts in parentheses not required for full credit)

REFERENCE CNS Containment System Description, pg CON-7, 10-11, 19-20 t

1 l

\ i

-2A,_EL8NI_QE11EN_INCLUDINE_18EEII_8NQ_EMEBGENGl_11SIEd3 PAGE 24 ANSWERS -- COOPER. -86/08/07-GRAVES, D.

-ANSWER 2.03 (3.50)

c. MO-ll must be opened first (0.5)
b. No (0.25), Yes (0.25), either of the two valves can be opened, but both cannot be open at the same time (0.5).
c. The white light means that only manual operation of the valve is allowed (0.5)-. Also accept that the valve is shut and an initiation signal is present.

The' condition can be c1 cared by :

- termination of the auto initiation signal (0.5)

- reactor pressure increases to > 450 psig (0.5)

- loss of power to the pump motor bus (0.5)

REFERENCE CNS Core Spray System Description, CS-5, 6, CNS Procedure 2.2.9, Core Spray System, Rev 26, pg 2

. ANSWER 2.04 (2.00)

a. Reactor building MG set room.- Manual Control building cable spreading room - manual Control room entrance - manual Turbine building switchgear room - manual Main generator - manual Turbine bearing #1 area - automatic Turbine bearing #2 area - automatic Turbine bearing #3 area - automatic (6 areas at 0.15 each, 6 initiations at 0.1 each)
b. - Reset button on the sprinkler control and fire alarm ~ panel in the' Control Room

- Manual pushbutton in the NW corner of the turbine generator operating floor

- Manual pushbutton on the North wall of the turbine generator operating floor shield wall (2 required at 0.25 each)

REFERENCE OP.2.2.2, Carbon Dioxide System, Rev 14, pg 2,5

2g__EL8HI_DE11GN_INGLuQ1NE_18EEIY_8NQ_EMEBEENGl_1111Ed3 PAGE 25

-ANSWERS'--' COOPER -86/08/07-GRAVES, D.

' ANSWER 2.05 (2.~00)

c. No,.theitorus' suction valve opens first, then the ECST suction valve shuts (0.5).
b. No, the steam supply block valve (RCIC-MO-131) shuts (0.5).
c. Yes (0.5)
d. No, the discharge and inj ection valves (RCIC-MO-20 and 21) do not close on an isolation (0.5).

REFERENCE SOP 2.2.67, RCIC,'Rev 25, pg 2-4 RCIC System Description, pg 9, 10, 13, 14, 15, 30, 31' ANSWER 2.06 (1.50) s.- - dilution (0.5)

- recombination (0.5)

b. Due to the possibility of combustion within the vacuum pump (0.5)

REFERENCE Offges and Augmented Offgas System Description, pg A0G-5, 8

' ANSWER 2.07 (1.50)

e. Reactor building exhaust plenum (0.5)

Primary containment exhaust ventilation line (0.5) b, HPCI gland steam condenser exhauster (0.5)

REFERENCE SBGTS System Description, pg 3, 4 I

J y- -.

.m. , - . - -- - = - ----.-t~---~w,---,,-.c. - ..--a - , - m--- - < - - - - - - - - - ,- e,--- w - , - - - . ,- e-.-r- ---

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

. ~~

22ialEL6NI_QE11EN_INCLUQ1NE_16EEI1_6NQ_EMEBEENQ1_111IEMS PAGE~ 26

-ANSWERS ---COOPER .

- 86/08/07-GRAVES, D.

ANSWER - 2.08 (3.00) j- o. Backup water. source for CRDH pump suction (0.75)..

' ~

b. Cooling _for-CRDH pump oil ~ cooler and pump thrust bearing-(0.75).
c. Collects water' drainage from the SDV & leakage from the HCU valves.

Collects discharge f rom the HOU accumulator when recharging (0.75).

I d.- Power'.to valves 140A!& 140B (backup scram valves) (0.75).

REFERENCE-Control Rod Drive Hydraulic System Lesson Plan, p. CRDH-30, 31 ANSWER 2.0g (3.00)

e. Decrease (0.25) due to loss of steam supply to SJAE C0.5).

t

b. RWCU pumps trip.(0.25) due to low flow as F/D FCV fails closed (0.5).

! .c.- Outboard MSIV's. drift closed (0.25) as accumulators discharge (0.5)..

d.- Rods indiscriminately scram (0.25) as scram valves open under spring pressure (0.5).

REFERENCE

, Plant Air System Lesson Plan, p. PA-16 ANSWER 2.10 (2.00)

The flow control valve is tripped closed when pressure upstream of-the valve is low (0.5) (less than 5 psig) to prevent' drawing a vecuum on'the RWCU system (0.5). When pressure between the flow control valve and the drain valves to the main condenser and radweste cystem is high (0.5) (greater than 140 psigli the valve trips to prevent overpressurizing the p ip'i ng downstream of the FCV (0.5).

REFERENCE
Roactor Water Cleanup Lesson Plan, Rev 0, pg RWCU-9 l

t

-* vm-~ 1-r -w - ~ , ,--w-y-,+,m r-----,e +w,a

21 _IN4IBudENI1_8NQ_GQNIBQLS PAGE 27 ANSWERS - . COOPER -86/08/07-GRAVES, D.

ANSWER- 3.01 (2.00)

Total steam flow would indicate 75% instead of the actual.100%.(0.5).

'The FWLCS would assume steam flow has decreased and reduce feed flow accordingly.CO.5). Level will begin to decrease. As' level con-tinues to decrease, a level. error signal.is generated which will increase feed flow back to the 100% value (0.5). .A new steady state lovel will be established lower than the original level-(0.5).

Will accept any similar-explanation.

REFERENCE CNS Feedwater Control System Description, pg FCS-16, 17 ANSWER -3.02 (3.00)

e. "A" pump speeds up to 45% (0,5), the low setting on the dual speed control limiter.CO.25). "B" pump speed is unaffected (0.25).
b. "A" MG will trip on-field undervoltage (0,5) . ~ The tachometer output is the reference signal to the voltage regulator (0.25).

"B" pump speed is unaffected (0.25).

c. No change until reactor vessel level reaches 27.5" (0.25), then both pumps (0.25) runback to 45% speed (0.25) due to the #2 speed limiter or single limiter (0.25).

REFERENCE CNS Recirculation System Description, pg Recirc-14, 15, 18, 19, Fig 10 l

i i

i

2tu_IN11BudENI1_8NQ_GQNIBQLH PAGE 28

-ANSWERS -- COOPER -86/08/07-GRAVES, D.

ANSWER 3.03 (3.50)

10. Depress both logic RESET.pushbuttons Turn off all running CS and RHR pumps Inhibit switches to INHIBIT (2 at 0.5 each)
b. 120 second timer (0.25) and low level (0.25)
c. With no initiation-signal present, the red light should be off (0.25), and the blue light should be on (0.25)
d. The red light indicates on when the solenoid is energized for valve opening (0.5). The blue light indicates on when a a high pressure in the tail pipe does not exist (0.5).
o. Excessive air supply pressure (0.5) can cause inadvertent opening.

REFERENCE CNS Nuclear Pressure Relief System, pg NPR 6, 7-10, Fig 3 ANSWER 3.04 (2.00)

3. Increased steam flow causes steam header pressure to decrease.

DEH closes down on the governor valves to maintain the steam pressure setpoint (1.0) or similar explanation.

b. Increased reactor power causes steam header pressure to increase.

DEH opens the governor valves until the load reference limit is reacned. At this point the increase in steam header pressure would overcome the bypass valves close bias and DEH would start to open the bypass valves (1.0) or similar explanation.

REFERENCE CNS DEH System Description, pg 29, 30

'22L_INRIBU5ENI1_8NQ_QQNIBQL1 PAGE 29 ANSWERS --' COOPER -86/08/07-GRAVES, D.

ANSWER 3.05 (3.50)

c. ' Pressure (0.33) and temperature (0.33) sensors in the SJAE

-discharge piping (0.33).

b.- The SJAE inlet' isolation valves shut (0.5).

c.- Offges rad monitors (0.5) with a 15 minute time delay (0.25)

Dilution fan low flow _ (0.5) with a 5 minute time delay (0.25)

Offgas timer switch to CLOSE (0'5) with no time delay. .

REFERENCE CNS-Offges and Augmented Offgas Systems Description, pg 31-32 ANSWER 3.06 (1.50)

Ycs, it is normal (0,5). The drive piston moves the RPIS magnet past the "00" reed switch and actuates only the green full-in " overtravel" reed switch (1.0).

REFERENCE CRD System Description, RMC System Text ANSWER 3.07 ( .50) 4 or tur'.ine control fluid pressure (0.5)

REFERENCE RPS System Description, pg 12 i

! ANSWER 3.08 (2.00)

- The system will automatically restart when level decreases to the initiation setpoint (1.0).

- The high level trip signal may be reset and the system will restart (1.0).

I t REFERENCE l HPCI Lesson Plan, Rev 0, pg HPCI-8, 32 l

l l

l

~.-. .-

21._4N1,IBUMENI1_8ND_QQNIBQLS PAGE 30 ANSWERS -- COOPER -86/08/07-GRAVES, D.

ANSWER 3.09 (3.00)

c. APRM channels ( 0. 5 3 '

RBM channels (0.5)

Recirc loop flow recorder (0.5) b.- - recirc loop flow recorder.

- rod block

- " Flow Ref. Off Normal" annunciator

- "Compar" indicating light (3 required at 0.5 each)

REFERENCE APRM System Description, pg'APRM-8

~

ANSWER 3.10 C. 50)

True C'.5). O REFERENCE APRM System Description, pg APRM-9 ANSWER 3.11 (2.50)

c. The NMS shorting links must be physically removed (1.0)
b. If the IRM indicates a Hi-Hi (0.25) or INOP (0.25) condition with its companion APRM indicating a downscale condition (0.5).
c. RUN (0.5)

! REFERENCE RPS System Description, pg 18-19 ANSWER 3.12 (1.00)

An equalizing valve leak allows the pressure in the reference and

-variable legs to equalize. This causes a zero differential pressure between the two legs. This causes the level to indicate high.

(0.5 for high, 0.5 for zero dp explanation) ,

t

-- _ , , _ _ _ . - - - - , . _ . - . .._._____,__mm,, _ _ _ _ - . . _ _ _ , - _ , . _ , , -,,,_...,..m-- ,,--..m , . . ~ , , . ,

2it_INIIBWHENIS_8NQ_GQNIBQL1 PAGE 31

-ANSWERS -- COOPER -86/08/07-GRAVES, D.

REFERENCE.

. Nuclear-Boiler. Instrumentation System. Description, pg 22 1

4 1

e i

r 4

,+rny-. .-p --n.g.n,. . -. ., .,_-,...~-m . , . .

r- .. , , , a,- ,m.g,,nang,,-. w,m._,_..,,m,,,,,,.,-.,,.-,,,_n,-w,,m,,,.

r-iz2_E89SEQUBE1_=_NQBd8Lt_8tNQBd8Lt_EMEBQENQ1_8ND PAGE 32 88DIQLQQ1Q8L_GQNIBQL ANSWERS -- COOPER -86/08/07-GRAVES, D.

ANSWER 4.01 (2.50) c.- Scram or half-scram (0.5)

b. 1. red
2. green
3. white (0.5 each) c.. An SRO licensed individual (0.5)

REFERENCE CNS Alarm Procedure 2.3.1, General Alarm Procedure, Rev 9, pg 4,7

' ANSWER 4.02 (2.00)

- Failure of the CRD pumps stops cooling water to the drives (0.5),

shortening seal life (0.5).

- Failure of the CRD pumps also allows the CRD accumulators to slowly depressurize (0.5). At low reactor pressures, the accumulators are required to ensure that the control rods are fully scrammed within the required time (0.5).

REFERENCE CNS AP 2.4.1.1.4, Loss of CRD Pump, Rev 6, pg 2 ANSWER 4.03 (2.50)

e. - Reactor Building RCIC Pump Area

- Control Building Cable Spreading Area

- Turbine Building 4160V Switchgear Room

- Turbine Building Control Corridor, 882'

- Telephone Switchboard in the Administration Office

- Reactor Building 931'6" instrument racks (3 required at 0.5 each)

b. - Deenergize the APRMs at the RPS Power Panels (0,5)

- Trip the Scram Discharge Volume High-High level switches (0.5)

REFERENCE CNS'EOP 5.2.1, Shutdown From Outside the Control Room, Rev 13, pg 1,2 i

- $Aa_RBQGEQUBE1_=_NQBd8Lt_8BNQBd8L&_EMEBQENQ1_8NQ PAGE 33 88DIQLQQ1Q8L_QQNIBQL

', EANSWERS -- COOPER -86/08/07-GRAVES, D.

ANSWER 4.04 (2.00)

- Scram the reactor

- Trip the turbine

- Isolate.the.RWCU system

- Shut down both recirculation pumps and associated oil pumps when the MG sets have stopped (4 at 0.5 each)

REFERENCE CNS E0P 5.2.3, Loss.of All Service Water, Rev 8, pg 1 ANSWER 4.05 (1.00)

Filling the RWCU domineralizers with borated water and inj ecting this via the RWCU system (1.0).

REFERENCE Ecergency Procedure 5.2.14, Alternate Means to Inj ect Boron to RPV, Rev 0 ANSWER 4.06 (2.00)

, c. Place the mode switch in REFUEL (0.25) and check the Refuel Permissive Light (0.25) illuminated.

Observe all green full-in lights on Panel 9-5 i lluminated (0.5).

b. Shut with individual control switches (0.5).

Place the mode switch to RUN (0.25) when reactor pressure is less i than 825 psig (0.25).

I REFERENCE GOP 2.1.5, Emergency Shutdown from Power, Rev 7, pg 2 I

l'

+ ' - P-mW-"v"-#w"--='T-

+m e p - *,ew- -mwe-v-, -v' --vw--*-m r v ys- Tvy-^--- +'w -*---:-e-m-7 e- -a**mm=y""---*-r-'-=v --f 'v v P'v*-W w"=ptmw

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SA>_BBQGEQkBE1_=_NQBd8Lt_8BNQBd8Lt_EMERGENGl_8NQ PAGE- 34 88019LQEIG8L_GQNIBQL

-ANSWERS -- COOPER -86/08/07-GRAVES, 0.

ANSWER 4.07 (2.00)

'o . 150 MREM /25 MREM per hour = 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> (0.5 for the 150 MREM limit, 0.5 for the stay time)

b. Remove self from the radiation field (0.5).

Report the incident (0.25) to individual's immediate supervisor (0.125) and to Health Physics (0.125).

REFERENCE HPP 9.1.1.3,. Personnel Dosimeter Program, Rev 20, pg 4 HPP 9.1.2.1, Radiation, Contamination, and Airborne Radioactivity Limits, Rev 15, pg'5 ANSWER- 4.08 (2.50)-

o. The 3 GEMAC's and associated recorder on panel.9-5 (1.03
b. The Yarways may be monitored locally in the Reactor Building (0.5).
c. The reactor vessel level reference legs will begin to flash when the RPV pressure approaches saturation pressure for the drywell temperature, causing erroneous high reactor level indication (1.0).

REFERENCE CNS E0P 5.2.5.1, Loss of All Site AC Power Station Blackout, Rev 3, pg 3 i

ANSWER 4.09 (2.00)

. c. 5
b. 3
c. 1 i d. 2 (0.5 each)

REFERENCE i CNS GOP 2.1.1, Cold Startup Procedure, Rev 43, pg 8,9 i

I i

I 1

W 8A_tESQGEQUBER_=_NQBd8Lt_8BNQBd8LI_EMEBEENQ1_8NQ PAGE 35

'88DIQLQEIQ8L_QQNIBQL ANSWERS -- COOPER -86/08/07-GRAVES, D.

ANSWER 4.10 (3.00)

s. A pushbutton on the control panel (Bd-C). turns on a blue flashing light in each Diesel room, alerting the operator to contact the

. control room (1.0).

b. Adj ust diesel engine speed (0.2) using the governor control switch (0.2) until the synchroscope is rotating slowly in the clockwise direction (0.4). Adj ust generator voltage (0.2) using the auto voltage adj ust (0.2) until it is slightly higher than bus voltage (0.4). Close the output breaker. at the "5 until 12:00" position (0.4).

REFERENCE CNS Procedure 2.2.20, Diesel Generator, Rev 20, pg 3 , <4 , 14 ANSWER 4.11 (2.50)

c. This can overpressurize the pump casing C.1.0).
b. This can cause a cold water injection to the RPV (0.5).
c. This may cause excessive jet' pump vibration (1.0) and damage.

REFERENCE CNS Procedure 2.2.68, Reactor Recirculation System, Rev 25, pg 13, 15 CNS Procedure 2.1.15,: Reactor Recirculation Pump-Startup and Shutdown,

-Rev 17, pg 1 ANSWER 4.12 (1.00) b is the desired method of operation (0.5). Operation continuously at icw pressure shortens the seal life (0.5).

REFERENCE CNS Procedure 2.2.68, Recirculation System, Rev 25, pg 15

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