ML20210N874

Exam Rept 50-254/OL-86-01 on 860331 & 0401-02.Exam Results: All Nine Candidates Passed Exam.Master Copy of Exam Encl

ML20210N874
Person / Time
Site:	Quad Cities
Issue date:	04/30/1986
From:	Biship M, Bishop M, Burdick T, Hanek J, Morgan T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20210N854	List: ML20210N849 ML20210N874
References
50-254-OL-86-01, 50-254-OL-86-1, NUDOCS 8605050287
Download: ML20210N874 (86)

Text

.

o U.S. NUCLEAR REGULATORY COMMISSION REGION III Report No. 50-254/0L-86-01 Docket No. 50-254/265 License No.

Licensee: Commonwealth Edison Company Facility Name: Quad Cities Nuclear Station Examination Administered At. Quad Cities Examination Conducted: March 31, April 1 and 2,1986 Examiners: T. L. Morgan d 8 Ddte h

B sh Ddte/

Yftyvik-(4 L l Approved By: Thomas M. Bur ck D

! Chief, Operating Licensing Section ga te/

i Examination Sumary Examination administered on March 31, April 1 and 2, 1986 (Report No. 50-254/

OL 86-01) to seven R0 and two SRO candidates. An examination was also administered to a General Electric instructor.

Results: All candidates passed the examination.

l l

l l

l 8605050287 860430 PDR V

ADOCK 05000254 PD1

REPORT DETAILS

1.

• Examiners

• 1. L. korgan, INEL J. F. Hanek, INEL M. O. Bishop, INEL

• Chief Examiner

2. Examination Review At the conclusion of the written examination, the questions and answers were given to the facility training staff for review and comment. At the exit meeting the facility supplied the examiners with their comments to the R0 and SR0 written examination. On the following pages are the facility comments and the examiner's resolution to each.

3. Exit Meeting At the conclusion of the site visit the examiners met with representatives of the plant site to discuss the results of the examinations. Those individuals who clearly passed the oral examinations were identified in this meeting. The examiners made the following observations:

a. Areas of common weakness were found in electrical theory and breaker designation, neutron detector operation, the n';w E0P usage and training, and the feed water level control system canponents (feed regulation valves).

b. The copy of the E0Ps found in the control room were poorly copies, i.e., the tett had shifted upward to where part of the text was cut off.

c. A copy of the EDG local shutdcwn procedure could not be located in the EDG room. The local startup and the remote startup and shutdown procedures were present.

d. The facility training department did a very good job in ensuring the examining process went smoothly while at the facility, i.e., security and availability cf the candidates.

2 m

QUAD CITIES 1 & 2 COBOENTS AND EXAMINER RESOLUTIONS EXAM DATE - MARCH 31, 1986 Facility Comment:

1.05 Some students assumed "NPSH is maintained" meant "NPSH remains the same".

Examiner's Resolution:

1.05 Comment noted. This would not be a reasonable assumption for the conditions in this question, therefore, the answer will remain unchanged.

Facility Comment:

2.07 Answer "C". Remote manual trip should be " Local Manual Trip" (error in lesson plan). Group V isolation must be reset prior to resetting the overspeed reset pushbutton.

Examiner's Resolution:

2.07 Answer "C" will be changed to read " Local Manual Trip". The group V isolation reset is not applicable to the question as it is asked, therefore, the answer remains unchanged in regard to this.

Facility Comment:

2.08 c There are two (2) 360' spray rings while the lesson plan implies that there are four (4) 180'.

Examiner Resolution:

2.08 c Comment noted. Since no documentation to prove otherwise was furnished by the facility and lesson plan LIC-1400, Page 12 of 35, Section 11.0 states there are four (4) spray spargers the answer will remain un-changed.

Facility Comment:

2.12 The list should include " Condensate Demin Air surge Compressor". This has been a modification recently installed.

Examiner's Resolution:

2.12 Comment verified per P&ID M-68. " Condensate Demin Air Surge Compressor" will be added to answer. Point value remains unchanged.

Facility Comment:

3.07 c Lower 400" should also be acceptable.

Examiner's Resolution:

3.07 c Answer for part "c" will be modified such that " lower 400" is also an acceptable answer since this is common operator usage at the facility.

Facility Comment:

3.10 120 second timer has been reset to 110 seconds for suppression pool downcomer water level considerations.

Examiner's Resolution:

3.10 Comment verified by Document No. M-4-2-82-32 and Memo, Michael S.

Tucker to N. J. Kalivianakis, Main Steam Relief Valve Logic Change Modification M4-1(2)-82-32 AIR 4-82-26 Station 4 Quad Cities, of October 15, 1982. Answer will be changed to "110 sec, timer timed out". Point value remains the same.

Facility Comment:

3.11 E Recirc pump trip is not part of ECCS. RCIC not on Tech Spec list of ECCS systems.

Examiner's Resolution:

3.11 E Comment is valid. Recirc Pump Trip and RCIC isolation will be removed from answer. Point value for the question will remain the same.

Facility Comment:

4.01 220-4 Main Steam Line Drain valve gets closed at 100 psig and the rest are closed after synchronizing.

Examiner's Resolution:

4.01 Comment verified by OGP 1-1 Normal Unit Startup, Rev. 35. Page 9, step i (1) and Page 16, step s (7). Answer will be modified to accept 2

"100 psig" or "900 psig" if explanation is written in on candidates answer sheet. Point value remains the same.

Facility Comment:

4.06 a If scram has not occurreo, enter normal 00P's as per QGA's.

Examiner's Resolution:

4.06 a Comment verified by OGA-00, QGA Manual Preface, Rev. 3, Page 1, General Caution #1. Answer will be changed to read: " Enter QGP (2-3), Reactor Scram if a scram has occurred or Normal Plant Operation, QOP's if no scram has occurred. Point value remains the same.

Examiner Change:

3.09 Add "will accept 2 inches for each level in" "c" and "d" for full credit.

Reason For Change:

Allowable range for full credit answer left off answer key and discovered during grading of-test.

i 3

6 .

1 QUA0 CITIES SR0 Facility Comment:

t 5.01 Our lesson plan also lists the reactivity of the rods not inserted.

EXAMINER RESOLUTION:

5.01 Comment not valid: Page 11 of SBLC lesson plan lists the answer exactly as shown on the answer key.

FACILITY COMMENT:

6.01 a. The 120 second timer has been reset to 110 seconds due to pressure suppression downcomer consideration,

b. Pressing the 2# reset will reset the timer if it hasn't timed out if 2# still exists the timer will restart.

EX'. MINER RESOLUTION:

6.01 a. Comment valid: Documentation supplied that shows setpoint change from 120 to 110 seconds.

b. Comment valid: Review of ADS logic indicates that resetting drywell l pressure will deenergize ADS timer.

FACILITY COMMENT:

6.02 a.1, Load reject should be followed by "TCV Fast Closure", not FASTC l

low pressure.

j EXAMINER RESOLUTION:

6.02 a.1. Comment not valid: Page 27 of LiC 5100/5600 lists three scrams f

and associated bypasses from the main turbine as follows:

Main stop valve less than 90% open, generator load reject, and FASTC low pressurt of 900 psig. Table 1 of LiC 0500-1 (RPS) lists these same scrams and bypasses.

l l Facility Comment:

l l 6.04 " Remote Manual Trip" should read " Local Manual Trip" and Group V I

isolation must be reset prior to resetting RCIC turbines.

l l

{

f Examiner Resolution:

6.04 Local manual trip will be accepted. Question did not ask for conditions to reset the RICI trips. Therefore Group V is not part of answer.

Note: Assure facility comment is referring to Question 6.05.

Facility Comment:

6.06 c. There are two (2) 360 spray rings while the lesson plan states that there are four (4) 180*.

Examiner Resolution:

Comment noted: Lesson plan 11C-1400 Page 12 of Section 11.0 states there are four (4) spray spargers therefore answer will remain un-changed. No reference data was supplied to support facility comment.

Facility Comment:

Recirc pump trip is not part of ECCS. RCIC not on Tech Spec List 6.09 e.

of ECCS systems.

Examiner Resolution:

6.09 e. Comment valid: Recirc pump trip and RCIC Isolation will be removed from answer. Point value for the question will remain the same.

Facility Comment:

7.01 a. There is no nine second time delay on the ARI valves.

Exaniner Resolution:

7.01 a. Comment valid: Documentation supplied to support facility comment, reference 4E-7573F ATWS trip schematic. Nine second time delay was deleted from the answer key. Point value remained unchanged.

Facility Comment:

7.09 a. Can come from tramp uranium.

Examiner Resolution:

7.09 a. Comment not valid. Question states that the plant is operating at 100% power and an increase in the airborne radiation level is detected, tramp uranium would be part of the normal background levels.

2

.  ; j 1

\

Facility Comment:

8.02 a. There are different requirements listed in QAP 1100-7 for temporary changes that change the intent.

Examiner Resolution:

8.02 a. Comment valid: Answer key will be changed to include the additional requirements of technical staff supervisor. Assist Supt. Operations and Operating Engineer. Point value will remain the same. Either answer will be acceptable.

Facility Comment:

8.04 c. Question asks for power supplys/MCCS but the answer gives breakers ire the 901 and 902 panels. It should be RPS panels. '

Examiner Resolution:

8.04 c. Comment valid: Answer key will be reworded to. indicate that the breakers in the RPS distribution panels which feed the 901 and 902 panels are tripped point value remained the same.

Facility Comument:

! 8.07 a. False (not true)

Examiner Resolution:

l 8.07 a. Comment valid: Answer key will be changed from true to false.

Facility Comment:

8.10 b. QAP 300-12, Page 2 states that the operating engineer audits the jumpers and blocks once per month, also the daily audit is done by the Shift Foreman which is the Shift Engineer's designee.

. Examiner Resolution:

l l 8.10 b. Comment valid: Either answer is acceptable. Answer key will be f changed accordingly. Point value will remain the same.

1 3

f n .

U. S. NUCLEAR REGULATORY COMMISSION

. REACTOR OPERATOR LICENSE EXAMINATION FACILITY: _ QUAD CITIES 1&2 REACTOR TYPE: -BWR-GE3 DATE ADMINISTERED: 86/03/31 EXAMINER: _MQBGAN. T.

APPLICANT:

INSTRUCTIONS TO APPLICAEIl 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 grade requires at least 70% in each category and a final grade of at least 80%. Examination papers will be picked up six (6) hours after the examination starts.

% OF CATEGORY  % OF APPLICANT'S CATEGORY VALUE TOTAL SCORE _YALUE__ CATEGORY

_g1 00 _05.00 -

-____ __-- _ 1. PRINCIFLES OF NUCLEAR POWER PLANT OPERATION, THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW

_24.50- _24.12 - - _ _ 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS 25.50 _01 50 3. INSTRUMENTS AND CONTROLS

_25 00 _ZE Q2 - 4. FROCELURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CJNTROL 122.2a__ 100.00 - - ____ __ TOTALC FINAL GRALE  %

All work done on this examinatien is my own. I have neither givan nor received aid.

~~~ ~~

AEPLICANT'S SI6 NATURE

1. PRINCIPfFR OF NUCf.FAR PCWER PLANT OPERATION. PAGE 2 THERMODYNAMICS. HEAT TRANSFER AND FLUID FLOW QUESTION 1.01 (3.50)

Concerning the core thermal limits:

a. For each condition (1-4) given below, INDICATE whether it will cause an INCREASE, a DECREASE, or have NO EFFECT on CRITICAL POWER.

1) Local peaking facter (LPF) INCREASES i

2) DECREASE in inlet nubcooling

3) INCREASE in reactor pressure

4) Axial power peak shifts from BOTTOM to TOP of channel (2.0) i

b. With regard to MAPRAT:

1) WHAT is the relationship between MAPRAT and MAPLHGR?

2) IS a MAPRAT of 1.05 acceptable?

3) WHAT physical consequence could occur if the MAPRAT limit is exceeded? (1.5)

QUES? ION 1.02 (2.00)

For the following transients, indicate which coefficient of reactivity; alpha T, alpha D, cr alpha V tends to change reactor power FIRST and what EFFECT does it have on power (increase /

decrease).

a. Fast closure of one MSIV.

b. Isolation of a feedwater heater string.

c. A control rod drop.

d. Relief valve lifting (opening). (4 @ 0.5 ea) l

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

o .

PAGE 3 W INCIPTTR OF NUCfFAR POWER PLANT OPERATION.

TmtRMODYNAMICS. HEAT TRANSyn.n AND FLUID FLOW QUESTION 1.03 (3.00)

o. Fill in the blanks with one of the given choices in the paragraph below.

As a shallow rod is inserted during power operation, the power in the region above the blade tip [1]

(INCREASES, DECREASES) causing a(n) [2] (INCREASE, DECREASE) in void concentration in the upper region of the bundle. This results in a [3] (POSITIVE, NEGATIVE) reactivity addition due to the void coefficient of reactivity.

If the reactivity from the chinge in void concentration exceeds the reactivity added by the '6serted rod, power will [4]

~

(INCREASE, DECREASE) slightly. [4 0 0.5 ea) (2.0)

b. Concerning control rod worth during a reactor startup with 100%

peak xenon versus a startup with xenon free conditions, WHICH STATEMENT IS CORRECT? (1.0)

1. PERIPHERAL control rod worth will be LOWER during the 100%

peak xenon startup than during the xenon free startup.

2. CENTRAL control rod worth will be HIGHER during the 100% peak xenon startup than during the xenon free startup.

3. PERIPHERAL control rod worth will be HIGHER during the 100%

peak xenon startup than during the xenon free startup.

4. BOTH CENTRAL and PERIPHERAL control rod worth WILL BE ThE SAME regardles: of core xenon concentration.

I l

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

\

a .

PAGE 4

1. PRINCIPLWA OF NUCLEAR POWER PLANT OPERATION.

TmtRMODYNAMICS. HEAT TRANSFER AND FLUID WM QUESTION 1.04 (3.00)

Indicate HOW each of the coefficients are effectei 1.e., become more negative, less negative, or remain the same, by each of the three parameters listed? Consider each parameter separa.ely.

(Nine answers required for full credit.)

c. Rod Worth (delta K/K/ Rod) by:

1. Moderator temperature INCREASES

2. Voids DECREASE

3. Fuel temperature INCREASES

b. Alpha Doppler (delta K/K/ F fuel) by:

1. Core age INCREASES

2. Fuel temperature DECREASES

3. Voids DECREASE

c. Alpha Voids (delta K/K/ % voids) by:

1. Fuel temperature INCREASES

2. Core age INCREASES

3. Control Rod Density INCREASES (9 @ 0.33 ea)

QUESTION 1.05 (3.00)

Describe HOW and WHY a centrifugal pump's discharge head i: affected for each of the following. (Consider each condition sepert ;ely and assume NPSH is maintained in al] cases.)

c. Suction pressure increases, l

b. The discharge valve is throttled closed.

c. The temperature of the fluid, being pumped, increases. (3 @ 1.0 ea) 1

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

1.

• PRINCIPLES OF NUCLEAR POWER PLANT OPERATION. PAGE 5 TmtRMODYNAMICS . HEAT TRANSFER AND FLUID FLOW QUESTION 1.06 (2.00)

The following questions are in reference to reducing reactor power by dscreasing recirculation flow.

(For each of the questions, choose the most correct answer.)

c. Initially when the recirculation flow is reduced the boiling boundary:

1. Physically moves'dewn the fuel rods, be:ause more BTU's per pound mass of water is now being transfered.

2. Physically moves up the fuel rods, because more BTU's per pound mass of water is now being transfered.

3. Physically moves down the fuel rods, because fewer BTU's per pound mass of water is now being transfered.

4. Physically moves up the fuel rods, because fewer BTU's per pound mass of water is now being transfered. ,

(1.0)

b. Reactor power centinues to decrease until:

1. The negative reactivity insertion rate due to increasing void fraction and doppler coefficient ever comes the positive reactivity still present in the core.

2. The positive reactivity insertion rate due to increasing void fraction and doppler coefficient over comes the negative reactivity still present in the core.

3. The negative reactivity insertion rate due to decreasing void fraction and doppler coefficient over comes the positive reactivity still present in the core.

4. The positive reactivity insertion rate due to decreasing void fraction and doppler coefficient sver comes the negative reactivity still present in the ccre. (1.0)

QUESTION 1.07 ;1.00)

HOW is condensate depression affected (INCREASED or DECREASED) by the following chang 2s in the circ water flowing through the condenser: ,

a. Flow decreaso- ',

b. Temperature incresses. (2 @ 0.5 ea)

(t**** CATEGORY 01 CONTINUED ON HEXT PAGE *****)

__~ _ - . .

1.

• PRINCIPr.RR OF NUCLEAR POWER PLANT OPERATION. PAGE 6 THERMODYNAMICS. HEAT TRANSFER AND FLUID FLOW QUESTION 1.08 (2.00)

With respect to the reactor vessel level indications:

a. An increased drywell temperature hes*,s the Level insturment reference leg. The reference leg w4ter density 1. INCREASES /

DECREASES resulting in a 2. HIGHER / LOWER sensed D/P causing indicated level to read 3.___ HIGHER / LOWER than actual level. (1.5)

b. Is reference leg flashing a concern under normal operating conditions? YES or N0? (0.5)

QUESTION 1.09 (1.00)

The following statements are concerned with suberitical multiplication.

CHOOSE the CAPATALIZED word'that will make the sentence correct. .

c. As Keff approaches unity, a LARGER / SMALLER change in neutron level occurs for a given change in Keff. (0.5)

b. As Keff approaches unity, a SHORTER / LONGER period of time is required to reach the equilibrium neutron level for a given change in Keff. (0.5)

QUESTION 1.10 (3.00)

c. Approximately what percentage of neutrens from U-235 are born delayed? (0.5)

b. How does the percentage of delayed neutrons produced in the CORE vary over core life and WHY? (1.5)

c. How do delayed neutrons contribute to the ecntrol capability of a commercial reactor? (1.0)

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

e .

1. PRINCIPLES OF NUCf.FAR POWER PLANT OPERATION. PAGE 7 THERH0 DYNAMICS. HEAT TRANSrik AND FLUID FLOW QUESTION 1.11 (1.50)

In reference to Figure 1 at the back of the exam:

(For questions a & b, choose the most correct answer from the four choices listed below,

s. During core alterations, the 1/m plot takes the shape of Curve 1.

What does this indicate in regard to neutron detector location?

b. During core alterations, the 1/m plot takes the shape of Curve 2.

Whnt does this indicate in regard to neutron detector location?

1. The neutron detector is located too close to the core alterations.

2. The neutron detector is located too close to the source.

3. The neutron detector is located too far from the core alterations.

~4. The neutron detector is located too far from the source.

c. Why would you be concerned if the 1/m plot took the shape of either Curve 1 or Curve 27 (3 @ 0.5 ea)

(** E!!D CF CATECOP.Y 01 * * * * * )

2. PLANT LESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 8 QUESTION 2.01 (3.00)

For the Rod Block Monitor (RBM), provide answers to the following questions ( a thru c):

c. Under what TWO (2) conditions is the REM automatically bypassed? (1.0)

! b. What is the system designed to prevent? (0.5)

c. When the Meter Function Switch on the 00X-37 Back Panel Meter ,

Section is in the " Count" position, what are the " units" of the indication on the meter and what can be calculated by utilising the indicated value? (1.5)

QUESTION 2.02 (2.00)

What are TWO of the THREE purposes for having numerous interlocks associated with the Refueling platferm?

QUESTION 2.03 (3.00)

Attached is a singic line diagram of the RHR System (Figure 2). List the icbeled components shown in the flow path for each of the following modes of the RHR System:

a. Shutdown Cooling

b. Suppression Pool Cooling

c. Drywell Spray QUESTION 2.04 ';.00) l Why is the Standby L;;uid Control System (SLC) designed to require at least ninety (30) m;:.utes to pump the CLC stotage tank contents into the RPV? (0,0)

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

2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 9 QUESTION 2.05 (1.50)

What is the effect on the SBLC system in the event that each of the following systems are lost? (Consider each system separately.)

1. Instrument Air

2. Clean Demin Water

3. Service Air (3 @ 0.5 ea)

QUESTION 2.06 (2.00)

What are FOUR (4) possible causes for an automatic trip of the Reactor Water Cleanup Pump? (Setpoints not required for full credit) (2.0)

QUESTION 2.07 (1.50)

What THREE (3) RCIC turbine trips cannot be reset by the RCIC Turbine -

Overspeed Reset Pushbutton on the 30X-4 panel? (1.5)

QUESTION 2.08 (4.00)

Answer the following questions for the Core Spray System:

a. List the power supply, Bus No., for each of the FOUR core spray pumps. (1.0)

b. What THREE signals will automatically start the core spray pumps. (Setpoints required for full credit.) (1.0)

c. Describe the core spray spargers. Include the number of sparser rings, HOW they are supported and HOW the flow is divided betweer. the :psrgere. (2.0)

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

2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 10 QUESTION 2.09 ( .50)

TRUE or FALSE HPCI is designed to operate without offsite or diesel generator powsr available. (0.5)

QUESTION 2.10 (1.00)

HPCI is designed to provide emergency core cooling during a

. (Three words) (1,0)

QUESTION 2.11 (1.50)

Answer the following in regard to the Area Radiation Monitors (ARM's).

a. What type of dete: tors are utilised for the ARM's? (0.5).

b. If an ARM RECORDER fails, what action must to taken and how often must it be done? (1.0)

QUESTION 2.10 '1.50)

What are SIX ccmp:<nents that would lose ecoling if TBCCW were lost? (1.5)

QUESTICN 2.13 (1.00)

What are the FOUR TE J:W Icada located in the Drywell that would be affected by a loss of RBCCW - *he Drywell?

Do not use similar 1;t !s ( A & B cr 1 & 2) as separate loads.

'+* ENO CF CATEGORY 02 *****)

3.' INSTRUMENTS A'ID CONTROLS PAGE 11 l

l QUESTION 3.01 (1.50)

During operation of RHR in the Shutdown Cooling Mode, the operating RHR Service Water Pump automatically trips. What are the three possible cEuses for this trip?

QUESTION 3.02 (1.00) 1

)

While in the shutdown cooling mode, both reactor recire pumps are lost:

n. What temperature indication would this have an affect on that you would be monitoring in this mode?

1

b. What temperature indication would you monitor after the recire pumps are leat?

l -

QUESTION 3.03 (2.00)

a. What TWO (2; parameters will initiate the loop select logic for the LPCI mode of RHR7 Include cetpoints. >

b. Explain how a recire loop is chosen for the injection flowpath i by the LPCI select logic. A::ume loep Delta-P < 2 psid at initiation signal.

l QUESTION 3.04 (2.50)

What are FIVE (5) autcmatic actions initiated by a ?X normal signal from the main steam line radiation detectcrs. (2.5)

I i 1 I

f I

i 1

4 k

I

(+**** CATEGORY 03 00NTINUED ON NEXT PAGE *****) /

3. INSTRUMENTS AND CONTROLS PAGE 12 i

{

QUESTION 3.05 (3.50)

With the plant operating at 100% power with the recire in Master Manual, an operator inadvertently DECREASES the EHC " Pressure Set" by 5 psi. WHAT will be the the INITIAL response and FINAL status of the following pcrameters due to this action? Briefly EXPLAIN. Assume NO operator cetion. See attached Figure 3, Speed and Acceleration Control Unit.

ANSWER ON THE ATTACHED HANDOUT PAGE.

4

c. TCV position

b. BPV position

c. Power

d. Pressure s

QUESTION 3.06 (3.00)

Rafer to attached Figure 4, Recirculation Speed Control Network, for the following:

a. The plant is operating at 30% power with both recire pump M/A transfer stations in MANUAL. FOR EACH of the following instances, INDICATE HOW the speed of Recire Pump "A" would change (increase, decreacc, or remain the same) AND WHICH component (s) of the control system is(are) limiting.

i

1. Recire Pump 'A" M/A transfer station is placed in "AUT0". (1,0)

3. The generatcr creed tachometer output feedback signal fails low due to a loss of continuity through the field breaker contacts. (1.0)

b. WHAT acticn must be taken by the control rocm operator prior to resetting a 'LOCKEL OUT" scocp tube? WHY? (1.0) 1 QUESTION 3.0? .:.00)

Answer the following in regard to the jet pumps:

a. Which jet pump: 3re fully instrumented? (1.0)

b. Which jet pumpe have in:tramentation taps that also serve RPV level instrumentation? (0.5)

c. Which type of RPV Icvel in:trumentation in fed by tape on the jet pumps? (0.5)

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

3.' INSTRUMENTS AND CONTROLS PAGE 13 QUESTION 3.08 (1.00) '

With the reactor at 100% power the water level in the core region is (a) inches (b) than the water level in the downcomer region due to the pressure drop across the (c),

Only the (d) GE/MAC and yarways are accurate during this condition. (Provide the answer for each blank.)

(4 @ 0.25 ea)

QUESTION 3.09 (2.50)

Answer the following in reguard to RPV water level instrumentation.

a. Why are all the actuation functions associated with RPV water level supplied from the Yarway Instruments? (1.0)

b. What Range of-RPV water level instrumentation is utilised to supply actuation functions associated with RPV water level? (0.5)

c. Narrow Range Yarways provide RPV water level indication from inches te inches on the 90X-5 panel. (Fill in the blanks.) (0.5) l d. Wide Range GE/MAC provide RPV water level indication from l inches to inches on the 90X-4 panel. (0.5)

QUESTION 3.10 (1.00) l l List FOUR of the signals necessary to activate the ADS trip _

l logic "A"? (Setpoints required for full credit) (1.0) i 1

l t

l l

l 3

1

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

l l

a .

3. INSTRUMENTS AND CONTRQLS PAGE 14 QUESTION 3.11 (3.00)

The reactor is operating at 40% power with the Feedwater Control System in eingle element control, and level channel "A" selected for input. The reference leg isolation valve to the channel "A" NR GEMAC develops a significant packing leak and the associated reference leg starts to gradually decrease.

Dascribe the effects on and of the following, assuming no operator action.

Include any setpoints

a. Actual RPV water level (0.5)

b. Indicated RPV water level on channel "A" (0.5)

c. FWLC (0.5)

d. RPS (0.5)

o. ECCS (0.5)

f. PCIS ,

(0.5) 1 QUESTION 3.12 (2.50)

With a Select Error on the RWM the rod can still be moved (Assume the RWM is not bypassed and no rod block existed prior to rod selection).

Explain the rod movement restrictions for both insert and withdraw imposed by the RWM in this situation.

t

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

a . ,

4.' PROCEDURES - NORMAL. ABNORMAL. EMERGENCY AND PAGE 15 RADIOLOGICAL CONTROL j

(

\

l QUESTION 4.01 (1.50)

While performing a normal startup and heatup, per QGP 1-1 " Normal Unit Startup", at what pressure, selected from Column "A", would each of these operations, in Column "B", be performed.

.. A ** B"

a. 100 psig 1. Start a recombiner if not already started.

b. 200 psig 2. Start a Reactor Feed Pump.

. c. 300 psig 3. Start a steam jet air ejector.

d. 400 psig 4. Close steam seal bypass feed valve if the regulator is able to maintain press to seals.

e. 500 psig

5. Verify that the operable recombiner is within

f. 600 psig the allowable band of the baseline plot.

g. 700 psig 6. Close the main steam line drain valvei.

I

h. 800 psig (6 C 0.25 ea.)

1. 300 psig l QUESTION 4.02 (0.50) t l

You are on watch in the control room and you receive a Bomb Threat phone call.

a. Where is the "Roccipt of Ecmb Threat' procedure located?

(Choose one.)

l l 1. QGP

2. QGA

3. 0AP

4. QOP (0.5)

, b. The First step :d the immediate actions states "DO NOT hang up phone when call is completed". What is the purpose of this step? (0.5)

c. What are FIVE :f thc NINE remaining immediate action steps, required by the " Receipt of Bomb Threat" procedure?

! (Credit will n;t b given for the action listed in Part "B".)

(More than one it c:.. may be listed f cr an immediate action step. ) (2.5) l

• • • • • )

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

a 6

4. PROCEDURES - NORMAL. ABNORMAL. EMERGENCY AND PAGE 16 RADIOLOGICAL CONTROL QUESTION 4.03 (1.50)

During testing of one of the main steam relief valves it is noted that the acoustic position detector shows that the valve did not reset properly.

What are the immediate operator action steps required by QOA 201-2

" Failure of a Relief valve to close or to reseat properly? (1.5)

QUESTION 4.04 (1.00)

During turbine shell warming WHY is it important that the MSDT's emergency drain valves be closed?

QUESTION 4.05 (2.50) ,

According to QGP 1-1, Normal Unit Startup:

a. If a proced e is terminated at any time during its execution, several things must se done to the precedure. List four of these things that must be done. (2.0)

b. A sustained reactor period Of  ? shall not be allowed.

[ Fill in the blank.] (0.5) l l QUESTION 4.06 (2.00)

Answer the following questions in reqard to the SEVEN (7) general CAUTIONS in procedure QGA Manual Preface:

a. Which procedure is entered when it is determined that an emergency no longer exists?

b. When RHR is in the LPCI mode, inject through the  ? (2 words) as soon as possitie. (Fill in the blank.)

c. How is Suppression Pool Temperature determined?

d. What two (2) parameters can be determined from the graphs in Caution #7 in regard to NPSH requirements for pumps taking sucticn from the suppression pool?

(4 @ 0.5 ea)

(***** CATEGORY 04 CONTINUED ON NEXT PAGE tttt*:

4. PROCEDURE - NORMAL. ABNORMAL. EMERGENCY AND PAGE 17 RADIOLO'3ICAL CONTROL QUESTION 4.07 ( .50)

[TRUE OR FALSE)

Once an Emergency Operating Procedure has been exited, it need not be re-entered even if an entry condition is reached.

QUESTION 4.08 (2.00)

List the four (4) entry conditions for QGA 100-1, Reactor Pressure Vessel Water Level Control. (Setpoints required for full credit.)

QUESTION 4.09 (2.00)

List four (4) of the five (5) entry conditions for QGA 300-1, Secondary Containment Temperature Control. (Setpoints required for full credit)

QUESTION 4.10 (1.50)

Answer the following in accordance with QGP 2-1, Normal Unit Shutdown:

a. Why is it undesirable to open the condenser vacuum breaker with the turbine at high rpm?

b. When is it acceptable to open the condenser vacuum breaker with the turbine at high rpm?

c. What restriction is imposed when it is necessary to open the condenser vacuum breaker with the turbine at high rpm?

(3 @ 0.5 ea)

QUESTION 4.11 (2.00)

Immediately prior to placing the Mode Switch in RUN during executien of QGP l-3, Unit Hot . Standby to Power Operations, 5 actions are necessary. List 4 of these actions.

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

a .

4. PROCEDURES - NORMAL. ABNORMAL. EMERGENCY AND PAGE 18 RADIOLOGICAL CONTROL QUESTION 4.12 (2.00)

State which emergency classification is appropriate for the l following definitions.

a. Events in progress or have occurred which involve an actual or potential substantial degradation of the level of safety of the Plant.

4

b. Events in progress or have cccurred which involve actual or likely major failures of plant functions needed for the protection of the public.

c. Events in progress or have occurred which indicate a potential degradation of the level of safety of the plant.

d. Events in progress or have occurred which involve actual or eminent substantial core degradation or melting with potential for Loss of Containment integrity.

(4 @ 0.5 ea)

QUESTION 4.13 (3.00)

Concerning the use of radiation dose meters, answer the following TRUE or FALSE.

a. Before entering a suspected radiation area, the meter selector switch should be turned to the highest range.

b. Earphones are only required in areas of low light conditions.

c. A GM detectcr is preferred for setting dose rates.

l 60 137

d. Check sources cf c:lbat (CO ) or cesium (CS ) one micro currie each will indicst' the same reading using a CP(Cutie Pie).

(4 @ 0.5 ea) l l

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

4. PROCEDURES - NORMAL. ABNORMAL. EMERGENCY AND PAGE 19 RADIOLOGICAL CONTROL QUESTION 4.14 (1.00)

Match the Technical Specification Section in Column 1 with the appropriate title in Column 2 (4 @ 0.25 ea) column 1 Column 2

1. Section 1 a. Administrative Controls

2. Section 3.0/4.0 b. Definations

3. Section 5 c. Design Features

4. Section 6 d. Limiting Conditions for Operation (General)

e. Limiting Safety System Setting Bases l

I l

l l

1 l

(+**** END OF CATEGO?tY 04 *****)

(************* END OF EXAMINATION t********+****+)

l

4 l

.;,.. g

/ s2-F /

//

/,, // _y '

/ //

/ '

/ '

/ . l 3'E

,/ 9 o 1 9

= / l ,

l O / t 4 i 9 0 / '

I 5 l l -= i cm

• t

/ i  ! c O! /

e -

/

-e s.

O , g,

/ / -- e. u

/ } '

l / /

, /  :

~u

?

f I l e C'

/ '

u.

/ / .L ., c o/

r

%s/,

/ I i

a u

! .1

.- r'  :

l o

12 74 e u  %

r- ->

~ / 8_ l

- , o d i a l

A B / s 8

_ .,E

/ 4

s. _M C

/ m b

.,. e s

/ y. 20 a o

/ _ , .

/

/ ..-

l/

6 4

4 D

I i

9 4

T

{

U l

U 4 4 3 *1 "

LJ/l, -

,. m o # m e - en--e m - - - m-**m

< Z

=

i o_ 2 re_7=

i s_ _ _ -. N l

I l l l

-  ! e g  !

i JJJ c  !

! l [E-E__*

-x-x-l . ._. '

dr  !

l LEJ GD J" "1 .i  ; g' l

.I I __a ,

l l l i .* g < '

l  ;

_R x . >

i

-T i.,______.._, ,7 o' l

'g fg lg -i-X-N '

I a

! Z F-

, Ta-

n W,

7-

LJ p3  :

-ir

-x-N g 3

..)

' ~

= u g l-Q] ~

m~ >~7 V

'q

_, V 3

J E I-3 Y f. , % b I- L to 4* !t:S 2._O LU 0 -x1 I C

-e o Ll - ,

r ..

~

U N' k- ,s

• 8  !

' Edi m

g f

ii f )\ "g W

a t > ..

W~

1 J l

• o

• e e x  :< h. ly L

N F y ii. -

e,  :< .=

y 3

J<

F -

V . .

I

?

e

3 1g* !s s is s s

1 =_li i 's

.x

- 3

.si I*alI  !*s E>s  !

E i

a el-E a

a -

i 1 a-a i.H =

S l h

= -~

3 $ l4 -s

• N J J

s ,

g a j s lsasl.* =

o gjg.y. , ;cg,  ; g

==y=======g i 3  :

., a ,

6s

=

su x t , I iq  !

x

= => ---@,  ;  ;

• g 4=g na ~

! ~)  ! *'b 'kr Ti (d l i

l a >-Mi 1 . -- i.

d,pp s .r. _ . . . .!

I,g E gg E I.' I g

• 1 5-g!! -

r a

s a

t- k q !! If rea n-

'b=

- n.

n I'

t ,

g -

s, r

= s wC,,.laa. 2 e

=m , ..

t. .

~ n i!!

~ -

ll  !!.i. @ ga @ ! !!_

1l -

.: i -. .

O

c %e  : soc (asMore comeu I

asma A M CoNTRoLLEn I .

O use .

O """

. to y too, spuo Co m et 2 M/A .A. RSCRC toCP rRANsFR 3pgD CoNTRot o STATIoM DUE m uNn s

. 1. - - - . .---

I como wMee amo4anos

. srAar soNa Q umm ~~ V"V8 'un croe aemama aos I anse w - e.w.

- nanosomi O 27 -

now 22as pdv -v am m aica ,, _ _ , , eson N , o 2 o ummNo MErWoEK SONE y y UAOE8EE3 I U .

A i GllNf90um SPufp/sMrD > %O

% -cer "T" CONTACTS amarca sNowN paa m.o essaan opee ,

7 _ _ _ _ _ _ _ .,I f

pas .. scoe, M TUM Figure A Recirculation Speed Control Network

.. _ . . __ ___ _. 6' i _

b

}

ANSWER SHEET for Questien 3.05

. INITIAL RESPONSE:

a. TCV position (in % steam ficw demand)

b. SPV position (in % steam ficw demand)

. Pcwer 1

((increase, decrease.or

d. Pressure F. rer.ain the sarne)

J Reasen:

l i

(

i l

l

.:'.NAL 5 ATUS:

3. TCV ::sition _ 'in % steam flew demand)

5. 37V positi:n (in % steam flow demand)

c. Power (nigher than, icwer than, or

d. Pressure '> the same as the initial value)

~

l Reason:

l l

l

{

1 l

1 l

l

1 EQUATION SHEIT C/cle efficiency = (1stwort f . .se v = 1/t cut)/(Erergy in)

. 3g s = V3 t

• 1/2 at g = x- A=Aeg A = AN

<g . 1/2 av a = (Vf - 13 )/t PE = agn

• = e/t A = ml/t1/2

• 0 3'3/81/2 vf . v, . at # 1/taff = C(tti,)(b)]

- 2

• • "# A= '$ C(c1/2)

• l 5 13 d * '3I " m v,,A.  ; , g ,-2x a = mCast I=IG g h = QA A T p, = a g I = I, 10-*/'-

f 1"ll. = 1.3/u sur(s) Hvt = -0.693/u 7 = Po- 10

? = Pge"j '

SCR = S/(1 - 4,ff)

SUR = 25.06/T C2 , = 5/(1 - <,ffx)

C2)(1 - < ,pf3) = C22 II ~ *eN 2)

SUR = 25s/t= + (s - o)?

= ( t=/s ) + C(a - s y is ]

M = 1/(1 - <,ff) = CR /CR i 3 M = ( 1 - <,ff,)/( 1 - 4,ff j )

7 = a/(s - s)

T = (a - s)/(Tal scM a ({- <,ff)/K,ff ta = to seconds a = (x ,ff-11/x ,ff = r.x ,ff/x,ff I = 0.1 seconds" s=C(t=/(T(,ff)]+Caff(1+It)] /

I8 11*I82g#22 g1:1

.2 2 P = (:st)/(3 x 1010) R/hr = (0.5 02)/12, (, ,g,7,)

= :s R/hr = 6 CE/aI (feet)

Miscellaneous 0:nversions dater par metem I curie = 3.7 x 10 I0 ces 1 gal. = 3.345 Tem. 1 4g = 2.21 lem 19 1no=2.54x103Stu,Mr 1f]a.=3.73litars

. = 7.44 gal. 1 as = 3.41 x 108 5tu,Nr I Density = 62.4 leg /ft3 lin = 2.54 :m 3ensity = 1 gm/c::ta 4 = 9/5'c + 32 1

r Heat of vacortratten = 970 Stu/lem 'C = 5/9 ( ? -32) dont of fusion = 144 Stu/1cm 1 STU = 778 ft-lbf 1 Aca = 14.7 sti = 29.9 in. Hg. .

1 ft. H 2O = 0.4335 1:f/in.

s a l . .

II PRINCIPLES OF NUCLEAR POWER PLANT OPERATION. PAGE 20 THERMODYNAMICS. HEAT TRANSFER AND FLUID FLOW ANSWERS -- QUAD CITIES 1&2 -86/03/31-MORGAN, T.

MASTER COPY ANSWER 1.01 (3.50)

a. 1. Decreases

2. Decreases

3. Decreases

4. Decreases [4 @ 0.5 ea]

b. 1. MAPRAT is the ratio of APLHGR TO APLHGR Limit OR the ratio of APLHGR(act) to MAPLHGR(LCO) (Either answer acceptable for full credit.)

2. NO

3. The clad temperature can exceed 2200 degrees F. during a DBA LOCA [3 @ 0.5 ea]

REFERENCE HT&FF, pg. 16,17; GE Thermodynamics, HT&FF, pg. 9-85 to 9-89 Guad City'HT&FF, BWR Thermal Limits Ch 9, pg 9-24, 26, 28, & 23 ANSWER 1.02 (2.00)

a. Alpha V increases power

b. Alpha T increases power

c. Alpha D decreases power

d. Alpha V decreases power (4 @ 0.5 es) i REFERENCE G.E. SWR Transient Analysis Guad City, Reactor Theory, VI.B.C.D. pg 46 - 56 ANSWER 1.03 (3.00)

a. 1. DECREASES

2. DECREASE

3. POSITIVE

4. INCREASE [4 @ 0.5 ea] (2.0) l

b. 3. (1.0)

REFERENCE NSP LP Rx Theory Quad City, Reactor Theory, VII.D.3.b & c pg 62 & 64 of 85,

1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION. PAGE 21 THERMODYNAMICS. HEAT TRANSFER AND FLUID F_ LOW ANSWERS -- QUAD CITIES 1&2 -86/03/31-MORGAN, T.

VIII.B.6, 7, & 8 pg 70 of 85 ANSWER 1.04 (3.00) a.1. more a.2. more a.3. remains the same b.1. more b.2. mor3 b.3. less c.1. more c.2. less c.3. more [9 9 0.33 ea]

EEFERENCE Monticello, Reactor Theory L.P., # M8102L-043 Rev 0, Figure 43 pg 43 of 43 Quad City, Reacter Theory Figure 46 and VII.C.1-6 pg.58, 60, & 62 of 85 ANSWER 1.05 (3.00)

a. Head increases [0.5] the pump is still putting the same amount of work into the fluid, therefore the came delta pre;sure increase across the pump, so as suction pressure increases so will the discharge head [0.5].

b. Head increasen [0.5] as system resistance to flow increases, pump head increases [0.5].

c. Head decreases [0.5] as temperature increases system resistance to flow decreases (1cwor viscosity); therefore head decreases [0.5].

REFERENCE Monticello, Thermodynamics and fluid flow ch 7 pg 111 Quad City, HT & FF Fluid Statics, Pump Characteristics, pg 6 6-102 ANSWER 1.06  : .00)

a. 1.

b. 4. (2 @ 1.0 ea)

REFERENCE Dresden Heat Trancfcr & Fluid Flow Quad City, Reactor Theory, X.E.3.g-k pg 82 of 85

1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION. PAGE 22 TERMODYNAMICS. MAT TRANSFER AND FLUID FLOW ANSWERS -- QUAD CITIES 1&2 -86/03/31-MORGAN, T.

ANSWER 1.07 (1.00)

c. Decreases.

b. Decreases. (2 @ 0.5 ea)

REFERENCE MNS Thermodynamics, pp. 5-18, 5-20, & 5-21.

Quad City, HT & FF Heat Transfer, pg 7-45 ANSWER 1.08 (2.00)

c. 1. decreases

2. lower

3. higher (3 @ o.5 ea)

b. no (0.5)

REFERENCE MNS Lesson Plan No. 1300B, p. 18.

1 ANSWER 1.03 (1.00) l i a. larter l

b. longer (2 @ 0.5 ea)

REtsREMCE RX PHYSICS REVIEW, pg 17 ANSWER 1.10 f3.00)

a. .64% (will accept 6 to .7%) (0.5)

b. Decreases [0.5] d a: to the production of Plutonium 239 hich has a lower. delayed neutron fraction than U-235. [1.0] (1.5) i

c. Delayed neutrons increase the average neutron generation time, i

increasing t..e control time of the reactor by a very large factor. Accentatic answers may vary considerabley from this exact wording. (1.0) i REFERENCE Quad Cities, Reactor Theory, page 10,38,40,& 85

1. PRINCIPLER OF NUCtWAR POWER PLANT OPERATION. PAGE 23 THERMODYNAMICS. HEAT TRANSFER AND FLUID FLOW ANSWERS -- QUAD CITIES 1&2 -86/03/31-MORGAN, T.

! ANSWER 1.11 (1.50) l

a. 2.

b. 4.

c. The criticality predection would not be correct and possibly not conservative. [3 @ 0.5 ea]

REFERENCE QC Lesson Plan - REFUEL - LIC-REFL, pp. 36 and Figure 21, i Section 4.b. and 4.c.

I l

l l

l l

I t

l

2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYS~5MS PAGE 24 ANSWERS -- QUAD CITIES 1&2 -86/03/31-MORGAN, T. l l

\

i 1

ANSWER 2.01 (3.00) i

n. Rx pwr <30% [0.5] or an edge rod selected [0.5]. (1.0)

b. Local fuel damage (by generating a rod withdrawal block). (0.5)

c. Units = volts [0.5], number of operable LPRM inputs can be calculated by using i volt per operable input [1.0]. (1.5)

REFERENCE QC Lesson Plan Rcd Block Monitor - LIC-0700-5 QC Lesson Plan Rod Block Monitor - LIC-0700-5, pp. 2 of 22.

QC Lesson Plan Rod Block Monitor - LIC-0700-5, pp. 18 of 22, Sec. 2.b.(4).

QC Lesson Plan Rod Block Monitors - LIC-0700-5, pp. 21 of 22, Sec III.C.b.

' ANSWER 2.02 (2'00)-

1. Prevent withdrawing control rods from the core during core alterations by means of the Reactor Manual Control System (RMCS).

2. Prevent performing eure alterations while any of the rods are not fully inserted.

l

3. To prevent withdrawing more than one rod while the refueling platform is over the core.

[2 required @ 1.0 each] (2.0)

REFERENCE QC Lesson Plan, Refuel - LIC-REFL, p. 10. Sec. S.a ANSWER 2.0? 30) l a. 50 valve, 47 valv., 43 va]ve, pump, HX or 16 valve, 28 valve, 29 valve, 68 valv>:, and 33 valvc.(HX OR 16 valve acceptable) (1.0)

b. 7 valve, pump, HX, 34 valve, and 36 valve. (1.0)

I

c. 7 valve, pump, HX vr 16 valve, 23 valve and 26 valve. (1.0) l (HX OR 16 valve n;eeptable) l l

e

2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 25

]

ANSWERS -- QUAD CITIES 1&2 -86/03/31-MORGAN, T.

REFERENCE QC Lesson Plan, RHR LIC-1000-1, Fig. 6, Fig. 7, and Fig. 4.

ANSWER 2.04 (2.00)

An excessive injection rate could result in poor mixing [0.5] of the coolant and boron [0.5] and result in reactivity or power chugging [0.5]

which in turn could cause fuel damage [0.5]. (2.0) i REFERENCE ,

QC Lesson Plan - Standby Liquid Control LIC-1100, pp. 11 of 14, Sec. '

IV.A.B.C. l ANSWER 2.05 (1.50) -

l

a. Loss of SBLC storage tank level indication. (0.5)

b. Lces of makeup water to the SELC tanks. (0.5)

c. Loss of air to the Storage tank sparger. (0.5)

REFERENCE QC Lesson Plan - Standby Liquid Control LIC-1100, pp. 13 of 14, Sec V.

l ANSWER 2.06 (2.00) l l a. Pump Low Flcw (30 gpm)

b. High bearing cocling water temperature.(140 deg. F) l l c. The TWO valve nc.t full open (CE Inlet Isclation Valve) l l d. The FIVE valve n:: full open (IB Inlet Isolation Valve)

e. EIGHTY talve full :lcaed (Cutlet to FW Hdr.)

[any FOUR (4) @ 0.5 each] (1.0)

REFERENCE QC Lesson Plan - React:r Water Cleanup System - LIC'-1200, pp. 10 of 1 Sec. B.4.

1 l

I -

t

2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 26 ANSWERS -- QUAD CITIES 1&2 -86/03/31-MORGAN, T.

ANSWER 2.07 (1.50)

c. RPV water level high (0.5),

b. Mechanical overspeed (0.5) c . - P.ini o -is -smanual Ltip

seto

/s.. / /? + / /ry 0.5)

REFERENCE QC Lesson Plan - RCIC-LIC-1300, pp. 13 ANSWER 2.08 (4.00)

a. PUMP POWER SUPPLY

~1A 13.1 1B 14.1 2A 23.1 2B 24.1 [0.25 each] (1.0)

b. High drywell prescure (0.25], low-low RPV water level, -59"

[0.25] and low RPV pressure, 325 psig [0.25], RPV water level at -59" for 8.5 min. [0.25] (1.0)

c. FOUR 180 degree sparger rings [0.5], supported by brackets on the core shroud [0.5), each of the TWO levels is supplied by one core spray system [1.0]. (2.0)

REFERENCE

a. QC Lesson Plan LIC-1400, pp. 6 of 35, Sec. 4.C.

b. QC Lesson Plan LIC-14CD, pp. 6 of 35, Sec. 4.e.

c. QC Lesson Plan LIC-1400., pp. 12 of 35, Sec. 11.0 ANSWER 2.09  ; .50)

TRUE (0.5)

REFERENCE QC Lesson Plan LIC-2000-1, pp.2

a .

2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 27 ANSWERS -- QUAD CITIES 1&2 -86/03/31-MORGAN, T.

ANSWER 2.10 (1.00)

Small Line Break (1.0)

REFERENCE QC Lesson Plan LIC-2300-1, pp. 2 ANSWER 2.11 (1.50)

3. Gamma sensitive GM Tube (0.51

b. Each ARM must be logged [0.5] once each hour [0.5] (1.0) i REFERENCE ,

QC Lesson Plan ARM LIC-1800, pp. 5 and 10 of 11, Sec II.A.2. and III.B.1.

l ANSWER 2.12 (1.50)

1. Circulating Pump Upper Bearings

2. Service Air Compressors and Aftercoclers

3. Sparge Air Compressors

4. Control Rod Drive Pumps

5. Feed Pump Oil and Seal Coolers

6. Condensate and Condensate Booster Pumps

7. EHC Coolers

8. Bus Duct Coclers

3. Alterex Coolers

10. Turbine Building Process Sampling system Sink

v. 6 i. s. r . i . ,. . . ,. w ,. c. ,, . . . ,

[any ?!X (6) @ 0.25 each] (1.5)

REFERENCE QC Lesson Plan TBCCW LIC-3800, pp. 4 of 7, Sec. II.E.

l

j

2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 28 ANSWERS -- QUAD CITIES 1&2 -86/03/31-MORGAN, T.

ANSWER 2.13 (1.00)

1. DW coolers

2. Recire pump seals

3. Recire pump oil coolers

, 4. DW equip. drain sump HX

[0.25 each] (1.0)

REFERENCE QC Lesson Plan (LIC-3700) pp. 6 Sec A.2 and Figure 1 I

(

i i

3. INSTRUMENTS AND CONTROLS PAGE 29 ANSWERS -- QUAD CITIES 1&2 -86/03/31-MORGAN, T.

ANSWER 3.01 (1.50)

1. Undervoltage

2. Overcurrent l

3. LPCI initiation signal [0.5 each] (1.5)

REFERENCE QC Lesson Plan - RHR-LIC-1000-1, pp. 10 of 67, Sec. B.9.

ANSWER 3.02 (1.00)

a. Recire Loop Temp. (0.5)

b. RHR HX inlet (0.5) l REFERENCE QC Lesson Plan - RHR-1000-1, pp. 50 of 67, Sec. C.4.

i l

ANSWER 3.03 (0.00)

a. Drywell press >/: 2 psig [0.5] and RFV water level '/: -59" l [0.5] (1.0)

b. Injection loop is selected by the comparison of recirc system riser DP's [0.5]. If loop A > B, A is selected and if loop B is >/ loop A, loop B is selected [0.5]. (1.0)

REFERENCE QC Lesson Plan - RHR LIC-1000-1, pp. 44 of 67, Sec. 4 l

l l

l l

3. INSTRUMENTS AND CONTROLS PAGE 30 ANSWERS -- QUAD CITIES 1&2 -86/03/31-MORGAN, T.

ANSWER 3.04 (2.50)

c. Chimney isolation valve closes

b. Air ejector suction valve closes

c. Mechanical vacuum puip trips

d. The off-gas line drain valve closes

o. The off-gas sample vacuum pump suction valve closes

f. Group I primary containment isolation

c. Direct reactor scram (Any 5 at 0.5 ea)

REFERENCE QC Lesson Plan OFF-GAS LIC-5450, pp. 22, Sec. IV.A.2 l ANSWER 3'.05 (3.50) -

INITIAL RESPONSE:

a. TCVs - Remain at 100% cpen (cr open to 100%) [0.35]

b. BPVs - Open 5% [0.35]

c. Power - Decreases (0.35]

d. Pressure - Decreases [0.35]

REASON: Above caused by PCU calling for '115% steam ficw ((350-315) x 3.3) and limited by MCF limit of 105% [0.35]. (1.75)

FINAL STATUS:

a. TCVs - At 100% position (or initial) [0.35]

b. EPVs - Shut [0.35]

c. Power - Slightly lower [0.35]

d. Pressure - Slightly lower [0.35]

REASON: Above caused by the decrease in pressure and power causing BPVs to shut -- PCU cycling to r.nw equilibrium state

((345-315) x 3.3) [0.35]. (1.75)

REFERENCE QC EHC Pressure Control and Logic, LIC-5650-2, pp. 4-3

3. INSTRUMENTS AND CONTROLS PAGE 31 ANSWERS -- QUAD CITIES 1&2 -86/03/31-MORGAN, T.

ANSWER 3.06 (3.00)

a. 1. Increase [0.5]. Master limiter, low speed limit (0.5]. (1.0)

2. Increase [0.5]. Scoop tube positioning unit or electrical limit switches [0.5]. (1.0)

b. The null voltmeter is used to match the speed from the tachometer with the speed demand from the speed controller [0.5], to prevent a ficw transient daring reset [0.5]. (1.0)

REFERENCE QC Recire Flow Control, LIC-0202-2, pp. 10, 12, 14, 34 ANSWER 3.07 (2.00)

a. 1, 6, 11, and 16 [0~.25 each] (1.0) i b. 6 and 16 [0.25 each] (0.5)

c. Yarway Wide Range r A- r / (0.5)

REFERENCE QC Lesson Plan - Reactor Vessel Instrumentation - LIC-0263, Sec. B.4.e.

ANSWER 3.08 (1.00)

a. 7 (+/- 1 inches)

b. lower

c. dryers

d. narrow range (4 @ 0.25 each)

REFERENCE QC Lesson Plan - Reactar Vessel Inatrumentation - LIC-0263, Sec. E.a

t .

3. INSTRUMENTS AND CONTROLS PAGE 32 ANSWERS -- QUAD CITIES 1&2 -86/03/31-MORGAN, T.

ANSWER 3.03 (2.50)

a. They require no power supply for operation. (1.0)

b. Narrow Range (0.5)

c. -60" [0.25] to +60" [0.25] (0.5) l

-42" [0.25] to +358" t0 251

d. (O.5)

L ,y w.p.c 2 / r t', . e t .. . . - -~ol I.. I'ai m l A REFERENCE QC Lesson Plan LIC-0263, pp. 14, Sec. C.c. and C.d ANSWER 3.10 (1.00)

1. RPV water level -53'.

2. Drywell press > 2 psig.

3. Any LPCI or CS pump discharge pressure > 100 psig

4. Timer reset pushbutton NOT depressed.

5. 400 see timer timed out

/ / s* pg r .. o .

[any FOUR (4) required @ 0.25 each]

ANSWER 3.11 (3.00)

a. Actual vessel level is decreasing. (0.5)

b. Level channel "A" will indicate increasing water level. (0.5)

c. FWLCS will close the FRVs to try to maintain level. (0.5)

d. Reactor will scram @ +8' due to low reactor water level. (0,5)

e. P.: ire ; ump--trip, PCIS Group 1 isc,latien. HFCI 4ad-RG1C initiation eH ? 53". ffr- (O.5)

f. PCIS Group 2 ar.3 3 isolations also 9 +8' . (0.5)

REFERENCE QC Reactor Level ;:. - E rezsure , LIC-07CJ, pp. 12

3. INSTRUMENTS AND CONTROLS PAGE 33 ANSWERS -- QUAD CITIES 1&2 -86/03/31-MORGAN, T.

ANSWER 3.12 (2.50) i It can be moved out one notch before a withdraw error will block further I movement [1.0]. If the rod was inserted, it will move as far as the i operator wants as long as it is not the third insert error [1.0].

If it were the third insert error, it would only go one notch [0.5].

REFERENCE l

Quad City RWM Lesson Plan LIC-0207 pg 22 i

l

.m--,- - - - - -.,-m-- ------,.--m _ _ _ _ _ _ ,

t-

4. PROCEDURES - NORMAL. ABNORMAL. EMERGENCY AND PAGE 34 RADIOLOGICAL CONTROL ANSWERS -- QUAD CITIES 1&2 -86/03/31-MORGAN, T.

ANSWER 4.01 (1.50)

1. g (700)

2. c (300)

3. b (200) h, $ hbo) ",. . . i . . < i. . ' d ' " r " ' sj e h *' ' ' ( '~'"If '"' " ' / " 0"

6. a (100) c- 4 U 2" [0.25 each)

An4 vers +/- 100 psig of designated pressure.

REFERENCE QC, QGF1-1, Normal Unit Startup, pp. G and 10 ANSWER 4.02 (3.50)

a. 3 (0,5)

b. Keep the line cpen for a trace. (0.5)

c. 1. Notify another control room operator or office clerk that a bomb threat call is being received and the phone trunk it is on.

2. Complete the 'Bemb Threat Call Checklist' , with the information acquired frca the caller.

3. Record sa much of the rhone conversation as possible.

4. Ask the call- r for the detonation time and location of

the bomb.

5. Ask the caller for their name.

! 6. Inform the caller that the building is occupied and the explosion may cause death or serious injury to many innocent people.

7. Listen for any background noises which could possibly indicate

! the locati:n of the caller.

l

8. Listen to *he voice.

9. By use of an..her phone, call phone company to determine if a trace u:a .vle.

[any FIVE $ 0.5] (2.5) l i

i REFERENCE I

QC, Receipt of Bomt !!.r:at Procedure QAP-1000-6, pp. 1 l ,

4. PROCEDURES - NORMAL. ABNORMAL. EMERGENCY AND PAGE 35 RADIOLOGICAL CONTROL ANSWERS -- QUAD CITIES 1&2 -86/03/31-MORGAN, T.

ANSWER 4.03 (1.50)

1. Attempt to properly close or seat the valve by opening and reclosing it using the appropriate key-lock switch.

2. If the value does not properly close, Scram the reactor.

3. If an entry condition for a QGA procedure occurs, then enter that procedure.

[3 @ 0.5 each] (1.5)

REFERENCE QC, Failure of a Relief Valve to Close or to Reseat Properly, QOA 201-2, pp. 1 ANSWER 4.04 (1.00)

The trubine will roll much easier [0.5] and very poor shell warming occurs if these valves are open. [0.5)

EEFERENCE Quad City QGP 1-1 Sec f.9 pg S (2.50)

ANSWER 4.05 l

a. 1. Insert statement at point of terminatien as to reason for termination.

l 2. Insert title of subsequent procedurcs at point of terminaticn

3. Insert NA in all remaining blanks

4. Date, time, and sign the last page

5. Retain the terminated procedure in the startup package. (2.0)

[4 @ 0.5 ea]

b. Less than 30 see.:nds. (0.5) l REFERENCE l Quad City QGP 1-1 Cec C.8 pg 3 l

l l

i

4. PROCEDURES - NORMAL. ABNORMAL. EMERGENCY AND PAGE 36 RADIOLOGICAL CONTROL ANSWERS -- QUAD CITIES 1&2 -86/03/31-MORGAN, T.

ANSWER 4.06 (2.00)

o. (QGP 2-3,) Reactor Scram er /M.e d t 9<~/L . Gu3 ./ m 5 /"> '" ' s e ' /

b. Heat Exchangers

c. Average Channels "A" and "B" of the Suppression Pool Temp recorder (1802-8).

d. Required head and Max Suction Flow [4 @ 0.5 ea]

REFERENCE-Quad City QGA Manual Preface Caution Notes pg 1-4 ANSWER 4.07 ( .50)

False REFERENCE Quad City QGA Caution #1 and Statement immediatly after each see of entry conditions pg 1 plus i

ANSWER 4.08 (2.00)

a. RPV water level <+8 inches

b. RPV pressure >1060 psig l

c. Drywell pressure >2.0 psig I

d. Reactor Scram required and power 23% or cannot be determined

[4 @ 0.5 ea]

REFERENCE Quad City QGA 100-1 Rev 1 RPV w/1 control

l

4. PROCEDURM - NORMAL. ABNORMAL. EMERGENCY AND PAGE 37 RADIOLOGICAL CONTROL ANSWERS -- QUAD CITIES 1&2 -86/03/31-MORGAN, T.

ANSWER 4.09 (2.00)

1. Differential pressure not able to be restored and/or maintained below 0 in. of water

2. An area temperature above its maximum normal operating value

3. Reactor building ventilation system exhaust radiation level above (3 mR/hr) setpoint.

4. An area radiation level above its maximum normal operating value

5. Reactor building floor drain sump A and B water level above the high water level alarm setpoint for greater than 15 minutes (4 @ 0.5 ea)

REFERENCE QGA 300-1, Secondary Containment Temperature Control ANSWER 4.10 (1.50)

a. Imposes excessive loads on the turbine last stage buckets

b. When it is necessary to quickly reduce turbine rpm

c. Do not lower condenser vacuum below 25 inches Hg. or no greater than 5 inches Hg. backpressure REFERENCE QGP 2-1 page 7 ANSWER 4.11 (0.00)

a. Verify that all APRM's are indicating between 4 and 12%

b. Verify that all AFRM's DOWNSCALE lights are not illuminated

c. Verify that the ..ain condenser backpressure is less than 9 inches Hg. or greater tha:. 21 inches Hg. vacuum

d. Verify that the CHANNEL A/B LOW VACUUM alarm is cleared

e. Place one IRM/AFEM recorder on each RPS channel to APRM

[4 @ 0.5 each] (2.0)

REFERENCE CGP 1-3 Sect. x. page

4. PROCEDURES - NORMAL. ABNORMAL. EMERGENCY AND PAGE 38 RADIOLOGICAL CONTROL ANSWERS -- QUAD CITIES 1&2 -86/03/31-MORGAN, T.

ANSWER 4.12 (2.00)

n. Alert (0.5)

b. Site emergency (0.5)

c. Unusual event (D.5)

d. General emergency (0.5)

REFERENCE QC Table QCA 5-1 GSEP

, ANSWER 4.13 (2.00) l a. True (0.5) i

b. False (0.5) l c. False (0.5) l d. False (0,5)

ANSWER 4.14 (1.00)

1. b

2. d

3. c

4. a 0.25 ea.

l REFERENCE Quad Cities Tech Specs Table of Cententa 1

,- S '. THEORY OF NUCLEAR POWER PLANT OPERATION. FLUIDS. AND PAGE 16 THERMODYNAMICS

, ANSWERS -- QUAD CITIES 1&2 -86/03/31-HANEK, J.

l N SWER 5.01 (2.50)

1. The elimination of steam voids

2. The moderator temp change from hot to 125 F

3. A reduced Doppler effect

! 4. A decreased control rod worth as the moderator cools and the l

boron being in competition with the control rods t

5. Xenon decay l

6. A shutdown margin of 3% dK (5 0 0.5 ea)

REFERENCE

. Dresden SBLC Lesson Plan pg 10 Quad Cities Lic-1100 pg 11 ANSWER 5.02 (1.50)

Plant efficiency would decrease (.5). All condensate /feedwater heat that is rejected to the cire. water must be added by the reactor (1.0). (1.5)

REFERENCE Quad Cities Heat transfer ch 7 pg 45 ANSWER 5.03 (3.00)

a. The decrease in the burnout term [0.5] with the production of xenon from iodine still at the higher power rate dominates [0.5]

causing the xenon concentration to increase. (1.0)

b. Peripheral rod worth will increase [0.5] because the highest xenon concentration will be in the center of the core where the highest flux existed previously [0.5]. This will suppress the flux in the center of the core and increase the flux in the area j of the peripheral rods, thereby, increasing their worth [0.5] (1.5)

c. More than one half the value at 100%. (0.5)

REFERENCE Quad Cities. Theory Review, pg. 66-70

5. THEORY OF NUCLEAR POWER PLANT OPERATION. FLUIDS. AND PAGE 17 TiiERM0 DYNAMICS ANSWERS -- QUAD CITIES 1&2 -86/03/31-HANEK, J.

ANSWER 5.04 (1.50)

1. They are physically located as far below the normal water line as possible to provide the greatest static head.

2. With feed flow less than 20% they are kept on minimum speed.

3. At high power operation adequate NPSH is obtained from feedwater subcooling.

4. Low reactor Vessel water level trip, cavitation interlock.

5. Suction valve closed trip, cavitation interlock.

(3 0 0.5 ea)

REFERENCE DRESDEN - Recire System Lesson Plan pg 16 & 18 GE Thermodynamics, Heat transfer & Fluid Flow, page 7-93 & 94 Quad Cities LIC 0202-1 pg 19 and 21 ANSWER 5.05 (3.00)

a. LHGR is based on prevention of 1% plastic strain on clad due to pellet swelling.

b. Used to limit clad temperature during a DBA to 2200 degrees F.

c. Will ensrue APLHGR limits are not exceeded. [3 @ 1.0 ca]

REFERENCE

! Quad Cities Heat Transfer and Fluid Flow page 9-15, 9-16, and 9-20 ANSWER 5.06 (2.00)

The notch insert transient took longer to stabilise(.5). On a down power transient, the rate of power decrease is limited to the rate of decay of the longest lived precursor (1.5) (2.0)

REFERENCE GE REACTOR THEORY REVIEW, pg 21 Quad Cities LIC Theory pg 38 1

5. THEORY OF N" CLEAR POWER PLANT OPERATION. FLUIDS. AND PAGE 18 THERMODYNAMICS ANSWERS -- QUAD CITIES 1&2 -86/03/31-HANEK, J.

ANSWER 5.07 (2.00)

o. U-238 absorbs a neutron [.25] and (beta) decays [.25] to Plutonium. (0.5)

b. The response of the reactor will be faster [0.5] due to the fact that Plutonium produces fewer delayed neutrons [1.0] than does Uranium. (1.5)

REFERENCE Dresden Reactor Theory Quad Cities Theory LIC pg 40 and 54 ANSWER 5.08 (2.00)

a. Transition boiling may occur which can result in clad failure. (1.0) ,

b. To make the MCPR limit more conservative to account for the possibility of a sudden flow increase and a corresponding power increase. The MCPR is increased (or core conservative) (1.0)

("Recire. pump runaway" acceptable for " sudden flow increase")

REFEEENCE NMP-1 Operations Technology, Mod.X, pg.X-34, Tech. Specs,pg.70-70a.

DRESDEN - Tech Spec 1.1, pg B 1/2.1-7, & 3.5K, pg B 3/4.5-37 Quad Cities Theory pg 9-25, 9-44 and Tech Spec Bases 1.1/2.1-4 I

ANSWER 5.09 (1.50)

a. The point where further heat addition or removal to a substance will cause it to boil or condense without a change in temperature at a constant pressure. (1.0)

b. Measure of energy content of a substance. (0.5)

REFERENCE Thermodynamics Heat Transfer and Fluid '71ow for RO/SRO License Class page 8.

Quad Cities Theory pg 3-8 and 1-47

5. THEORY OF NUCLEAR POWER PLANT OPERATION. FLUIDS. AND PAGE 19 THERMODYNAMICS ANSWERS -- QUAD CITIES 1&2 -86/03/31-HANEK, J.

ANSWER 5.10 (3.00)

c. 1. Decrease in pressure causes increased voids, void coefficient would add negative reactivity. (1.0)

2. Rod drop inserts positive reactivity causing power to increase, fuel temperature increases, and doppler is first to react by adding negative reactivity. (1.0)

b. Pressure / temperature initially increases then turns due to the ,

negative effects of reactivity coefficients [0.5]. Power also initially l

increases and levels out at a value equal to the ambient losses and power reactivity coefficient losses [0.5). (1.0)

. REFERENCE MTC Book 4, LP 12, pg. 31-32 and pg. 50 Quad Cities LIC Theory pg 48-56 i

ANSWER 5.11 (2.00)

A. Neutron level would start and continue to increase until the As the coolant heats up, point of adding heat is reached.

negative reactivity is added and power turns. Pcwer would l stablize at the point of adding heat. (1.0)

B. Period would take a step jump due to the production of prompt

neutrons. Immediately after this step, the rate of power l change decreases to a rate controlled by delayed neutrons i until the reactivity is no longer being increased. Then a sharp drop would occur as the rate of reactivity addition drops to zero. A stable period would continuc until negative reactivity is inserted. Stabilizes at infinity. (1.0)

REFERENCE Dresden NUS Theory Quad Cities Theory Review pages 44-45 and 78.

ANSWER 5.12 (1.00) a, larger (0.5)

b. longer (0.5) l l REFERENCE I RX PHYSICS REVIEW, pg 17 i

l

6. PLANT SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION PAGE 20 ANSWERS -- QUAD CITIES 1&2 -86/03/31-HANEK, J.

ANSWER 6.01 (3.50)

'" o. Drywall pressure >/= +2 psig. (0.5)

Reactor water level </= -59 inches. (0.5)

//O 496 second timer timed out. (0.5)

Any Low Pressure ECCS pump (core spray or LPCI) running with

>/= 100 ps$g (0.5)

-b. A loss of power (0.5)

Timer reset button being depressed. ## (0.5)

RX water leve] increasing p > 59 inches (0.25) within Pte seconds

[0.25] />J e /1 ge g g p// pf,ggp fpp/ (O. )

REFERENCE QC ADS LIL-0287-1 pg 5 and 6 ANSWER 6.02 (2.50)

--a. 1. Load reject (0.5)

2. TSV fast closure (0.5)

3. FASTC low pressure (TCV fast closure) (0.5)

b. Setpoint fer the auto bypass is within capacity of the bypass valves plus aux steam loads. (1.0)

REFERENCE QC RPS LIC 0500-1 PG 26 OF 27 ANSWER 6.03 (2.50)

Initial Final

c. TCV Position Decrease (0.25] Same [0.25] (0.5)

b. BPV Position Open [0.25] Closed [0.25] (0.5)

c. RX Power Increase [0.25] Same (0.25] (0.5)

d. RX Pressurc Increase [0.25] Increase [0.25] (0.5)

e. RX Water Level Decrease (0.25] Same [0.25] (0.5)

REFERENCE QC LIL-5650-2 pg 4

. 6. PLAN" 'vSTEMS DESIGN. CONTROL. AND INSTRUMENTATIQE PAGE 21 ANSWERS -- QUAD CITIES 1&2 -86/03/31-HANEK, J.

ANSWER 6.04 (1.50)

c. Unit 2 Bus 23 (0.5)

b. Unit 1 Bus 13 (0.5)

c. None (0.5)

REFERENCE QC Diesels LIC 6600 pg 16 and 18

-- ANSWER 6.05 (1.50) i

e. RPV water level high (0.5)

b. Mechanical overspeed . (0.5)

c. Remote manual trip gr /c / p/.ei. < . I T// (0.5)

REFERENCE QC Lesson Plan - RCIC-LIC-1300, pp. 13 ANSWER 6.06 (4.00)

a. PUMP POWER SUPPLY 1A 13.1 1B 14.1 2A 23.1 2B 24.1 [0.25 each) (1.0)

b. High drywell pressure (0.25), low-low RPV water level, -50"

[0.25] and low RPV pressure, 325 psig [0.25), hPV water level at -59" for 8.5 min. [0.25] (3 ')

-- c. FOUR (4) 180 sparger rings (0.5], supported by brackets on the core shroud [0.5), each of the TWO (2) levels is supplied by one core spray system [1.0]. (2.0)

REFERENCE

a. QC Lesson Plan LIC-1400, pp. 6 of 35, Sec. 4.C.

b. QC Lesson Plan LIC-1400, pp. 6 of 35, Sec. 4.e.

c. QC Lesson Plan LIC-1400, pp. 12 of 35, Sec. 11.0

6. PLANT SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION PAGE 22 ANSWERS -- QUAD CITIES 1&2 -86/03/31-HANEK, J.

ANSWER 6.07 (2.00)

c. Drywell press >/= 2 psig [0.5] and RPV water level </= -59"

[0.5] (1.0)

b. Injection loop is selected by the comparison of recirc system riser DP's [0.5]. If loop A > B, A is selected and if loop B is >/= loop A, loop B is selected [0.5]. (1.0)

REFERENCE QC Lesson Plan - RER LIC-1000-1, pp. 44 of 67, Sec. 4 ANSWER 6.08 (2.50)

o. Chimney isolation valve closes

b. Air ejector suction valve closes

c. Mechanical vacuum pump trips

d. The off-gas line drain valve closes

e. The off-gas sample vacuum pump suction valve closes

f. Group I primary containment isolatioi.

g. Direct reactor scram REFERENCE QC Lesson Plan OFF-GAS LIC-5450, pp. 22, Sec. IV.A.2 ANSWER 6.09 (3.00)

a. Actual vessel level is decreasing. (0.5)

b. Level channel "A" will indicate increasing water level. (0.5)

c. FWLCS will close the FEVs to try to mair.tain level. (0.5)

d. Reactor will scram G +6" due to low rcactor water level. (0.1)

- e. E::ir: ru- ; t. ip , PCIS Group 1 isolation,iHPCI and-Rete initiation all 6 -59". (0.5)

PCIS Group 2 and 3 isolations also @ +8*. (0,5) f.

REFERENCE QC Reactor Level and Pressure, LIC-0263, pp. 12

, . 6. PLA11T SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION PAGE 2'i 1

ANSWERS -- QUAD CITIES 1&2 -86/03/31-HANEK, J.

ANSWER 6.10 (2.50)

It can be moved out one notch before a withdraw error will block further covement [1.0). If the rod was inserted, it will move as far as the cperator wants as long as it is not the third insert error [1.03 If it were the third insert error, it would only go one notch [0.5].

REFERENCE Quad City RWM Lesson Plan LIC-0207 pg 22 i

i l

l

7. PROCEDURES - NORMAL. ABNORMAL. EMERGENCY AND PAGE 24 RADIOLOGICAL CONTROL ANSWERS -- QUAD CITIES 1&2 -86/03/31-HANEK, J.

ANSWER 7.01 (3.00)

- c. -59 inches water level ammmenW55558e or 1250 psig reactor pressttre. (1.0)

b. Trip reactor recire pumps. (0.5)

c. Will render them inoperative as they are energized to open. (0.5)

d. It will open the valves and cause a scram. (It will not trip the recire pumps.) (1.0)

REFERENCE QC CRD LIC-0300-2 pg 46 ANSWER 7.02 (2.00)

e. Alert (0.5)

b. Site emergency (0.5)

c. Unusual event (0.5)

d. General emergency (0.5)

REFERENCE QO Table QCA 5-1 GSEF pg QCA 5-2 ANSWER 7.03 ( .50)

False REFERENCE QO Tech. Spec. 3.3.B.3.6 ANSWER 7.04 (1.00)

The Shift Engineer shall immediately issue the shear valve key to the I operator (0.53 The problem should be investigated and repairs initiated

[0.5] (1.0) l l

, 7. PROCEDURES - NORMAL. ABNORMAL. EMERGENCY AND PAGE 25 RADIOLOGICAL CONTROL ANSWERS -- QUAD CITIES 1&2 -86/03/31-HANEK, J.

REFERENCE QC QOP 700-6 TIP System pg 1 ANSWER 7.05 (3.25)

c. 1. Reactor metal temperature (.25)

2. Vessel level (.25)

3. Water temperature (.25)

b. 1. Increase shutdown cooling flow

2. Raise vessel water level

3. Use head spray

4. Startup the RWCU system

5. Startup both CRD pumps

6. Bleed through cleanup system and feed through feedwater system.

7. Flood the main steam lines, and drain through the main steam line drains if the cleanup sytem is not available.

[5 required @ 0.5 each] (2.5)

REFERENCE QC QOP 1000-5 pg 2 ANSWER 7.06 ' (2.50)

O. 1. 95 F allows sufficient margin for complete condensation i

of the steam following a blowdown from 1000 psi. (0.75) ,

l 2. 160 F assures a not positive suction head for the core spray and RHR pumps. (0.75)

b. 110 F (0.5)

c. RX is scramed (0.5)

REFERENCE QC Tech. Specs. 3.7.A and QOP 1000-9 ANSWER 7.07 (1.00) c

7. FROCEDURES - NOEUAL. AENORMAL. EMER3ENCY AN!' F/.GL D:

, B&DIOLOGICAL CONTROL ANSWERS -- QUAD CITIES 1&2 -86/03/31-HANEK, J.

REFERENCE QC Tech. Specs. 3.6.C ANSWER 7.08 (2.00)

c. True

b. False

c. False

d. False [4 0 0.5 ea)

REFERENCE Quad Cities Rad Protection LIL H-3 i ""' ANSWER 7.09 (2.00)

, c. Fuel Element Failure (0.5)

b. KR 88 leaves the reactor as a gas, via steam leaks enters the turbine building and decays to a particulate. (0.5)

c. 1. Reactor Coolant Iodine.

2. Main Steam Line Rad

3. Off Gas Activity (2 required @ 0.5 each] (1.0)

REFERENCE Quad Cities GE Chart of the Nuclidec, Rad Protection LIC G-6 ANSWER 7.10 (2.00)

a. RPV water level level below +8 in. (.0)

b. RTV prc: cure above 1060 pcis. (.5)

c. Drywell pressure above 2.0 psig. (.5)

d. Conditions which require a reactor scram and following the (.5) automatic scram condition or manual scram reactor power is above 3% or cannot be determined.

REFERENCE Quad cities QGA 100-1 Page 1

7. FROCENhIC- NORNkL. AENORM/[. EMERGESCY AQ IAGE ;T RADIOLOGICAL CONTROL

\

ANSWERS -- QUAD CITIES 1&2 -86/03/31-HANEK, J.

ANSWER 7.11 (3.50)

c. 1. Cause: Poor mixing of the boror and coolant. (.5)

2. Effect: Reactivity or power chtgging (.5)

3. Result: Possible fuel damage (.5)

b. 1. Amber light of squib continuity not lit. (.5

2. Flow indicating pilot lit. (.5)

3. RWCU isolated. (.5)

4. Decreasing level in SBLC storage. tank. (.5)

I 5. SBLC squib valve circuit f ailure. annunciator not lit. (.5)

REFERENCE

. Quad Cities Standby Liquid Control LIC 1100 Page 11 and12.

ANSWER 7.12 (2.00)

1. Insert statement at point of termin:. tion as to reason for termination.

2. Insert title of subsequent procedures at point of termination

3. Insert NA in all remaining blanks

4. Date, time, and sign the last page

5. Retain the terminated procedure in he startup package.

[4 @ 0.5 es]

REFERENCE Quad City QGP 1-1 Soc C.8 pg 3 i

l w--_-_--_-_--_____. __ ___ -_ _ _ _ _ _ _ _ _ _ _ _ _

6. APMINICTRATIVE FROCEDUFIE. COUDITIONS. AND LIMITATIOEE FACE S ANSWERS -- QUAD CITIES 1&2 -86/03/31-HANEK, J.

ANSWER 8.01 (l.50)

c. Two (0.5)

b. 3 counts per second (0.5)

c. Fully Inserted (0.5)

REFERENCE QC Tech Spec's 3.3.B4 9- ANSWER 8.02 (3.25)

o. 1.2T The intent of the original procedure is not altered. (0.75)

2. The change is approved by two members of the plant management staff at least one of whom holds an SRO License on the unit affected. (0.75) g 3. The change is documented, reviewed by the onsite review Q and investigative function and approved by the station superintendent within 14 days of implementation. (0.75) i > b. 30 days (0.5)

c. FALSE (0.5) l REFERENCE

\ QC Tech Specs. 6.2b and QAP 1100-5 PG 2

.s e ANSWF.E 8.03 (1.50)

. Be within 10 minutes of the control room. (0.75)

Be able to be reached immediately. (0.75)

D

\' REFERENCE QAP 300-1 PG 2 m s, mi,a ,.a... s a.a 7

... ,( :

m ,.y.n i.;. -

c.. , e.,,. (e,7

w. . . .tr e.,u a //.+ r n L . -. i s / 4 s . ,,ea. : w

.c fl' i sea .u,J . u'. ~ ,1 ,( n is:. -;,

imiUid.i.I s <. / < . . ] , ;, o ( , .

s

, . g p,,

*,

• l (~;s t. i j, , , f .. ,J ,17. , /,

L b i 'Y '

i, /* /~ s .< y. /c .. . . , f . l* -

' - . .:4 le c. n' i, .

,- /' ,

, , /j ,, . ,-(

.- / . ,pe, n n' , t ,., f

E. ADMINISTRATIVE FROCEDUhES. CONDITICNG. ASD LIMITATIONS IAGE C?

ANSWERS -- QUAD CITIES 1&2 -86/03/31-HANEK, J.

ANSWER 8.04 (4.00)

o. 1. R keys -(0.5)

2. Electromatic Relief Valves (0,5)

3. Local valve control station (0.5)

4. 1/2 diesel generator room vent fan bypass isolation switch (0.5)

b. Instrument racks 2201-Q 2201-6 d 2202-5 and 2202-6 ,

(1.0) tJhe$ Grl. flr;.:. foi /3' & /7[0 35queach]E

a. -/T

• II A'* /3 /^

W fc.OfWUH O.. L_: 15 -ad 1 '?

• 001 x2 902 ,.(uol, M r #/J eJ/r.'la/,e A/) (0.5) i OR RPS HG sets at MCC's 18 and 28-2 and 19-29-2 (0.5)

REFERENCE QOA 010-5 pg 1 and 2 ANSWER 8.05 ( .50)

False REFERENCE QOA 700-3 pg 1 and 2 ANSWER 8.06 (4.25)

n. 1. At least one door in each access opening in closed. (0.75)

2. Standby gas treatment cystem is operable. (0.75)

3. All reactor building automatic ventilation system isolation valves are operable or are secured in the isolation position. (0.75)

b. 1. Reactors are suberitical and sufficient chutdown margin (0,5) exists.

2. Reactor water temperature is below 212 F and the reactor coolant system is vented. (0,5)

3. No activity is being performed which can reduce the shutdown margin below that specified in T.S. (value not required). (0.b)

4. The fuel cack or irradiated fuel is not being moved in the reactor building. (0.5)

0. AP.I N1 CIhh11EL F h ?CNUhEL . CUN1?]Th %:. AN,_L1011611 M f /.GL e.

. ANSWERS -- QUAD CITIES 1&2 -86/03/31-HANEK, J.

REFERENCE QC Tech Spec 1.0 X Definitions QC Tech Specs 3.7C ANSWER 8.07 (2.00)

' O. M M fA N (0.5)

b. FALSE (0.5)

c. FALSE (0.5)

d. TRUE (0,5)

REFERENCE QC Tech. Specs. Section 3.3.A ANSWER 8.08 (3.50)

c. Any individual who exceeds his approved exposure level is required to promptly report his exposure to radiation protection and to his own supervisor. (1.5)

b. 1. 3 rem /qtr not to exceed 5 (N-18) (0.5)

2. 7 1/2 rem /qtr (0.5)

3. 18 3/4 rem /qtr (0.5)

c. False (0.5)

REFERENCE LIL: RAD PRO Lesson Plan Quad Cities QAP 1120-2 pg 54 l ANSWER 8.09 (2.50)

I

c. 1. To protect personnel doing an operating evolution. (0,5) l 2. To protect equipment during an operating evolution. (0.5) l 3. If equipment maintenance is required and maintenance l

supervisor is not on site and will not be coming out. (0,5) l l b. Work group supervisor's immediate supervisor or somebody of higher authority with respect to the work involved. (1.0)

~

---

u- - u. .. - . .. _ m. u L k - " ' > Whu bh* "IESLUkliL Ih2  :

, ANSWERS -- QUAD CITIES 1&2 -86/03/31-HANEK, J.

REFERENCE QAP 300-14 pg 2 ANSWER 8.10 (2.00)

o. Operating Engineer (1.0)

= b. 1. Daily

2. Shift Engineer (0.5) cc /lg /efj}g4# OF /51 A1 y f (0.5)

REFERENCE Quad Cities QAP 300-12 pg 1 i

=

l l

---

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

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

1 I

U. S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION FACILITY: QUAD CITIES 1&2 REACTOR TYPE: BWR-GE3 DATE ADMINISTERED: 86/03/31 EXAMINER: RANEK. J.

APPLICANT:

INSTRUCTIONS TO APPLICANT:

Uce 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 1 cast 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 24.94 5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND THERMODYNAMICS 25.50 25.44 6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION 24.75 24.62 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL 25.00 24.94 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS Li(L.L 120.OQ TOTALS FINAL GRADE  %

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

~

APPLICANT'S SIGNA 7URE

5.* THEORY OF NUCLEAR FOWER PLANT OPERATION. FLUIDS. AFD PAGE  : '

THERMODYNAMICS QUESTION 5.01 (2.50)

The Standby Liquid Control System is designed to overcome SIX positive reactivity effects. WHAT are FIVE of these effects? (5 9 0.5 ea)

QUESTION 5.02 (1.50)

Most condensers are designed with excess condensing capability so that the condensed liquid leaves the condenser hotwell several degrees below the naturation temperature. WHAT EFFECT would there be on plant cfficiency if the temperature of the condensate were lowered to 30 F below the saturation temperature and WHY7 QUESTION 5.03 (3.00)

Regarding the xenon transient following a significant DECREASE in reactor power from high power operation:

a. Briefly, EXPLAIN WHY the xenon concentration will peak folloving the manuever. (1.0)

b. HOW will peripheral control rod worth be affected (INCREACE, l DECREASE, REMAIN T."E SAME) during the xenon peak? BRIEFLY l

EXPLAIN your answer. (1.5)

c. If the decrease in reactor power was from 100% to 50%, would the new '50% power) equilibrium xenon reactivity be MORE THAN, LFOS THAM OR EQUAL TO one half the 100% equilibrium value. (0,5)

QUESTION 5.04 (1.50)

What are THREE of the decign or operational f actors that insure adequate Net Positive Suction Head (NPSH) for the recirculation pumps? (3 @ 0.5 ea)

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

1 _ _ _ .____. .- _-- -. . _ ,

5.* THEORY OF NUCLEAR POWER PLANT OPERATION. FLUIDS. AND PAGE 3 THERMODYNAMICS QUESTION 5.05 (3.00)

WHAT is the purpose or basis for the following limits?

o. LHGR

b. APLHGR

c. MAPRAT (3 3 1.0 ea.)

QUESTION 5.06 (2.00)

A reactor is operating at a steady state power level. A control rod is withdrawn one notch and power increases, then stabilices.

Now the operator inserts the same control rod one notch and power decreases, then stabill:es. WHICH transient event took LONGER to stabilise; the withdrawal notch or the insert notch, and WHY?

QUESTION 5.07 (2.00)

c. How is Plutonium-239 produced in the reactor? (Be specific) (0.5)

b. Discuss the difference in neutron yield from the thermal ficsion of U-235 and Pu-239. How doec this difference affect the recpente of the reactor to a reactivity change? (1.5)

QUESTION 5.08 (2.00)

Regarding M;FE (Minimum Critical Power Ratio):

l a. What PHENOMENON could exist in a fuel fundle if it were

! operated at a MCPR LESS THAN ONE (< 1.0) and WHAT would very likely be the CONSEQUENCE of the phenomenon? (1.0)

b. WHY must the Technical Specification MCPR limit be modfied when core flow is LESS THAN RATED 7 (Include in your answer

whether MCPR is increased or decreased.) (1.0) l l

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

5.* THEORY OF NUCLEAR POWER PLANT OPERATION. FLUIDS. AED PAGE 4 THERMODYNAMICJ e

QUESTION 5.09 (1.50)

Define the following terms,

c. Latent Heat of Vaporization (1.0)

b. Enthalpy (0.5)

QUESTION 5.10 (3.00)

c. For each of the' events listed below indicate which reactivity coefficient will respond first, why it responds first, and whether it adds positive or negative reactivity.

1. SRV opening at 100% power. (1.0)

2. Rod drop from 100% power. (1.0)

b. Following initial criticality a constant positive 11.0) period is established. Explain what happens over the next several hours to pressure, temperature and power if no rod movement occurs. (1.0)

QUESTION 5.11 (2.00)

The reactor is exactly critical LOW in the intermediate range.

A centrol rod is withdrawn one nctch.

, A. Describe what happens to indicated neutron level AND why?

l (Continue yottr discussion until a steady state condition is reachrJ. Assume no futher operator action other than ranging the IRM metcrs. (No other parameters are changed.) (1.0; l

E. Describe how reactor period would respond AND why? (1.0) l (***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)

l l

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

3.* THEJRY OF NUCLEAR POWER PLANT OPERATION. FLUIDC. AND PAGE 5 THERMODYNAMIQS QUESTION 5.12 (1.00)

The following statements are concerned with suberitical multiplication.

CHOOSE the CAPATALIZED word that will make the sentence correct.

c. As Keff approaches unity, a LARGER / SMALLER change in neutron level occurs for a given change in Keff. (0.5)

b. As Keff approaches unity, a SHORTER / LONGER period of time is required to reach the equilibrium neutron level for a given change in Keff. (0.5)

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

- E,* PLANT SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION FAGE E QUESTION 6.01 (3.50)

c. List FOUR (4) plant conditions with setpoints that will allow ADS to auto initiate. (2.0)

b. List THREE (3) conditions which will reset the ADS timer. (1.5)

(.b4STION 6.02 (2.50)

c. List THREE (3) permissives and/or control signals provided by the main turbine first stage pressure switches. (1.5)

b. What is the basis for the setpoint selected for the auto bypass on these permissives? (1.0)

QUESTION 6.03 (2.50)

With the plant operating at 100% power and the recire system in master canual, the controlling EHC regulator output (A) fails to 0 output.

Assume max combined flow set at 105, and limit set at 100. What will be the initial transient response (increase, decreace or remain the sar.e) cnd final status of the following parameters to this acticn? Values are not required. Refer to the attached EHC block diagran..

Initial Final

c. TCV Position (0.!)

b. BPV Position (0.E) l c. RX I.wer (0.5) l d. RX Pressure (0.!)

e. RX water levc1 (0.E; i

(***** CATEGORY 06 CONTINUED ON NEXT PAGE *****)

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

. 6.- PLANT SYSTEMC DESIGN. CONTROL. AND INSTRUMENTATION FAGE 7 3

QUESTION 6.04 (1.50)

I In reference to the Diesel Generator 1/2 output breaker control, state which Bus will receive the diesel for the following conditions. Assume both keylock switches are in the normal plant position when operating. '

O. Unit 2 Bus 23 is deenergized followed by Unit 1 Bus 13 deenergizing 5 minutes later. (0.5)

]

b. DG 1/2 is feeding Bus 23 and Unit i receives a LOCA and loss of Bus 13 power simultaneously. (0.5)

c. DG 1/2 is feeding Bus 23 and Unit i receives a LOCA signal. (0.5)

QUESTION 6.05 (1.50) i What 'a: FEE RCIC turbine trips em.aot be reset by the RCIC Turbine Overspeed Reset Pushbutton on the 90X-4 panel? (3C 0.5 ea)

I.

QUESTION 6.06 (4.00)

An:wcr the fc11owing quentienc for the Core Spray Syctem:

e. List the power supply, bus no., for each of the FOUR

core spray pumps. (1.0) l l b. WHAT THREE signale will automatically start the core spray pumps? (1.0) l (Include applicable setpoints.)

i

c. Describe the core spray spargers. Include the number of I

sparger rings, HOW they are supported and HOW the flow is divided between the spargers. (L.0)

QUESTION 6.07 (2.00)

c. What TWO (2) parameters will initiate the loop select logic for the LPCI mode of RHR7 Include setpoints. (1.0)

b. Explain how a recire loop is chosen for the injection flowpath by the LPCI select logic, if loop delta press is < 2 psid at the time t'io initiation signal is received. (1.0)

(***** CATEGORY 06 CONTINUED ON NEXT PAGE *****)

6.' PLANT SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION PAGE 8 1

QUESTION 6.08 (2.50)

WHAT are FIVE automatic actions initiated by a 7X normal signal from the main steam line radiation detectors. (5 9 0.5 ea.)

QUESTION 6.09 (3.00)

The reactor is operating at 40% power with the Feedwater Control System in cingle element control, and level channel "A" selected for input. The reference leg isolation valve to the channel "A" NR GEMAC develops a cignificant packing leak and the associated reference leg starts to gradually decrease, i

Describe the effects on AND of the following, assuming no operator action.

Include applicable setpoints.

o. Actual RPV water level

b. Indicated RPV water level on channel "A"

c. FWLC

d. RPS

o. ECCS

f. PCIS (6 @ 0.5 ea.)

QUESTION 6.10 (2.50)

With a select Error on the RWM the rod can still be moved. Arzume the RWM is not bypassed and no rod block existed prior to rod sele: icn.

Explain the rod movement restrictions, for both and incert and withdrawal, imposed by the RWM.

(***** END OF CATEGORY Oc *****)

7.' PROCEDURES - NORMAL. ABNORMAL. EMERGENCY AND PAGE C RADIOLOGICAL CONTROL QUESTION 7.01 (3.00)

Concerning the ATWS valves in the scram air header.

c. What are the setpoints for auto initiation? (1.0)

b. In addition to a reactor scram, what other automatic action will occur if actuated? (0.5)

c. What affect will a loss of the 125 volt DC supply to the valves have? (0.5)

d. What affect (s) will depressing the ARI (ATWS) pushbuttons have? (1.0)

QUESTION 7.02 (2.00)

State which emergency classification is appropriate for the following definitions.

a. Events in progress or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant. (0.5)

b. Events in progress or have occurred which involve actual or likely major failures of plant functions needed for the protection of the public. (0.5)

c. Events in progress or have occurred which indicate a pctential degradation of the level of safety of the plant. (0.5)

d. Events in progress or have occurred which involve actual or iminent substantial core degradation or melting with potential for Loss of Containment integrity. (0.5) ,

CUESTION 7.03 ( .50)

TRUE or FALSE A Reactor Startup may be commenced with the RWM bypassed by substituting a second qualified operator for the inoperable RWM.

(***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)

. 7.- FROCEDURES - NORMAL. ABNORMAL. EMERGENCY AND FAGE IC RADIOLOGICAL CONTROL QUESTION 7.04 (1.00)

At the completion of a TIP scan in the auto mode, what action is required if the TIP Ball Valve fails to close?

QUESTION 7.05 (3.25)

If operating in shutdown cooling and both recire pumps are lost, QOP 1000-5(SHUTDOWN COOLING START-UP AND OPERATION) states to monitor for temperature stratification. ,

Stratification is indicated by increasing (A.1.) without a corresponding (A.2.) or (A.3) change.

c. List parameters A.1., A.2., and A.3. (.75)

b. List five (5) of the suggested actions to minimize stratification if both recire pumps are off. (2.5)

QUESTION 7.06 (2.50)

During normal plant operation, the temperature of the suppression pool ir maintained less than 95 F and during accident conditions should be maintained less than 160 F.

a. What is the basis for these temperature limits? (1.5)

b. What is the maximum suppression pool temperature allowed during operation? (0.5)

c. What action is taken if this maximum temperature is reached? (0.5)

(***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)

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

. 7. PROCEDURES - NORMAL. ABNORMAL, EMERGENCY AND PAGE 11 RADIOLOGICAL CONTROL QUESTION 7.07 (1.00)

Which of the following statements is correct with regards to reactor coolant chemistry, Tech. Spec. limits.

c. For steaming rates >/= to 100,000 lb/hr conductivity < 1.0 unho/cm chloride ion < 1.0 ppm

b. For steaming rates </= 100.000 lb/ar conductivity < 2 umho/cm chloride ion < 1.0 ppm

c. The steady state radioiodine concentration in the reactor coolant shall not exceed 5 uci of I 131 dose equivalent per gram of water.

d. For reactor startups, the maximum value for conductivity shall not exceed 10 umho/cm and the maximum value for chloride ion concentration shall not exceed 1.0 ppm for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after placing the reactor in the power operating condition.

QUESTION 7.08 (2.00)

Concerning the use of radiation dose meters, answer the following TRUE or FALSE.

a. Before entering a suspected radiation area, the meter selector switch should be turned to the highest range. (0.5)

b. Earphones are only required in areas of low light ecnditiens. (0.5)

c. A GM detector is preferred for setting dose rates. (0.5) 60 137

d. Check sources of eclbat (CO ) or cesium (CS ) one micro Currie each will indicate the same reading using a CF(Cutie Pie). (0.5) l l

l

(***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)

7.' PROCEDURES - NORMAL. ABNORMAL. EMERGENCY AND PAGE 12 RADIOLOGICAL CONTROL QUESTION 7.09 (2.00)

While operating at 100% power HP reports an increase in the Airborne Radiation level in the turbine building. Half life and energy level indicate Rubidium (Rb 88) as the primary isotope.

c. What is source of this activity 7 (0.5)

b. What is the mechanism of it's transport into the turbine building 7 (0.5)

c. List TWO (2) other checks you would make to confirm the source. (1.0)

QUESTION 7.10 (2.00)

OGA 100-1 Reactor Pressure Vessel Water Level Control lists FOUR entry conditions. List these conditions, include any applicable setpoints.

(4 @ 0.5 ea.)

QUESTION 7.11 (3.50)

Concerning the standby liquid control system (SBLC).

l I a. Why is this systyem designed to require at least ninety (90) minutes to pump the SBLC storage ecntents into the Reactor?

Include in your answer cause, effect, and result. (1.5)

b. List FOUR indications / parameters, other than reactor power level, that l would provide a means to monitor that SELC injection HAD STARTED after system I had been initiated. (2.0) l QUESTION 7.12 (2.00)

According to QGP 1-1, Normal Unit Startup, if a procedure is terminated at any time during its execution several things must be done to the procedure. List four of these things that must be done. (4 @ 0.5ea.)

l

(***** END OF CATEGORY 07 *****)

. B.* ADMINISTEATIVE FROCEDURES. CONDITIONS. AND LIMITATIONS PAGE 13 QUESTION 8.01 (1.50)

Complete the following statement. Tech Spec's provide the following limits with respect to SRM's for a Reactor Startup:

Control rods shall not be withdrawn for startup unless at least (a) source range channels have an observed countrate of (b) and these SRM's are (c). (3 0 0.5 ea.)

QUESTION 8.02 (3.25)

c. List THREE requirements to make a temporary change to an operating procedure. (2.25)

b. What is the effective time a temporary change can be used without renewal? (0.5)

c. TRUE or FALSE A temporary change is required to change a valve lineup check list. (0.5)

QUESTION 8.03 (1.50) l In accordance with QAP 300-1 (CONDUCT OF OPERATIONS) the shift engineer is l

required to be in the control room or the shift enginecrs office with two exceptions. What are those exceptions? (2 @ .75 ea.)

QUESTION 8.04 (4.00) ,

a. If an evacuation of the control room is required, what FOUR keys must the shift engineer take with him' (2.C)

b. What locatir,ns are the SEO Licensed personnel directed to proceed to per QOA 010-5, (PLANT OPERATION WITH THE CONTROL ROOM INACCESSABLE)? (1.0)

I c. What are the power supply panels /MCC's used to scram the reactor from outside the control room. (1.0) l

(***** CATEGORY 08 CONTINUED ON NEXT PAGE *****)

l

8.* ADMINISTRATIVE PROCE3URES. CONDITIONS. AND LIMITATIONC PAGE ,14 QUESTION 8.05 ( .50)

TRUE or FALSE During refuel, an SRM channel is considered inoperable when indicating

<3 CPS if TWO fuel assemblies are loaded into that quadrant adjacent to the SRM.

(

QUESTION 8.06 (4.25)

Tech Spec's de, fine secondary containment integrity to mean that the reactor building is intact and THREE conditions are met.

c. List these THREE conditions. (2.25)

b. List FOUR plant conditions that allow secondar# containment requirements to be relaxed. (2.0)

QUESTION 8.07 (2.00)

TRUE or FALSE.

Answer the following concerning inoperable control rods.

a. Control rods which are inserted and electrically disarmed are considered inoperable. (0.5)

b. A control rod whose position window when fully withdrawn indicates blank, must be fully inserted, scrammed, and declared inoperable. (0.E)

c. During power operation, the number of inoperable control rods may exceed 8 total rods. (0.5)

d. All control rods that havc been fully inserted and scrammed must bc given an insert signal once per shift. (0.C)

(***** CATEGORY 08 CONTINUED ON NEXT PAGE *****)

8.* ADMINISTRATIVE PROCEDURES. CONDITIONS. AND LIMITATIONS PAGE 1E l

QUESTION 8.08 (3.50)

n. What action is required by any individual who exceeds his approved expiTure limit at Quad Cities Station? (1.5)

b. What kre the 10 CFR limits?

1. for whole body exposure (assume NRC-4 completed). (0.5)

2. skin of whole body. (0.5)

3. . hands and feet. (0.5)

c. TRUE or FALSE Pocket type direct reading dosimeters are used to furnish the exposure data for the 10 CFR limits. (0.5)

QUESTION 8.09 (2.50)

n. List THREE conditions when equipment is taken out-of-service for the Shift Engineer. (1.5)

b. If the supervisor in charge of the work is not available, who may request the Shift Engineer to remove his out-of-service cards? (1.0)

QUESTION 8.10 (2.00)

a. What level of authority is required to authorize installation and removal of electrical jumpers? (1.0)

b. The location of all electrical jumpers and relay blocks is audited (b1) by the (b2). (2 C 0.5 ea.)

l

(***** END OF CATEGORY 08 *****)

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

i

8:l>1 s 8

lglj:>1 lll s .a

>

5

" Eli" "

i _t l

i lll -

"T g

la it i I

cdell

l g ,t?Il M."!.

,, =

= y = = = = == = = l ll, -

i ;

e= ,

g . a

("A ~[= g a i nI I

8-

_ g l> --(~y!i .I i

.= == .

i gM u a i

I ~! > l1b $

u l ll 1,

., 6s=

" > ail i g

h [E j ll 1 !h I+ t s_A tsli!.g - } .

_3,

_ 33

, < =', (s' s*l{ '

s

! 4tki!-d"2f  ! 1 ..

!  ! o eij!

11 11 1 R *E ll 1 @ai g e

EQUATION SHEET f a ma v = 1/t Cycle efficiency = (. 4et work out)/(Energy in) 2

, = 33 s = V,t + 1/2 at s

E = m- . '

KE = 1/2 av 2

, , gyf ,y g)jg 3 ,13 g ,g o,-at PE = agn vf= V, + at . = e/t 1 = an2/tifg = 0.693/t1/2 y=,g -

,g 2 1/2*ff " C(tus)(t )3 A= , [(g ),( 33 aE = 931 an -gx a = V,,Ao ,

Q = mCoat 4

• UA&T I=Ie* g Pwr = Wyah I = I,10**N TV1. = 1.3/u P = P 10 sur(t) HVI. = -0.593/u P = P e*/I l SUR = 25.06/T SG = 5/(1 - Kdf I G, = 5/(1 - Kgf,)

SUR = 26s/a* + (a - o)T G j(1 - K g,5) = CR2 II * "aff2)

T = ( t=/s ) + [(s - o '/ Io ] M = 1/(I - Kg,) = CRj /G 3 7 = V(a - s) M = (1 - K e foI /II ~ #ef'll

(a - o)/(To) SOM=(}-Kgf)/Kef a - (Kgf-1)/Kg f

• g e/K ff 5"

• 10 5'c*"C5 A = 0.1 seconds )

s = [(t=/(7 K df)] + [Tg,/(1 + It)]

l d Ij j = I d2 =2 2 P = (:aV)/(3 x 1010) idjj I#

22 ,

I = 2N R/hr = (0.5 OI)/c'-(meters)

R/hr = 6 CE/d2 (f,,g) ,

j Watae Pergneters Miscellaneous Ocnve.sions

' 1 gal. = 8.345 10m. 1 curie = 3.7 x 1010 ag, 1 4g = 2.21 13m 1gaj.=3.7811 tars

= 7.44 gal. I np = 2.54 x 103 Stu/nr 1 f.

Density = 62.4 lbg/ft3 1 m = 3.41 x 10' 5tu/hr Gensity = 1 gs/c9 Ifn = 2.54 cm Heat of vacarization = 970 Stu/lem 'F = 9/5'C - 32 Heat of fusion = 144 Stu/lem 'C = f/9 (**-32)

, 1 Atm = 14.7 ssi = 29.9 in. He. ~

1 BTU = 778 ft-ibf j 1 ft. H 2O = 0.4335 Inf/in.

i i

s

, - . , , _ , . .