ML20203N667

Exam Rept 50-261/OL-86-01 During Wk of 860127.Exam Results: Eight of Nine Candidates Passed Oral Exam & All Candidates Passed Written Exam

ML20203N667
Person / Time
Site:	Robinson
Issue date:	04/14/1986
From:	Casto C, Munro J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20203N666	List: ML20203N667 ML20203N678
References
50-261-OL-86-01, 50-261-OL-86-1, NUDOCS 8605060002
Download: ML20203N667 (118)

Text

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ENCLOSURE 1 EXAMINATION REPORT 261/0L-86-01 Facility Licensee: H. B. Robinson Steam Electric Plant P. O. Box 790 Hartsville, SC 29550 Facility Name: H. B. Robinson Steam Electric Plant Facility Docket No. 50-261 Written and oral examinations were administered at H. B. Robinson near Hartsville, South Carolina.

Chief Examiner: (

C

.1M<#

is Casto Y [G

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Date Signed Approved by: h um1 [6*O. k J6hn F. Munro, Acting Section Chief V-/4/ - M, Date Signed Summary:

Examinations week of January 27, 1986.

Oral examinations were administered to 9 candidates; 8 of whom passed. Written examinations were administered to 9 candidates; all of whom passed.

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! 8605060002 860418 PDR ADOCK 05000261 y PM i

. Y REPORT DETAILS

1. Facility Employees Contacted: .

C. A. Bethea, Training Director ,

• B. Blasdell, Senior Instructor '

• S. Allen, Senior Instructor

• D. Neal, Senior Instructor

• B. Hansley, Senior Instructor

• Attended Exit Meeting

2. Examiners:

• C. A. Casto, RII P. Isaksen, EG&G F. Jaggar, EG&G B. Hemming, EG&G

• Chief Examiner

3. Examination Review Meeting At the conclusion of the written examinations, the examiners provided S. Allen, Senior Instructor, with a copy of the written examination and answer key for review. The following comments were made by the facility reviewers:

a. R0 Exam (1) Question 1.02(b)

NRC Resolution: Facility recommendation is considered an .

acceptable amplification of the answer key. No change in key required.

(2) Question 1.03(c)

NRC Resolution: Concur. Answer key revised.

(3) Question 1.08(a) and (b)

NRC Resolution: Concur. Answer key revised.

Enclosure 1 2 April 18, 1986 (4) Question 1.11(c)

NRC Resolution: Approximate results obtained by rounding figures will be acceptable. No change in key required.

(5) Question 1.12 NRC Resolution: Concur. Either answer is acceptable; answer key revised.

(6) Question 2.10(b)

NRC Resolution: Interlock as installed at facility has a basis regardless of training material coverage; therefore, no change in answer key required.

(7) Question.2.14(a)

NRC Resolution: Facility recommendation is an amplification of existing answers. No change to answer key required.

'(8) Question 2.16 NRC Resolution: Concur. Answer key revised.

(9) Question 2.17(d)

.NRC Resolution: Concur. Answer key revised.

(10) Question 3.11(a)

NRC Resolution: Concur. Answer key revised.

(11) Question 3.12(d)

NRC Resolution: Concur. Answer key revised.

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! (12). Question 3.13

!- NRC Resolution: Concur. Question deleted.

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(13) Question 3.17(b)

NRC Resolution: Concur. Answer key revised to include a more 1-descriptive signal.

(14) Question 4.01 i NRC Resolution: Caution on page 13, GP-007 has all referenced f conditions. No change in answer key required.

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c Enclosure 1 3 April 18, 1986 (15) Question 4.11(b)

NRC Resolution: Concur. Answer key revised.

(16) Question 4.15 NRC Resolution: Do not concur. Guidelines concerning symptom .

based E0P's, off-normal procedures are included in Examiner Standard 202, paragraph B.4, and Examiner Standard 402, paragraph -

A.3. No change in answer key required.

(17) Question 4.17(b)

NRC Resolution: Concur. Answer key revised.

(18) Question 4.19(b)

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NRC Resolution: Concur. Answer key revised.

b. SR0 Exam (1) Question 5.12 NRC Resolution: Reference to varicus measurements, are made-within the plant curve book, question required a conceptual knowledge of measurement types. No change in key required.

(2) Question 5.15 NRC Resolution: Concur. Answer key revised.

(3) Question 5.19 .

NRC Resolution: Do not concur. Facility comment does not require technical change to answer. No change to answer key required.

(4) Question 6.01 NRC Resolution:

(a) Concur. Answer key revised.

(b) Concur. Additional answer appropriate, candidate must provide original answers. Key revised.

(5) Question 6.02 .

NRC Resolution:- Point value reduced to .be consistent with Question 2.14(a). Answer key revised.

Enclosure 1 4 April 18, 1986 (6) Question 6.04 NRC Resolution:

(a) Concur. Answer key revised.

(b) Do not concur. No change to answer key required.

(7) Question 6.06(a)

NRC Resolution: Answers will be evaluated if assumptions provided. No change to the answer key required.

(8) Question 6.10 (Part 2)

NRC Resolution: Do not concur. No change in answer key required.

(9) Question 6.11 NRC Resolution: Same as R0 Question 2.16.

-(10) Question 6.13 NRC Resolution: Each condition may or may not be used; however, each case does have a corresponding condition. Case 2 - reference above comment. No change in answer key required.

(11) Question 6.14 NRC Resolution: Concur. Question deleted.

(12) Question 6.17(b)

NRC Resolution: Question used terminology provided in facility reference material. No change in answer key required.

(13} Question 7.15(b)

NRC Resolution: Same as R0 Question 4.11(b).

(14) Question 7.17(b)

NRC Resolution: Same as RO Question 4.17(b).

, (15) Question 7.22 NRC Resolution: Same as R0 Question 4.15.

(16) Question 7.24 NRC Resolution: Same as R0 Question 4.01.

L Enclosure 1 5 April 18, 1986 (17) Question 8.19 NRC Resolution: Concur. Answer key revised to accept actions of T.S. 3.3.1.3. only.

(18) Question 8.21

-NRC Resolution: Do not concur. Proctor gave candidates clarifi-cation during examination. No change to answer key required.

(19) . Question 8.22(b)

NRC Resolution: Concur. ' Answer key revised.

4. Exit Meeting At the conclusion of the site visit the examiners met with representatives of the plant staff to discuss the results of the examination. Those individuals who clearly passed the oral examination were identified.

There were no generic weaknesses noted during the oral examination.

The cooperation given to the examiners and the effort to ensure an atmos-phere in the control room conducive to oral examinations was also noted and appreciated.

The licensee did not ' identify as proprietary any of the material provided to or reviewed by the examiners.

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ENCLOSURE 3 U. S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION FACILITY: ROBINSON REACTOR TYPE: PWR-WEC3 DATE ADMINISTERED: 86/03/14 EXAMINER: ISAKSEN, P.

APPLICANT: _PBDgTO R_ _CJ3 9 f_ _ _ _ _ _ _ _ _ _ _

INSTRUCTIONS TO APPLICANT:

Uze 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 VALUE CATEGORY 30.00 25.00 PRINCIPLES OF NUCLEAR POWER

________ ______ ________--- -------- 1.

PLANT OPERATION, THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW 30 0 S PLANT DESIGN INCLUDING SAFETY

___1_0___ _'1_1_00 _ ___________ ________ 2.

AND EMERGENCY SYSTEMS 30 0 25 0 INSTRUMENTS AND CONTROLS

___I_0_._ ___1_0 _ ___________ ________ 3.

30.00 25*00 PROCEDURES - NORMAL, ABNORMAL,

________ ___ __ ___________ ________ 4. .

EMERGENCY AND RADIOLOGICAL CONTROL 120.00 100.00 TOTALS FINAL GRADE _________________%

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

~~~~~~~~~~~~~~

5PPL5C5UTI5~555U5TURE

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1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 2

--- isEER557AisiEi- REsi isissFEE is5 EEUi5 EE5s QUESTION 1.01 (3.00)

Compare the response of the following at BOL and EOL to a dropped rod at full power. (Assume all rods out, the dropped rod has the same worth at BOL and EOL, and the reactor does not trip.)

e. Initial power drop. (Greater or Less) Explain.

b. Rate of power change. (Faster or Slower) Explain.

c. Final steady state Tavs. (Higher or Lower) Expla.in.

QUESTION 1.02 (2.00)

a. Why does RCP pump amperage increase during a plant cooldown?

b. During RCS cooldown, why do the steam dumps have to be opened, further as temperature decreases to maintain the same cooldown rate?

QUESTION 1.03 (3.00)

The ratio of the PU239 and Pu240 atoms to U235 atoms increases over core life. Explain the effect this ratio change has on the fo110 win 3

a. Delayed neutron fraction

b. SUR for equal reactivity insertions.

c. Doppler Temperature Coefficient 00ESTION 1.04 (3.00)

a. Compare Xenon-135 and Samarium-149 fis,sion product poisons by EXPLAINING the differences AND the reasons for the differences for the following: (actual values are not necessary)

1. Time to reach equilibrium conditions after startup.

2. Ma3nitude of ne3ative reactivity at equilibrium conditions.

b., Explain why the following statement IS or IS NOT true.

' Equilibrium Xenon concentration at 50% power is NOT approximately half its concentration at 100% power'. (1.0)

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

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1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 3

--- iAEER557aERi5s- sEAi fEinsFEE AE6 FEUi5 FE5s QUESTION 1.05 (2.00)

A motor driven centrifugal pump is operating at rated flow when the discharge valve is throttled shut. How are the followin3 parameters affected by this action? (Increase, Decrease, or Remain Unchanged)

e. Motor current

b. Discharge pressure of the pump

c. NPSH available .

d. NPSH required QUESTION 1.06 (2.50)

a. If steam Soes through a throttling process, specifically as in a leak from a main steam header high pressure line to atmosphere, will the following parameters Increase, Decrease, or Remain the Same? (no e:<planation required) (2.0)

1. Enthalpy

2. Pressure

3. Entropy

4. Specific volume

~5. Temperature

b. State whether the steam will be Subcooled, Saturated, or Superheated at the point where it leaks out. (0.5)

QUESTION 1.07 (3.00)

During a reactor startup, will the actual

• critical position be NIGHER, LOWER or the SAME AS the estimated critical position calculated before the followin3 changes? EXPLAIN your .

choices. (Consider each change separately).

a. The operator starts warmin3 the main turbine prior to reaching

, criticality. (1.0)

b. Actual boron concentration was 30 ppm highe than the value used for figuring the ECP. (1.0)

c. Startup was delayed 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> beyond the ECP time; a shutdown time of 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> was used for the ECP. (1.0)

(xx*** CATEGORY 01 CONTINUED ON NE' , AGE **xxx)

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1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 4

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____________________________________________ j QUESTION 1.08 (2.50)

a. Explain the effect on Shutdown Margin of a 25 ppm boron addition while operating at 50% power with normal / automatic system lineup. (1.0)

b. List THREE factors, other than RCS baron concentration, which affect Shutdown Marsin and are used in the SDM calculation. (1.5)

QUESTION 1.09 (1.00)

Which one of the following conditions is the Moderator Temperature Coefficient MOST negative?

o. BOL, high temperature

b. BOL, low temperature

c. EOL, high temperature

d. EOL, low temperature GUESTION 1.10 (3.00)

m. How do each of the following parameters change (increase, decrease or no chanse) if one main steam isolation valve closes with the plant at 50% load. Assume all controls are in automatic and that no trip occurs.

1. Affected loop steam Senerator level (INITIAL change only) 2.- Affected loop steam Senerator pressure

3. Affected loop cold les temperature

4. Unaffected loop steam senerator level (INITIAL change only)

5. Unaffected loop steam Senerator pressure

6. Unaffected loop cold les temperature GUESTION 1.11 (2.00)

a. What is an advantage of condensate depression? (0.5) b., What is a disadvantage of condensate depression? (0.5)

c. Determine the condensate depression if the condenser is operating at 4' Hs absolute and the condensate temperature is 115-F. (1.0)

(xxxxx CATEGORY 01 CONTINUED ON NEXT PAGE xxxxx)

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1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 5

--- isEER667sAsiEs- sEAi isissFEE As5 FE6i6 FE60 OUESTION 1.12 (2.00)

It is the ultimate responsibility of the reactor operator to onsure that the core power distribution limits are maintained at all times. Operation within these limits is reasonably assured when four conditions are met. What are these FOUR conditions? (2.0)

QUESTION 1.13 (1.00) .

Explain how xenon can delay a reactor startup for a day or more near the cnd of core life.

(***** END OF CATEGORY 01 xxxxx) 1-f

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2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 6 QUESTION 2.01 (3.00)

Indicate how the following valves fail (open, closed, or not affected) by a sustained loss of Instrument air.

c. FCV-113A (Boric acid to blender)

b. FCV-113B (Blended flow to charging pump suction)

c. CVC-310 A&B (Char 3i ng flow to loops 182)

d. LCV-460 ARB (Letdown line stop)

o. Feed Res. valves -

f. LCV-1530B (Heater drain tank emergency dump to condenser)

QUESTION 2.02 (1.50)

Indicate whether the following statements are TRUE or FALSE concerning the Main Steam System. -

e. The flow nozzel (venturi) in the steam lines is used for flow instrumentation and will limit steam flow in case of a steam line break.

b. When all the MSR motor operated purge valves reach their fully open position, the air operated vent valves to the condenser will open.

c. For loads below 10%, all the MSR timer valves shall be open.

QUESTION 2.03 (1.00)

During Main Generator startup operations, before it is tied to the grid, which of the below adjustments will zero the regulator second sta3e output?

a. > Volta 3e Re3ulator in ' Test', using th'e Manual Field Current Adjuster.

b. Voltage ReSulator in " Auto', usin3 the Voltage Adjuster. .

c. Voltage Regulator in " Test', using the Volta 3e Adjuster.

d. Voltage Regulator in 'Off", usin3 the Manual Field Current Adjuster.

(xxxxx CATEGORY 02 CONTINUED ON NEXT PAGE xxxxx) l l

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2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 7 QUESTION 2.04 ( .50)

TRUE or FALSE?

The effluent of the Excess Letdown Heat Exchanger may be aligned to either the Reactor Coolant Drain Tank or the Volume Control Tank.

QUESTION 2.05 (1.00)

Indicate whether the followin3 are TRUE or FALSE in regard to the Instrument Air system.

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c. When the air compressor is operating in automatic it will run continuously with the air receiver pressure automatically bein3 maintained between 98 and 102 psis. by the unloader.

b. Instrument Air low pressure alarm will be received when the pressure drops to 95 psis.

QUESTION 2.06 (1.00)

Which of the following statements concerning the Individual Rod Position Indication system is correct?

s. The rod bottom bistable is adjustable and is normally set at 10 steps from the bottom of travel.

b. The rod bottom bistable only provides indication functions.

c. There is one control bank bypass bistable associated with each control bank except control banks A and B.

d. The control bank bypass bistable provides a blockin3 action on the turbine runback signal and the inhibiting of the automatic rod

, withdrawal when the rods of the associated bank are to be operated near or below the rod bottom bistable setpoints.

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(xxxxx CATEGORY 02 CONTINUED ON NEXT PAGE **xxx) i l

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2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 8 QUESTION 2.07 (1.00)

Indicate whether the following statements are TRUE or FALSE concerning the Reactor Protection system.

o. The 108 % Power Range nuclear flux trip does not provide protection until the low range trip is manually blocked.

b. The Intermediate RanSe high nuclear flux trip can be blocked if 1 of 4 Power Range channels is above 10 %.

QUESTION 2.08 (2.00) -

Indicate WHETHER or NOT each of the following signals / conditions would result in a main steam line isolation si3nal.

a. Low steamline pressure coincident with high steamline flow.

b. High steamline differential pressure.

c. Hi-I containment pressure. i si . i . . (o w e:- c e A . d p e r e- sdf0"d

$*d P #' #

d. Hi-II containment pressure. p //. -d is 4per Ced wed~ F = N QUESTION 2.09 (2.00)

e. What condition, IN ADDITION TO a SI or High S/G 1evel signal, will automatically close the main feedwater control valves? (1.0)

b. Which of the following is NOT a bases / reason for main feedwater isolation actuation? (1.0)

1. Prevents moisture carryover resultin3 in damage to the main turbine blading.

,2. Prevents / mitigates a loss of secondary coolant accident.

3. Prevents / mitigates excessive plant cooldown following a turbine '

trip.

4. Prevents / mitigates the consequences of the event which caused a SIS.

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

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2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 9 QUESTION 2.10 (1.50)

o. For which of the following turbine trip signals will the power circuit breaker from the generator immediately open (no time delay)? (1.0)

1. Manual Turbine Trip

2. Unit Aux Transformer. Fault Pressure

3. Overspeed Trip

4. Thrust Bearing Trip

b. What are the TWO ' safety-related' reasons for the time delay associated with the opening of the generator output breaker? (1.0)

QUESTION 2.11 (2.50)

State the type of automatic fire suppression system (water, carbon dioxide, or Halon) for each of the areas listed below.

a. Computer room

b. Unit 2 Startup transformer

c. Emergency switchgear room

d. Cable vaults

e. Hydrogen lube oil seal unit and manifold area QUESTION 2.12 (3.00)

a. ,What protection si3nals will generate

• safety injection actuation for a main steam line rupture outside of the CV upstream of the MSIV's? Setpoints and logic NOT required. .

b. What are the TWO major functions performed by the Safety Injection System to mitigate the effects of a main steam line rupture?

c.' Why is RCS cooling maintained after a main steam line rupture accident?

(***** CATEGORY 02 CONTINUED ON NEXT PAGE xxxxx) l F

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2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 10 QUESTION 2.13 (2.00)

List FOUR different systems / components that have interlocks which

, interface with the Penetration Pressurization System.

QUESTION 2.14 (3.00)

a. State FOUR locations that Service Water can be cross-connected.

b. -How is the Service Water system affected by an extended loss of power to the E-2 bus with a SI signal present?

c. Which of the followin3 statements concerning th'e purpose of the Service Water Booster pumps is correct?

1. Supply suction pressure to the service water pumps to meet NPSH requirements.

2. Insures that the cooling water to the HVH unit cooling coils will not boil or flash to steam durinS a desi3n basis accident.

3. Supply water pressure to the oil coolers on the emergency diesel generators.

4. Insures that the AFW pump NPSH requirements are met when service water is supplying feedwater to the S/G's.

QUESTION 2.15 (1.50)

Indicate whether the following statements are TRUE or FALSE concerning the Emergency Diesel Generator.

a. The main lobe oil pump and coolins water pump are driven by the diesel's upper crankshaft.

b. JWhen the diesel receives a manual sta'rt signale the signal will also start the diesel's ventilation equipment.

c. Three controls on the diesel speed governor are synchronizer, speed droop and load limit.

(xxxxx CATEGORY 02 CONTINUED ON NEXT PAGE xxxxx)

2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 11 QUESTION 2.16 (1.00)

If power is at 100 % and the Steam Dump is in Tavs mode when the first otage pressure channel 447 fails low, which of the following describes the response?

o. All 5 condenser dump valves and 3 steam generator PORV's arm.

b. All 5 condenser dump valves arm and trip open.

c. All 5 condenser dump valves arm.

d. There will be no effects on the Steam Dump syst.en because there has not been a load rejection nor trip.

QUESTION 2.17 (2.50)

State the type of detector used AND control function (s) upon receipt of an slarm (if any), for the followin3 RMS channelst

a. R-11

b. R-15

c. R-18

d. R-19

o. R-37 L

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

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3. INSTRUMENTS AND CONTROLS PAGE 12 l

QUESTION 3.01 (1 50)  ;

i Indicate whether the following statements are TRUE or FALSE concerning the Main Turbine and Controls.

o. The reheat stop valve and interceptor valve actuators can position these valves in any position from fully open to fully closed.

b. With the turbine auto-stop mechanism latched, the pilot-operated dump valve closes to build up fluid pressure under the cylinder piston, opening the reheat stop and interceptor valves.

c. Lubricating oil is used as the control medium for the interface emergency trip valve in the mechanical-hydraulic trip system.

QUESTION 3.02 (1.00)

If the Main Turbine Emergency Lubricating 011 Pump has been running and then the white lights on the RTGB so out, which of the following is correct? ASSUME no further operator action.

a. Pump discharge pressure is greater than 25 psis. and the pump is still running,

b. Pump discharge pressure is greater than 25 psis. and the pump has automatically stopped.

c. Pump discharge pressure is less than 25 psis. and the pump is stopped.

d. Pump discharge pressure is less than 25 psis. and the pump is still running.

4 (xxxxx CATEGORY 03 CONTINUED ON NEXT PAGE xxxxx) l

3. INSTRUMENTS AND CONTROLS PAGE 13 QUESTION 3.03 (2.00)

Cr,ncerning MANUAL protection actuation from the RTGB, match the following cetuations in Column A to their associated actions from Column B.

NOTE: Column B selections may or may not be used more than once.

Column A Column B

a. Containment Spray ('P' signal) 1. Depress ONE pushbutton

b. Safety Injection ('S' signal) 2. Depress TWO pushbuttons

c. Reactor trip 3. Change the position of a selector switch

d. Instrument air to C.V. override (with 'S' signal)

QUESTION 3.04 (1.00)

Which one of the following is correct concerning the Source Range channel high voltage cutoff?

a. During a reactor startup either IR channel increasing above P-6 will turn off the high voltage.

b. If one IR channel fails low while at power, the Source Range high volta 3e will be re-ener3 1zed.

c. Two out of four PR channels above 10% power will turn off the high volta 3e.

d. During a reactor shutdown either IR channel decreasins below P-6 will turn on the high voltage.

s (xxxxx CATEGORY 03 CONTINUED ON NEXT PAGE **xxx)

3. INSTRUMENTS AND CONTROLS PAGE 14 QUESTION 3.05 (2.00)

Indicate whether the Over Temperature Delta Temperature (OT-DeltaT) trip cetpoint will INCREASE, DECREASE, or REMAIN THE SAME for the following parameter changes. Consider each separately.

a. Increasing Tavs.

b. Tavs decreasing to less the than rated full power Tavg.

c. Delta I becoming more negative.

d. Pressurizer Presure increasing. ,

QUESTION 3.06 (1.00)

Which of the following statements concerning the effects of controlling PZR pressure channel PT-444 failing high during mode 1 operation is correct? Assume N0 operator action.

c. The master controller will cause control heaters to deenergize and both PORV's to fail open.

b. Both spray valves will remain open and RCS pressure reduction results in reactor trip and SI.

c. The reactor will trip on hiSh pressure signal.

d. The reactor will not trip on high pressure due to plant safety valve actuation reducin3 RCS pressure.

QUESTION 3.07 (2.00)

Indicate WHETHER or NOT each of the following statements concerning'the Low Temperature Overpressure Protection Subsy, stem (LTOPS) are correct.

o. Wide range pressure and auctioneered low narrow range temperature

. are inputs to the control circuitry. .

b. If the LTOPS requires the PORV's to open and the isolation valves are shut, the isolation valves automatically open.

c.* The purpose of the LTOPS is to protect the RCS from pressurized thermal shock.

d. In mode 1, a temperature input fails low and the LTOPS is armed the PORV's will fail open.

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

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3. INSTRUMENTS AND CONTROLS PAGE 15 QUESTION 3 08 (1.00)

Which one of the following is correct concerning the operation and const-ruction of the Power Range Excore detectors?

o. Uses Argon gas inside the detector to limit ' dead time.'

b. Has Baron Triflouride (BF3) gas in BOTH inner and outer volumes of the detector.

c. Operates in the proportional region of the gas amplification curve.

d. Uses no compensation circuitry to remove samma, current.

QUESTION 3.09 (1.00)

List FOUR devices / controllers that receive an input from auctioneered Tavs, OTHER than meters or recorders.

QUESTION 3.10 (1.50)

a. How will thermocouple indication be affected (increase, decrease or no change) by an INCREASE in reference junction temperature? (0.5)

b. Provide TWO sources where the reference junction temperature can be obtained, OTHER than locally, for the incore thermocouples. (1.0)

GUESTION 3.11 (2.00)

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c. Provide THREE locations / panels where S/G wide range level can be monitored outside of the control room. (1.5)

6. Where does the DS Diesel output breaker receive control power to

, charge its closing springs? '

(0.5)

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

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3. INSTRUMENTS AND CONTROLS PAGE 16 QUESTION 3.12 (2.00)

Indicate WHETHER or NOT each of the following is a result (DIRECT OR INDIRECT) when the PZR level channel 459 (controlling channel) fails high with NO operator action. Assume Mode 1 operation.

o. Charging flow decreases.

b. High pressure reactor trip and SI.

c. Letdown isolates.

d. High level reactor trip. ,

QUESTION 3.13 (1.00)

][EL_d N D Which one of the following conditions / interlocks must be satisfied, in order to allow for a manual reset of a SIS?

c. 20 seconds have elapsed since SI initiation.

b. Reactor trip breakers open.

c. PZR pressure above 2000 psis.

d. SI signal cleared.

QUESTION 3.14 (2.00)

List the FOUR automatic Safety Injection signals AND indicate whether or not the signal can be blocked. Setpoints and loS i e not required.

o

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

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3. INSTRUMENTS AND CONTROLS PAGE 17 QUESTION 3.15 (2.00)

Indicate whether the following are applicable to a Load Limit runback, Load Reference runback, OR both.

c. PRNI dropped rod signal.

b. RPI dropped rod signal.

c. OP or OT Delta-T runback signal

d. Inputs from both turbine first stage pressures above the pressure corresponding to 70% powere the runback continu,es until one pressure indication drops below 70% power.

QUESTION 3.16 (1.50)

The following concern the Rod Control System

a. The _____ unit converts the power mismatch signal to a temperature error in addition to varying the effect of larger load changes.

b. The _____ unit compensates for the different effects on the rate of change in thermal power for a given reactivity change at high and low power levels.

c. Why is a mismatch between nuclear power and turbine load signals possible during steady-state operation?

QUESTION 3.17 (2.00)

6. The Loose Parts Monitoring System (LPMS) detects the presence of metal-lic debris in the __1__ system. The metallic impacts generate pressure waves which are detected by __2__.

b. JWhat TWO signals will inhibit the LPM'S alarm?

(xxxxx CATEGORY 03 CONTINUED ON NEXT PAGE xxxxx) l i

3. INSTRUMENTS AND CONTROLS PAGE 18 QUESTION 3.18 (1.50)

c. What is the purpose / function of the turbine first stage pressure input to the S/G Level Control System (SGLCS)? -

b. Indicate whether feedwater flow would INITIALLY Increaser Decreaser or not changer if the controlling S/G pressure transmitter failed low during normal 50% power operation. Consider only the SGLCS, assume no operator action and no plant tripe and EXPLAIN your choice.

QUESTION 3.19 (2.00) ,

The following concern the Reactor Vessel Level Indicating System (RVLIS)

n. Where are the RVLIS strap on RTD's installed?

b. What is the purpose / reason for the strap on RTD's?

c. Which input signal is used to compensate the measured reactor vessel D/P when the coolant is saturated?

d. If the instrument loop RCP is not running the upper range will read approximately ____%, assume the other RCP's are running.

I

/ .

(xxxxx END OF CATEGORY 03 xxxxx)

4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE- 19

~~~~ - ------------------------

R5656L65565L 66NTR6L QUESTION 4.01 (1.00)

What is the reason for not exceeding 40% steam flow indication during a cooldown according to OP-001, Reactor Control and Protection System?

QUESTION 4.02 (1.00)

Select the malfunction which DOES NOT list an orderly reactor shutdown OR a reactor trip as an immediate action step, according to AOP-001, Malfunction of Reactor Control System procedure. -

c. More than 1 dropped rod.

b. Failure of e control bank to move in AUTO and MANUAL.

c. More than 1 misaligned control rod.

d. Continuous insertion of a control bank in AUTO and MANUAL.

QUESTION 4.03 (1.00)

If a loss of condenser vacuum is impending, with 23' Hs and decreasing, which of the following is NOT an immediate operator action according to AOP-012, Partial Loss of Condenser Vacuum procedure?

a. Reduce Turbine Generator load.

b. Verify the standby vacuum pump running.

c. Start the standby circulating pump.

d. Verify the Steam Generator levels not decreasing.

e (xxxxx CATEGORY 04 CONTINUED ON NEXT PAGE xxxxx)

4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 20

~~~~~~~~~~~~~~~~~~~~~~~~

~~~~Rd656L55fEAC CBNTR L QUESTION 4 04 (1.00)

Which one of the following statements concerning a dropped control rod and retrieval is correct according to AOP-001, Malfunction of Reactor Control System procedure?

o. Manually insert control rods to match Tref if rods are in manual.

b. The " Rod Control System Urgent Failure' alare must be reset prior to commencing retrieval of the rod.

c. Control rods will automatically withdraw to compensate for the dropped rod.

d. Tave should be controlled by baron changes during retrieval of the rod.

QUESTION 4.05 (1.00)

TRUE or FALSE?

o. If while implementing a red Functional Restoration Procedure (FRP), a higher priority red condition occurs, then the operator should leave the lower priority red FRP and immediately implement the higher priority red FRP.

b. In using the End Path Procedures (EPP's), the right hand column of actions is to be used ONLY if the associated action in the left hand column does not result in the response specified.

QUESTION 4.06 (1.00)

If the Plant Vent monitor (R-14) alarms, one of the required actions is to shift R-11 and R-12 to the plant vent. What must be done prior to shifting R-11 and R-12 according to AOP-005, Radiation Monitoring System procedure?

o. Ensure FCV-1436A is closed from the local panel.

b. Evacuate the containment.

c.* Perform a source check on R-11 and R-12.

d. Verify R-15 is operatins Properly.

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

4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 21

~ ~~~~~~~~~~~~~~~~~~~~~~~~

~~~~Rhd56L665 CAL 66NTR6L QUESTION 4.07 (1.00)

Redundant RTGB indicators which require operator attention are checked once o shift. This check is made by comparing the highest and lowest channels of redundant indicators for the same parameter on the same scale. Which of the following is the maximum acceptable deviation according to DMM-001, Operations - Conduct of Operations procedure?

o. 4% of the full range of the indicator's movement.

b. 4% of the highest reading indicator. *

c. 4% of the lowest reading monitor.

d. 4% of the average of the indicator's readings.

QUESTION 4.08 (1.50)

The following concern EPP-Se Natural Circulation Cooldown procedure

o. When is switchover of AFW pump supply to alternate water sources required?

b. While maintaining a cooldown rate of 25-F/hre what specific indication of temperature is utilized?

c. Why is RCS subcooling >190-F required during RCS cooldown/depressuriza-tion?

QUESTION 4.09 (1.00)

When performing equipment status checks on manual LOCKED valves, which one of the following describes how their posi, tion is verified?

o. Verifyin3 the lock is in place and securely locked.

b.' Verifying local valve position indication is indicating the required Position.

c. Operatin3 the valve in the open direction.

d. Operatin3 the valve in the closed direction.

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

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4. PROCEDURES - NORMAL ABNORMAL, EMERGENCY AND PAGE 22

~~~~R56 6L6656AE~C6NTR6E~~~~~~~~~~~~~~~~~~~~~~~~

QUESTION 4 10 (1.00)

While performing steps in EPP-le Loss of All AC Powere a SI signal may be ,

-Senerated. What must be done and why?

o. No action is necessary for the SI signal as it has no effect.

b. Reset the SI to permit manual loading of equipment on the emergency buses after power is restored.

c. Reset the SI to permit the D/G's to energize the emergency buses.

d. Place SI in test to prevent an overpressure transient on the RCS.

. QUESTION 4.11 (1.00)

Complete the following statement concerning EPP-9, Transfer to Cold Les Recirculation.

The maximum time between RHR flow termination during the injection phase and reinitiation of flow in recirculation phase must be less than ___(a) ___ minutes to prevent ___(b) ___ damage.

QUESTION 4.12 (1.00)

During a reactor startup, if criticality is attained above the control rod low insertion limit, but below the estimated critical position (ECP) lower band, which one of the following actions must be taken accordin3 to.GP-003, Normal Plant Startup from Hot Shutdown to C itical procedure?

a. , Insert rods to low insertion limit and recalculate ECP.

b..' Notify Reactor engineering personnel, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and continue normal startup operations. '

c. Reinsert all control banks to the bottom of the core, evaluate condition and recalculate ECP.

d. No special action is requiredi continue normal startup operations.

(***** C Al t GORY 04 CONTINUED ON NEXT P AGE ***** )

4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 23

~~~~

RA656E66ICAE~C6 TRUE~~~~~~~~~~~~~~~~~~~~~~~~

QUESTION 4.13 (2.00)

Which of the below choices of numbers would correctly complete the following precautions and limitations concerning starting and restarting Reactor Coolant Pumps in OP-101, RCS and RCP Startup and Operation procedure?

o. After any period of running, or after any attempt to start where the motor has failed to achieve full speed before it is stopped, a restart should not be attempted until the motor has bee,n allowed to cool by standing idle for a period of not less than __________ minutes.

Starts should not averaSe more than ________ per day throughout the life of the RCP motor.

1. 30, 4

2. 30, 6

3. 60, 4

4. 60, 6

b. Within any two-hour period, the number of starts should be limited to maximum of ______ (starts) with a minimum idle period prior to each restart. When these starts or attempted starts have been made within a two-hour period, then an additional s' art should not be attempted until the motor has been allowed to cool by standing idle for at least

_______ hour (s).

1. Two, Two

2. Three, Two

3. Two, One ,

4. Three, One QUESTION 4.14 (2.00)

The following ncern Foldout A of the EPP's

a. What is the RCP trip criteria?

b. What is the SI actuation criteria?

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

v - .a-e .

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4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 24

~~~~RA5i5C55fCAL C5NTR6E~~~~~~~~~~~~~~~~~~~~~~~~ ,

QUESTION 4.15- (3.50)

o. How is a reactor trip verified according to EPP-le Loss of all AC power procedure? (1.0)

b. What operator actions are required if a manual trip of the reactor fails from the RTGB, according to PATH-17 (FIVE actions required) (2.5)

QUESTION 4.16 (1.00) ,

Which of the following is the maximum time that a temporary change may remain in effect, accor_ ding to AP-004, Developmente Review and Approval of Procedures, Revisions, and Temporary Changes procedure?

o. 21 days

b. 30 days

c. 45 days

d. 90 days GUESTION 4.17 (2.00)

o. If an individual has already received a whole body exposure of 1000 stem this quarter, what would be the maximum additional exposure'to skin that is allowed without exceeding 10 CFR 20 limits? (0.5)

b. What are the H.B. Robinson administrative whole body limits according to DP-014e Quarterly Dose Limit Extension Authorization procedure for the following: (1.5)

, 1. No NRC Form 4? .

2. With NRC Form 4? .

3. With NRC Form 4 and approved exposure extension?

(rxxxx CATEGORY 04 CONTINUED ON NEXT PAGE xxxxx)

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4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 25

~~~~Rd65UEUU5E5L"6 NTR E~~~~~~~~~~~~~~~~~~~~~~~~

QUESTION 4.18 (1.50)

From the list of indications / characteristics in column B below, select those which are characteristics / indications for each of the accidents in column A. Note that indications / characteristics may be used core than once. (for example, 4. f,seh, 5. fri)

Column A Column B

1. Large LOCA a. Low S/G pressure

2. SGTR b. Low PZR pressure

3. Steam break in containment. c. Low PZR level

d. High CV pressure

e. High PZR level QUESTION 4'.19 (1.5/)

02 your answer sheet indicate the werd or words that serrectly sempletes th] following precautlens and llaltations of the "Neraal Plant Startup From H3t Shutdown To Critical" Procedure (GP-003).

c. If the countrate on either Source Range channel increases by a f aster of ______ or more during any step involving a boren concentration

'4 change, the operation must be stopped lamediately and suspended until a satisf actory evelation of the situation has been made.

b. The Control Banks must be maintained above their respective insertion llalts while the reactor is critical. When at power, ___ _ __

aust be initiated immediately if the " Rod Banks A/B/C/D EXTRA LO LIMIT" alare is actuated. -

c. " lux multiplication rates shall not be permitted to exceed __--

cacade(s)/ minute. .

QUESTION 4.20 (1.50)

List three different conditions that require an operator to emergency borate the Reactor Coolant System in accordance with AOP-002, Emergency Boration procedure.

(*x*** CATECORY 04 CONTINUED ON NEXT PAGE *****)

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40 PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 26

~ ~~~~~~~~~~~~~~~~~~~~~~~~

~~~~EA656L66f6dL 66UTR6L GUESTION 4.21 (1.50)

List three parameters that would require monitoring in order to determine if a Reactor Coolant Pump should be stopped due to a loss of seal injection.

QUESTION 4.22 (1.00)

During a plant startup to 100% power, how many MWe should be available before transferring the ti, 2, and 4 4160V Busses from the Startup Transformer to the Unit Auxiliary Transformer? ,

t (xxxxx END OF CATEGORY 04 xxxxx)

(xxxxxxxxx*xxx END OF EXAMINATION xxxxxxxxxxxxxxx) -

l t

1 l

l i i i

1 l

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~

. E0uAfton SHtti Where og = 82 L.

i teenstnylgtvelocityl i ternig = (eensity) (nlocity) (areair Et = evt Pt = egh Ptg+Ktg+PgVg = Pt 2+Kt +P t V22 where V = specific "Y volume P = Pressure 0 = &c,(Tout. Tin) 0 = UA (T, . Tim) 0 = 6(hg.hg) p = p,10(SUR)( t) p . p,,t/T syg . 26.06 T = (B.p)t I 7 delta K = (K,gp-1)/K,gg CRg(1-K,ggi) = CR2 (1-Reff2) CA

• 3/Il-Keff)

M = (1.K ,ggg) SDM = (1.K,gg) x 1005 Il-Keff2I Keff decay constant = In (2) = 0.693 A = A,e.(decay constant)m(t) t t 1/2 1/2 Water Parameters Miscellaneous Conversions t

1 gallon = 8.345 lbs 1 Curie = 3.7 x 10 10 dps 1 gallon = 3.78 liters 1 kg = 2.21 lbs .

I ft3 = 7.48 gallons I hp = 2.54 x 103 Stv/hr Density =62.4lbg/ft 3 1 MW = 3.41 x 106 Btu /hr Density = 1 pm/cm 1 8tu = 778 ft-lbf Heat of Vaporization = 970 Btu /lbe Degrees F = (1.8 x Degrees C) + 32 Heat of Fusion = 144 Btu /lba 1 inch = 2.54 centimeters 1 Atm = 14.7 psia = 29.9 in Hg g = 32.174 f t.lbm/lbf-sec 2 6

. I y 5

. 6 TABLE D It -

Properties of Dr3 Saloreled Sieam (aserdese6 Temperature speede venene Eminem $suee Temp., A b' 9i Set

• F 9" '

9'*

Ses les vepe les

• heed tw ,,,,

Sea g,,,g Eg ,,,,-

hee.4 af a A, 8a 8, e e o f

• , m 8f 3306 0.00 1975.8 1015.8 0.0000 2.1877 2.1877 32 0.05854 0.01602 0D1602 2947 3.02 1014.1 1977.1 0.006l 2.l709 2.1710 35 0 09995 2.1435 2.1597 2444 B.05 1011.3 1079.3 0 0162 40 0.12J10 0 01602 20M 4 13.06 1068 4 1081.5 00M2 2 1167 2.1429 45 0.14752 0.01602 1703.2 18.01 1065.6 1083.7 0.0MI 2.0003 2.1264 50 0.l7811 0 01603 28.06 1059.9 1084.0 0.0555 2DM) 2DH8 to 0.2563 0 01604 1206.7 1054.3 1002.3 0 0745 8.9902 2.0H7 70 0.M31 0.01606 367.9 30.04 0.01608 633.1 48 02 1048.6 1096 6 0.0932 l.W28 2 0360 IO 0.5069 0.6982 0.01610 468.0 57.99 1042.9 1100.9 0 til5 1.8972 2.0087 90 1.98M 0 01613 350.4 67.97 1037.2 1105.2 0.1295 1.8531 100 0.9492 77.M 1031.6 1809.5 0.1411 1.8106 1.9577 110 1.2748 0.01617 MS4 87.92 1025.8 til).1 0.lHS 1.76M l.93M 120 16924 0 41620 203.27 97.90 1020.0 t il7.9 0.1816 1.7296 1.9112 130 2.2225 0.01625 157.34 107.99 1014.1 1822.0 0.1984 1.6910 1.8894 140 2.8886 0 01629 123.01 150 3.718 0.01634 97.07 117.09 1004.2 IIM.I 0.2149 l.6537 1.8685 ,

77.29 127.39 1002.3 1130J 0.*311 1.6174 l.8405 160 4.741 0.01639 996.3 1834.2 0.2472 l.5822 1.8293 170 5.992 0.01645 62.06 137.90 147.92 990.2 1838.l 0.2630 1.5400 1.8109 ISO 7.510 0 01651 50.23 157.95 984.1 1142 0 0.2785 1.5147 1.7932 190 9.339 ODl657 40.96 33.H 167.99 977.9 1145.9 0.29M 1.4824 f.7762 200 11.526 0.0lM3 27.82 178D5 971.6 1849.7 0.3000 1.4500 l.1598 210 14.123 OD1670 910.3 1150 4 0.3120 1.4446 1.1566 212 14.696 0.01672 26 10 100.07 108.13 965.2 1853.4 0.3239 1.4201 1.7440 220 17.186 0 01677 23.15 958.8 1857.0 0.3387 1.M01 1.7288 230 20 790 0.01684 19.382 198.23 952.2 1140.5 0.3531 1.3609 1.7140 240 24.969 0.01692 16.32) 208.34 M5.5 1164 0 0.3675 1.3323 1.6998 230 29 825 0.01100 13.821 216 48 938.1 l167.3 0.3817 1.3043 f.6800 260 35 429 ODl109 II .M3 228.H 10.061 238.84 931.8 1870.6 0.3958 1.2M9 1.6727 270 41:358 0.01717

. 924.7 1873.8 0.4096 1.2501 1.6597 280 49.203 Chl726 8.645 249.06 p

7.461 259.31 917.5 llM.8 0.4234 1.2238 1.H72 290 $1.556 0D1735 910.1 1179.7 04M9 1.1980 1.6350 I 300 67413 0h1745 6 466 269.59 -

902.6 1182.5 0.4504 1.1727 1.6231 310 77.68 0.01755 5.626 279.92 894.9 1185.2 0.4637 l.1478 1.6115 320 39 M 0.01765 4.914 290.28 1.6002 330 103.06 0.01776 4.307 300.64 887.0 1987.7 0 4769 1.1233 1.5891 340 118.01 0.01787 3.788 311.13 879D 18901 0 4900 1.0992

,i--e-- .- '+%.

- r_ ., 9, , . - ,_.,,,.__,.-..-,,,,.,.---...--w.,- - ,., _ , , . -.,._,,..--,-,w--__-_,_,.,--.,,---,-c _-_

pl, Q' c, *. 1 b+

TABLE D.lb Properties ot Dr3 Saturated Seesm (amthats Temperature g Specdu solume E nthats Emers Temp.

'F #* hi hi hi

" Set Eiep hi hi heed weper head isper he.d E . epee e r .o e, b, he b, s. se s, 350 134 63 0 01799 3 34 32163 810 7 1192.3 0.5029 1.0754 1.5783 0 01811

• 3e0 153 04 2 957 332.18 852.2 1994 4 0 5158 1.0519 1.5677 370 173.37 0 01823 2 625 342 79 853 $ I196.3 0.5286 I0287 1.5573 .

380 195.77 0 018 % 2 335 353 45 544 6 1898 1 0 5413 1.0059 1.5471 390 220.37 0 01850 208% 364 17 835 4 1899.6 0.5539 0 9832 1.5371 400 247.31 0 01864 I8633 374.97 826 0 1201.0 0.5664 0 9408 1.5272 410 276.75 0 01878 I.6700 385 83 816.3 1202.1 0.5788 0 9386 1.5174 420 308 83 0 01894 1.5000 396 77 806 3 1203.1 0.5912 0.9 th I.5078 430 343 72 0.01910 1.3499 407.79 796 0 12038 08035 0.8947 1.4982 440 381.59 0.01926 1.2171 418 90 785 4 1204.3 0 6158 0 8730 1.4887 450 422.6 0.0194 1.0993 4301 774.5 1204 6 0.6280 0 8513 1.4793 480 AM 9 0.0196 0 9944 44I 4 763.2 1204 6 0 6402 0 8298 1.4700 410 514.7 0 0198 0.9009 452 8 751.5 1204.3 0 65:3 0 8083 1.4606 480 %6.1 0 0200 08172 464 4 739 4 1203.7 06645 0 7868 14513 490 621.4 0 020: 0.7423 476 0 7268 1202.8 06766 0 7653 1.4419 500 680 8 0 0204 0.6749 487.8 713 9 1201.7 0 6487 0.7438 14325 520 812.4 0 0209 0.5594 511.9 686 4 1198 2 0.7130 0.7006 1.41 %

$40 962.5 0 0215 04649 5%6 6%6 1193 2 0.7374 0 6568 I.3942 Seo  !!)3.1 0 0:21 0 3868 M22 624.2 l186 4 0 7621 0.612l 1.3742 ,

580 1325.8 0 0:28 0.3217 588 9 548 4 l 177.3 0 7872 0.M59 1.353:

400 1542.9 0 02 % 02664 610 0 548.5 1165.5 0.8131 0.5176 1.3307 620 1786 6 0 0247 0.2201 646.7 503 6 l150.3 0 8398 0 4664 1.3062 640 2059.7 0 0260 0.1798 678.6 452 0 l 130.5 0 8679 0 4110 1.2789 660 2%$4 0 0278 0.1442 714.2 390.2 l104 4 0 8987 0.3485 1.2472 680 27081 0 0305 0.1115 757.3 309.9 ,

1067.2 0.9351 0.2719 1.2071

• I 700 3093 7 00%9 0 0761 823.3 172.1 995 4 0 9905 0.1484 1.1389

, 705 4 3206.2 0 0503 0 0503 902 7 0 902.7 1.0540 0 1.0580 a .

9 r- -

e - .-n.,-w --v-. .-

m ----e -o---+,.n- - , ---,,g<m -. - , . - , , - - - - , , , - - , - -n e---,--

," \, e w.

TABLE D la' Propenses of Dr) Saturain! Steam +

Pressure a 7 amp.

Scecir. voa.m. Enthain Entron preu . .

ps 9 Sai Sai lei g'W Set Set 3.

I.ea d vapor lie d vapor lie d Sver p , e, e, e, 4, 4, ,, ,, ,,

1.0 101.74 0 01614 333 6 69 70 10M.3 Il06D 0 1326 1.84 % 1.9M2 20 126 08 0 01623 173 73 . 93 99 1022.2 1116.2 0.1749 3.0 141.48 f.7451 1.9200 0 01630 III 71 109 37 1013.2 1122.6 0.2005 1.6855 1.8863 4.0 152 97 0 01636 90 63 120 66 1006 4 1127.3 0.2198 l4427 l.8625 5.0 162.24 0 0lH0 73.52 130.13 1001.0 1831.1 0.2347 2.80N l.8441 60 170 06 00lH5 61.98 137.96 996.2 1834.2 0.2472 1.5820 1.8292 1.0 IM 85 00lH9 53 H 144. 4 992.I IIM.9 0.2541 1.5586 1.8167 8.0 182.86 0.01653 47.34 9.0 150 79 988.5 llM.3 0.M74 I.5M3 1. 5 57 188.28 0 01636 42 40 156 22 985.2 1141.4 0.27M I.5203 1.7962 10 193.21 0 01659 3842 161.17 982.1 1143.3 0.2835 1.3041 1.78 4 14 696 212.00 0 01672 26 80 180 07 970.3 1830 4 0.31 2 1.4446 1.7566 15 213 03 0.01672 26 29 181.11 969.7 1830.8 0.3135 1.4415 1.7549 20 227.% 0.01683 20 089 196.16 960.1 IIM.3 0.33M l.3962 1.7319 25 240 07 0 01692 16 30) 208 42 952.1 1840 6 0.3533 1.3006 1.7t M -

30 250.33 0.01701 13.746 218 82 945.3 IlW.I 0.3680 1.3313 I.6993 35 259.28 0 08708 II.89s 227.91 9M.2 1867.1 0.M07 1.J063 IA010 40 267.25 0.01715 10 498 2M.03 933.7 1169.7 0.M19 1.2844 1.643 45 274.44 0 01721 9.401 243.M 928.6 1872.0 0 4019 I.2630 IA660 30 281.01 0 01727 8.515 230.09 924 0 1874.1 0 4110 1.2474 14585 55 287.07 0 01732 7.787 2M.30 919 6 1875.9 0 4193 1.2316 1.65(N 80 29211 0 01738 7.175 262.09 915.5 11774 0.4270 1.2168 1.64M 65 297.97 0 01743 6.655 267.30 til 6 1879.1 0.4M2 1.2 32 14374 10 302 92 0.01748 6 306 272.61 907.9 1180 6 0 4409 1.1906 14315 75 307.40 0 0175.1 5.816 277.43 904.5 l181.9 0 4472 1.1787 14239 -

80 312.03 0.01757 3472 282.02 901.1 1183.1 0 4531 1.16M l.6207 g 85

, 316.25 0.0141 5.168 286.M 89 [8 1884.2 0.4587 1.1571 I A158 90 320 27 0 01 % 6 48% 290.M 894.7 1885.3 0 4641 1.1471 1.6112

~. 95 324.12 0.01770 4 652 294 % 891.7 l186.2 0 4692 1.1376 1.6068

• 100 327.81 0 01774 4 432 298 40 888.8 l187.2 0 4740 1.1286 1.5-?26 110 334 77 0.01782 4.049 305 66 883.2 1988.9 0 4832 1.1117 1.9948 4

i

=

-e- ~-,.m , v - - . - - e e_-, - -- ,- - ,---- r-e--e + y wm.p- ~w- -

m-- +-s-------p- w-- g--

a..

n

. . . . s e s e e

e TABLE D la Propenies of Dr) Saturated Steam tremem,c4#

Preuurt UN Aho 7eme .

Sei Sei Sei Sei les Sei C** +1r lie d veper Wed Ew ,,,,, g,,,4 Eiap ,,,,,

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1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 27

--- isEEs557sAsiEs- sEAi isissFEE As5 FE5i5 FE5s ANSWERS -- ROBINSON -86/03/14-ISAKSEN, P.

ANSWER 1.01 (3.00)

c. The initial power drop will be greater at EOL CO.53. The smaller B, the greater the prompt drop for a given reactivity addition E0.53.

b. The reactor responds faster at EOL [0.53. The smaller B, the higher the SUR for a given reactivity insertion CO.53.

c. Tave will be lower at BOL E0.53. The smaller MTC requires a larger temperature drop to balance the neSative reactivity inserted by the rod CO.53.

REFERENCE CP&L Reactor Theory Chap. 12 p.22 and Chap. 14 p.6 HBR RXTH-HO-1, Session 47.

ANSWER 1.02 (2.00)

a. As temperature decreases the density of the fluid increases, thus more power is required to pump the heavier fluid. (1.0)

b. As temperature decreases both the steam density and steam velocity (dP across the valves) decreass. Thus the steam dump valves must be opened further to maintain a constant flow rate. (1.0)

REFERENCE General Physics HT&FF p. 319-344 & 351-354

' ANSWER 1.03 (3.00)

c. Delayed neutron fraction decreases CO.53 because the beta is less for Pu239 as compared to U235. [0.53 (1.0)

b. Higher SUR CO.53 because delayed neutron fraction decreases over core life.CO.53 (1.0)

c. Doppler Coefficient is more negative E0.53 because Pu240 has a higher resonance cross section than u235. [0.53 (1.0) 413V

V 4

1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 28

--- isEER55isisics- sEAi isAssFEs As5 FEUi5 FE5s ANSWERS -- ROBINSON -86/03/14-ISAKSEN, P.

REFERENCE Nuclear Energy Training p.5.3, 6.2, 11.3 HBR RXTH-HO-1, Session 47.

ANSWER 1.04 (3.00) e.l. Samarium takes much longer to reach equilibrium conditions E0.53 because it, is formed by decay of a precursor with a longer half life than for Xenon CO.53. (1.0

2. Xenon has the most worth at equilibrium E0.53 because it is more abundant E0.253 and because it has a higher neutron absorbtion cross-section E0.25] (1.0)

b. True CO.53, Equilibrium Xenon is flux dependent and non-linear since burnout is relatively less significant at 50% power than at 100% power (production is flux dependent but the removal terms are not both flux dependent) E0.53 (1.0)

REFERENCE Nuclear Energy Training Unit 10 HBR RXTH-HO-1, Session 37 and 38.

ANSWER 1.05 (2.00)

a. Decrease

b. Increase

c. Increase

d. Decrease E0.5 each] (2.5)

REFERENCE WNTC Thermo.

General Physics HTFF, p 319-334.

}

1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PACE 29

--- isEER557EARiEE- REEi iEissFEE An5 FEUi5 FE5E ANSWERS -- RODINSON -86/03/14-ISAKSEN, P.

ANSWER 1.06 (2.50)

s. 1. Remain the same

2. Decrease

3. Increase

4. Increase

5. Decrease [0.4 each] (2.0)

b. Superheated (0.5)

REFERENCE General Physics HTFF, Chapter 2, Steam Tables.

ANSWER 1.07 (3.00)

a. ACP LOWER than ECP because the lowering of temperature will insert positive reactivity resulting in criticality at a lower rod height. (1.0)

b. ACP HIGHER than ECP because the higher boron concentration inserts negative reactivity, resulting in a higher rod height. (1.0)

c. ACP LOWER than ECP because xenon concentration will be decreasing which inserts positive reactivity therfore a lower rod height. (1.0)

REFERENCE C-E Reactor Theory HBR RXTH-HO-1, Session 51.

1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 30

--- isiss557nisiCi- sEAi isissFER As5 FE5i5 FE5s ANSWERS -- ROBINSON -86/03/14-ISAKSEN, P.

ANSWER 1.08 (2.50)

a. SDM is increased CO.53, with an increased baron concentration the amount of reactivity by which the reactor is or would be subcritical from its present condition is increased E0.53 (1.0) b.

'ivt i s a n f K r.'y.P M I L. ; f f '/b

1. Control rod position 4. Xenon concentration

2. RCS average temperature (Time since shutdown)

3. Fuel burnup 5. Power level (1.5) 6.gSamarium/ t/WW ctthI ( 3 9 0. 5 e a )

REFERENCE C-E Reactor Theory HBR RXTH-HO-1, Session 50.

ANSWER 1.09 (1.00) c REFERENCE Instr. Notes; Review of Reactivity Coefficients.

HBR RXTH-HO-1, Session 26, p 2.

ANSWER 1.10 (3.00)

c. 1. Decrease

2. Increase ,

3. Increase

4. Increase

5. Decrease

6. Decrease E0.5 each]

REFERENCE Simulator Malfunction #179.

HBR RXTH-HO-1, Session 48.

l l

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1.

PRINCIPLES OF NUCLEAR POWER TION, PLANT OPERA

--- isEss55isAsiEs- REEi iEEssFEE FE5s Es5 FEG PAGE 31

- ROBINSON ______________________________________i5 ANSWERS ______

-86/03/14-ISAKSEN, P.

ANSWER 1.11 a.

(2 00)

Increases NPSH

b. (prevent cavitation)

Reduced efficiency

c. 4' (0.5)

Hs = 1.9632 psiaCO.253 Tsat vs table 1 is used) = 125-FCO.53 (0.5) 125-115 = (-0.25 if table 2 REFERENCE 10-F condensate depressionCO.253 GP HT&FF Sect II, Part B, (1 0) p.

155-159; Sect. III Part B, p.

ANSWER 1.12 319-320.

(2.00)

- All control rods no single rod in the position from the bank demand bank differin 3 by morein ogether awith single bank are moved than 15 inches

-- Control Control rod groups are sequenc.

- Axial powerrod insertion limits are observeded with bank properoverlap.

j the AFD requirements. og /// f0C- dTdistribution e limits is of maintained within th

\

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REFERENCE CO.5 each]

\

WNTC Rx Core Control, 8-32 (2.0)

{ HBR TS, p 3.10-13.

ANSWER 1.13 (1 00)

Followins a reactor shutdown Xe will reactivity in the startup below thanwould the existin3 excesseactivity.

result until r increase If and may add more nes this occured, the existin3 excess reactivity.Xe peaked and then decayed toaa delay REFERENCE val ue HBR RXTH-HO-1, 39, p.2.

2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 32 ANSWERS -- ROBINSON -86/03/14-ISAKSEN, P.

ANSWER 2.01 (3.00) l

a. OPEN

b. CLOSED

c. OPEN

d. CLOSED

9. CLOSED

f. OPEN [0.5 each3 (3.0)

REFERENCE HBR AOP-017, p 9,10.

ANSWER 2.02 (1.50)

a. T.

b. T.

c. F.

REFERENCE HBR/SD-025 pp. 1, 8, 11, 23a.

! ANSWER 2.03 (1.00) c.

REFERENCE HBR/SD-034, p. 53.

ANSWER 2.04 ( .50)

T.

2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 33 ANSWERS -- ROBINSON -86/03/14-ISAKSEN, P.

REFERENCE HBR/SD-021, p. 10.

ANSWER 2.05 (1.00)

8. F

b. F REFERENCE HBR/SD-017, pp. 7, 8.-

ANSWER 2.06 (1.00) d REFERENCE HBR/SD-009, p. 3.

ANSWER 2.07 (1.00)

c. F

b. F REFERENCE HBR SD-011, p 2r5.

ANSWER 2.08 (2.00)

a. Yes

b. No

c. No

d. Yes [0.5 each3 REFERENCE SHNPP ESFAS-HO-1.0, p 10.

HBR DWG-No CP-300-5379-2759.

- - - , , -.r -e y , -y , . - - - . - - , , ,.--,,1,.,w, ,w-..,,.r-,.y- - - ,w,,,, ,.e .m.. --,w- , ... ~ . .,. mr.-e.,- y,,-.. .- , , , - - - -

2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 34 ANSWERS -- ROBINSON -86/03/14-ISAKSEN, P.

ANSWER 2.09 (2.00)

c. (P-4) reactor trip breakers open and Low Tavg. (1.0)

(also accept loss of instrument air or DC power)

b. 3 (1.0)

REFERENCE SHNPP ESFAS-HO-1.0, p 4,10,11.

HBR DWG No CP-300-5379-2761; SD-027 p 13.

ANSWER 2.10 (1.50)

a. 2 (0 5)

b. 1. Prevent loss of RCS forced flow.

2. Prevent / limit RCP- overspeed. Cadd. wrong reason -0.253 (1.0)

REFERENCE P

SHNPP GEN-HO-1.0, p 14,15.

HBR DWG No CP-300-5379-3695; SD-033.

ANSWER 2.11 (2.50)

a. Halon (0.5)

b. Water (0.5)

c. Halon (0.5)

d. Carbon dioxide (0.5)

e. Water (0.5)

REFERENCE HBR SD-041; -043; -0443 P 5; 045 p 8; 047 p 5.

.-.- - - - - - - - , , , . - - , - - , - - , , , - , . .- , ,. -y--. , . . - _ , , - - . . . . - .

. , - , , - _ _ ---.._,-.-._,p, ,r-,, ,e--,- - - - - - , - - ---w.-. - . . --,,m-,,. r--

2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 35 ANSWERS -- ROBINSON -86/03/14-ISAKSEN, P.

ANSWER 2.12 (3.00)

e. PZR low pressure High steamline differential CO.5 each]

b. -Inject concentrated boric acid to compensate for the positive reactivity caused by the cooldown. [0.53

-Provide makeup to restore PZR level from the ' shrinkage' caused by the cooldown. [0.53

c. To prevent a pressure transient (PTS) resulting from subsequent RCS heatup and expansion from decay heat. E1.03 REFERENCE HBR SD-002, p 28; exam bank 2-6-25.

ANSWER 2.13 (2.00)

-CV Purse

-Vacuum relief

-Pressure relief

-Personal air lock

-RMS inlet and outlet valves Efour required, 0.5 each]

REFERENCE HBR SD-037, p 11.

ANSWER 2.14 (3 00)

m. -Turbine bids supply

-SW booster pump suction

-SW booster pump discharse

-Aux bids hallway (above booster pumps

-A diesel room

-Intake structure of SW pump discharge

-Intake structure of SW to cire. water Pump seals. Cfour required](1.0)

b. Supply to the turbine bids. shuts to.53, and only two SW pumps have power available.CO.53

c. 2 I

, . - , . _ . - , . . - . - . . . . . . _ , _ , , , , , , _ ..,_,,,7 . _ , , , , . _ __,

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

2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 36 ANSWERS -- ROBINSON -86/03/14-ISAKSEN, P.

REFERENCE HBR SD-004; -006.

ANSWER "( .13 (1.50)

c. F

b. T

c. T REFERENCE HBR/SD-005 pp. 2-3.

ANSWER 2.16 (1.00) US

[b REFERENCE HBR/SD-025, p. 16.

ANSWER 2.17 (2.50) ,

s. Scintillation-isolates CV purse, vacuum and pressure relief.

b. GM-Shifts AE exhaust to the plant vent.

c. Scintillation-isolates liquid waste release (RCV-018). g f

d. Scintillation-isolates S/G blowdown, sample and blowdown tank drain.

C/ Vf Si

e. Scintillation-isolates condensate polisher waste (RCV-10549).

REFERENCE HBR SD-019, p 12-20.

1

- Y t 1

3. INSTRUMENTS AND CONTROLS PAGE 37 ANSWERS -- ROBINSON -96/03/14-ISAKSEN, P.

ANSWER 3.01 (1.50)

a. F

b. T

c. T REFERENCE HBR/SD-033 pp. 12-15.

ANSWER 3.02 (1.00) e.

REFERENCE HBR/SD-033, p. 20.

ANSWER 3 03 (2.00)

a. 2.

b. 1.

c. 1.

d. 3. [0.5 each3 (2.0)

REFERENCE HER Dws. No.'s 300-5379-3753; -2759 HBR/SD-006, Ps. 4, 5, 10, 12 ANSWER 3.04 (1.00) c REFERENCE FNP, Excore Nuclear Instrumentation System '

WBN, LP - Excore Instrumentation, pp. 10, 13, & 14 SHNPP RPS-HO-1.0, p 12.

HBR SD-010, p 9,20,21,25.

i - -i

3. INSTRUMENTS AND CONTROLS PAGE 38 ANSWERS -- ROBINSON -86/03/14-ISAKSEN, P.

ANSWER 3.05 (2.00)

a. DECREASE

b. INCREASE

c. DECREASE

d. INCREASE CO.5 each]

REFERENCE FNP, Tavs, Delta T, and Pimp, pp. 16 & 17 Surry, Instrumentation Manual, Sect. 9, p. IV-5.5 WBN, LP - Reactor Coolant Temperature Instrumentation, p. 8 3HNPP RPS-HO-1.0, p 14,15.

HBR SD-011, p 17.

ANSWER 3.06 (1.00) b REFERENCE SHNPP PZRPC-HO-1.0, p 25.

HBR SD-001, p 34,35.

ANSWER 3.07 (2.00)

a. No

b. No

c. Yes

d. Yes (CAF) [0.5 each]

REFERENCE SHNPP PZRPC-HO-1.0, p 22, fig. PZRPC-TP-5.0.

HBR DWG No HBR2-8643.

ANSWER 3.08 (1.00) d.

REFERENCE HBR/SD-010, pp. 6, 19-22.

i . >

3. INSTRUMENTS AND CONTROLS PAGE 39 ANSWERS -- ROBINSON -86/03/14-ISAKSEN, P.

ANSWER 3.09 (1.00)

Steam dump Rod control PZR level Feedwater isolation Tavg-Tref alarm Efour required, 0.25 each3 REFERENCE HBR SD-001, 007, 011, 025, ANSWER 3.10 (1.50)

a. Decrease EO.53

b. Saturation monitor, P-250 computer.EO.5 each3 REFERENCE HBR SD-012, p 12.

ANSWER 3.11 (2.00)

a. AFW pump room Secondary control panel CharSing pum control,roo

-W* C k,^td.CO.5

/L each].w f u) h//' V(/W 5 b.

07 he From the out ut of the DS Diesel E0.53 REFERENCE HBR Exam Bank, 2-6-54.

ANSWER 3.12 (2.00)

c. Yes

b. No

c. Yes

d. yt 5 s E0.5 each]

REFERENCE SHNPP PZRLC-HO-1.0, p 19.

HBR SD-001, p 34.

i . ,

3. INSTRUMENTS AND CONTROLS PAGE 40 ANSWERS -- ROBINSON -86/03/14-ISAKSEN, P.

ANSWER 3.13 (1.00) b CAF REFERENCE SHNPP ESFAS-HO-1.0, p 7.

HBR SD-006, p 8-12.

ANSWER 3.14 (2.00)

Low PZR pressure-YES High steamline differential-YES High steamflow (coincident with low Tavs or low steamline pressure)-YES High Containment pressure-NO [0.'5 each3 REFERENCE

- HBR SD-002, p 7,26, ANSWER 3.15 (2.00)

a. Both

b. Load Limit

c. Load reference

d. Load Limit E0.5 each]

REFERENCE HBR SD-011, p 26-28.

ANSWER 3.16 (1.50)

a. Non-linear

b. Variable gain

c. Because the power mismatch circuit is rate sensitive (zero output and control is based now on Tavs) [0.5 each]

REFERENCE HBR SD-007, p 21,22.

4

, - - . - - ~,,- - - , ,m--- n, - , , , , , , , ,--wn-, - , . , - . , - - - . , - - - y o---+ --m-, ,- -

'1 S

3. INSTRUMENTS AND CONTROLS PAGE 41 ANSWERS -- ROBINSON -86/03/14-ISAKEEN, P.

ANSWER 3.17 (2.00)

3. 1-RCS 2-accelerometers

b. Manual O hn la Control rod cabinet p,/LTh E0.5 each3 REFERENCE HBR SD-052, p 4,18.

o ANSWER 3.18 (1.50)

a. Provides the programmed water level setpoint CO.53.

b. Decreases CO.253, the loss of pressure compensation causes the steam flow signal to decrease which causes the steam flow-feed flow error signal to close the FWRV.CO.753 REFERENCE HBR SD-027, p 12,19.

ANSWER 3.19 (2.00)

o. The impulse lines (inside CV)

b. To compensate the D/P measurement for temperature changes inside the CV (i.e. accident conditions inside CV).

c. Wide range RCS pressure.

d. 90.

REFfRENCE HBR SD-051, p 7,11,13.

9

40 PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 42

~~~~ ~~~~~~~~~~~~~~~~~~~~~~~~

R 65 E66565E~C6UTR L ANSWERS -- ROBINSON -86/03/14-ISAKSEN, P.

ANSWER 4.01 (1.00)

This in conjunction with low steam line pressure or low tavs will initiate SIS and steam line valve closure. (1.0)

REFERENCE HBR OP-001, p 5.

ANSWER 4.02 (1.00) b (1.0)

REFERENCE HBR AOP-001.

ANSWER 4.03 (1.00) d REFERENCE HBR AOP-012, p 4-5.

ANSWER 4.04 (1.00) a REFERENCE HBR AOP-001, p 15-18. -

ANSWER 4.05 (1.00)

a. T.

i b. T.

! REFERENCE l HBR OMM 22, p 6,7,12,13.

. v

4. PROCEDURES - NORMAL, ABNORMAle EMERGENCY AND PAGE 43

~~~~

RA5i5E55fEAC 55aTR6E~~~~~~~~~~~~~~~~~~~~~~~~

ANSWERS -- ROBINSON -86/03/14-ISAKSENe P.

ANSWER 4.06 (1.00) b.

REFERENCE HBR ADP-005, p 15.

ANSWER 4.07 (1.00) a REFERENCE HBR OMM-001, p 45.

ANSWER 4.08 (1.50)

a. If CST level drops below 10%.

b. RCS wide ranse cold les temperature.

c. Prevent steam voidin3 in the reactor vessel. CO.5 each]

REFERENCE HBR EPP-5, p 5,6,10.

ANSWER 4.09 (1.00) ,

d REFERENCE HBR AP-027, p 6.

ANSWER 4.10 (1.00) b (1.0) i i

, .- m

4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 44

~~~~R d6 6L65 65L'6UUTR6t ANSWERS -- ROBINSON -86/03/14-ISAKSEN, P.

REFERENCE HBR EPP-1, p 6.

ANSWER 4.11 (1.00)

a. 10 (0.5)

b. fvel m 4'N' b y (0.5)

REFERENCE HBR EPP-9, p 5.

ANSWER 4.12 (1.00) c REFERENCE HBR GP-003, p 25.

ANSWER 4.13 (2.00)

a. 2 ,

b. 4 REFERENCE HBR OP-101, p 10-11.

ANSWER 4.14 (2.00)

a. At least one SI pump running Less than 25-F subcooling (C35-F])

b. Less than 25-F subcooling (C353)

Cannot maintain >10% PZR level CO.5 each]

REFERENCE HBR EPP Foldout A.

i l

1

4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 45

~~~~EA656[6656A[~C6UTRUE~~~~~~~~~~~~~~~~~~~~~~

ANSWERS -- ROBINSON -86/03/14-ISAKSEN, P.

ANSWER 4.15 (3.50)

a. RX trip and bypass breakers open Neutron flux decreasing

b. Manually insert control rods Manually trip the turbine Sta t AFW or FW pumps Ir.:tiate emergency boration of the RCS D: a ztch operator to trip the rod drive MG sets CO.5 each3 REFERENCE >

HBR EPP-1, p 3; PATH-1.

ANSWER 4.16 (1.00) a REFERENCE HBR AP-004, p 30.

ANSWER 4.17 (2.00)

a. 6500 mrem. L60.53

b. 1. 375 mren Y

2. 1250 mrea

3. 3000 mren E0.5 each3 REFERENCE 10 CFR 20; HBR DP-014, p Si HPP-001, p 5.

ANSWER 4.18 (1.50)

1. b,ced.

i

2. bec.

3. arbaced,(e). 00.5 each]

l l

5 i

l

. i- .

4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 46 EUNTR5[------------------------

~~~~

RI65UE655EEE ANSWERS -- ROBINSON -86/03/14-ISAKSEN, P.

REFERENCE HBR SD-00,2, p 27.

ANSWER 4.19 (1.50)

a. t, c'

. b. EmergencyCO.23 BorationC0.S]. (%C)' 8#

c. 1 REFERENCE HSR/GP-00Ss pp. 10-12.

ANSWER 4.20 (1.50) 9 0.5 points each, any three of the following:

1. Excessive control rod insertion (below limit).

2. Uncontrolled cooldown following a reactor trip.

3. Unexplained or uncontrolled reactivity increases.

4. 2 or more RPIs fail to indicate rods fully inserted after a trip or normal shutdown.

REFERENCE

) HBR AOP-002, pp.3-4.

ANSWER 4.21 (1.50)

Any 3 0 0.5 points each!

1. CCW flow to thermal barr ier (<25 spm)

2. CCW inlet temp (>105F)

3. Pump bearing temp (>180F)

4. No. 1 seal leakoff temp (170F)

REFERENCE HBR AOP 18, p.14.

ANSWER 4.22 (1.00) 100 MWs t

\

y .-

o t' D 1 40 PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND '

PAGE 47

~~~~

Rd6 6E6656AE~C6UYR6E~~~~~~~~~~~~~~~~~~~~~~~

ANSWERS -- ROBINSON -86/03/14-ISAKSEN, P.

REFERENCE HBR GP-005, p.25.

W

.w d

[

t e

ew.6 g v

y-4 &'

4*.

t 4

+-

e-I.

-. - , , , . .,,,-,.-....__,.,,---,-,,c, , , - - . .

2 a

,e ENCLOSURE 3

'O A~

y U. S.-NUCLEAR REGULATORY COMMISSION' SENIOR REACTOR OPERATOR LICENSE EXAMINATION FACILITY: ROBINSON REACTOR TYPE: PWR-WEC3 s DATE ADMINISTERED: 86/03/14 EXAMINER: TOM ROGERS APPLICANT!' _ PR_OCT,O R_ _QO?_X_ _ _ _ _ _ _ _ _ _

INSTRUCTIONS TO APPLICANT:

Use separ, ate 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 VALUE CATEGORY

_------- __- g- -___-_----_ ----_--- -------_---------------------------

30.00 25.00

5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND q// , o c ' ,1 *F. J :. THERMODYNAMICS f.#

30, 25iOO 6. PLANT SYSTEMS DESIGN, CONTROL, r

AND INSTRUMENTATION v

30 0 '5 00 PROCEDURES - NORMAL, ABNORMAL,

-__1_0___ _1_1__ ___________ ________ 7.

EMERGENCY AND RADIOLOGICAL CONTROL 30.00

_ _ _ _ _ _[_1__ _ _ _ ' S '0 0

___________ __ _____ 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS 3/7

m. 0 100.00 TOTALS FINAL GRADE _________________%

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

EPPL5CEU575~5EGUATURE~~~~~~~~~~~~~~

a .

5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 2 QUESTION 5.01 (1.00)

The xenon peak that occurs after a reactor trip is higher following a 100% power equilibrium xenon condition than a 25% power equilibrium condition because

a. the fission yield for xenon is higher at 100% power.

b. there is more iodine in the core at the time of a trip from 100% power.

c. there are more thermal neutrons in the core at 100% power.

d. there are more delayed neutrons in the core at 100% power.

QUESTION 5.02 (1.00)

The effective delayed neutron fraction decreases over core life partly because

c. the number of delayed neutron precursor groups increase.

b.-the fission yield for Pu-239 increases.

c. of a buildup of Pu-239 in the core.

d. soluble boron is removed from the core.

-QUESTION 5.03 (1.00)

Which of the following statememts describes the relationship between integral and differential rod worth?

a. Integral rod worth (at any location) is the slope of the differential rod worth curve at that position.

b. Inte3ral rod worth (at any location) is the total area under the differential rod worth curve from the end of the rod to that location.

c. Integral rod worth (at any location) is the square of the differential rod worth at that location.

d. There is no relationship between integral and differential rod worth.

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

5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE- 3 QUESTION 5.04 (1.00)

The 2200 degrees F maximum peak cladding t.emperature limit is used because

o. it is 500 degrees F below the fuel cladding meltins Point.

b. any clad temperature higher than this correlates to a fuel center line temperature at the fuel's meltin3 Point.

c. a ircalloy-water reaction is accelerated at temperatures above 2200 F.

d. the thermal conductivity of zircalloy decreases at temperatures above 2200F causins an unacceptably sharp rise in the fuel centerline temperature.

QUESTION 5.05 (1.00)

The most serious problem with reaching the critical heat flux is caused by

a. the poor thermal conductivity of steam since steam blanketin3 occurs on the fuel cladding.

b. the blockage of flow through the core when steam bubble formation becomes si3nificant.

c. the displacement of boron from the core as steam bubble formation becomes significant.

d. the high pressure surges in the Reactor Coolant System caused by steam bubble formation. .

(xxxxx CATEGORY 05 CONTINUED ON NEXT PAGE xxxxx)

5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 4 GUESTION 5.06 (1.00)

The Reector Protection System would become unreliable for DNB protection from the OT delta T trip if voids were allowed to form in the Reactor Coolant System because

a. the heat transfer coefficient of the cladding is reduced significantly.

b. the specific heat capacity of the reactor coolant inventory changes when voiding occurs and is not measurable by the RTDs.

c. the critical point of water is reached and is not measurable by the RTDs.

d.. entropy becomes more limiting than enthalpy, which is not within the design considerations of the Reactor Protectior System.

QUESTION 5.07 (2.00)

The reactor is operatins at 30% power when one RCP trips. Assumins no reactor trip or turbine load chanse occur, indicate whether the following parameters will INCREASE, DECREASE, or REMAIN THE SAME.

a. Flow in operatin3 reactor coolant loops (0.5)

b. Core delta T (0.5)

c. Reactor vessel delta P (0.5)

d. Operatins loop steam senerator pressure (0.5)

DUESTION 5.08 (2.00)

A motor driven centrifu3a1 pump is operating at rated flow when the discharge valve is throttled shut. How are the following Parameters affected by this action? (Increase, Decrease, or Remain Unchanged)

a. Motor current

b. Discharse pressure of the pump

c. NPSH available

d. NPSH required

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

r

5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 5 DUESTION 5.09 (3.00)

c. How do each of the followins Parameters change (increase, decrease or no change) if one main steam isolation valve closes with the plant at 50% load. Assume all controls are in automatic and that no trip occurs.

1. Affected loop steam senerator level (INITIAL change only)

2. Affected loop steam senerator pressure

3. Affected loop cold les temperature

4. Unaffected loop steam senerator level (INITIAL change only)

5. Unaffected loop steam senerator pressure

6. Unaffected loop cold les temperature (3.0)

QUESTION 5.10 ( .50)

TRUE or FALSE?

For similar heat exchangers operating under the same inlet. temperatures end flow rates, a counterflow heat exchanser will transfer more heat than a parallel flow heat exchanser.

QUESTION 5.11 (1.50)

List the three bases for the required rod insertion limits.

QUESTION 5.12 (1.00)

If you were given a los of data that included containment dew point .

temperature, wet bulb temperature, and dry bulb temperature, in what order, from the highest to lowest temperature, would you find them?

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

i

5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 6 GUESTION 5.13 (3.00)

Compare the response of the following at BOL and EOL to a dropped rod at full power. (Assume all rods out, the dropped rod has the same worth at BOL and EOL, and the reactor does not trip.)

o. Initial power drop. (Greater or Less) Explain.

b. Rate of power chanSe. (Faster or Slower) Explain.

c. Final steady state Tav3 (Higher or Lower) Explain.

QUESTION 5.14 (3.00)

Durin3 a aeactor startup, will the actual critical position be HIGHER, LOWER or the SAME AS the estimated critical position calculated before the followins chanses? EXPLAIN your choices. (Consider each change separately).

a. The operator starts warmin3 the main turbine prior to reaching criticality. (1.0)

b. Actual boron concentration was 30 ppm hi3her'than the value used for figuring the ECP. (1.0)

c. Startup was delayed 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> beyond the ECP time; a shutdown time of 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> was used for the ECP. (1.0)

GUESTION 5.15 (1.00)

Why does the rod insertion limits increase as reactor power increases?

QUESTION 5.16 (1.00)

Explain how xenon can delay a reactor startup for a day or more near the end of core life.

(xxxxx CATEGORY 05 CONTINUED ON NEXT PAGE xxxxx)

5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 7 QUESTION 5 17 (1.00)

(a) Explain why other installed neutron sources in addition to the antimony beryllium source must sometimes be used in the reactor and (b) SiVe tWo examples.

QUESTION 5.18 (1.00)

Explain how the CVCS cation demineralizer removes suspended and dissolved impurities.

QUESTION 5.19 (1.00)

When an AC Senerator is said to have a leading or la33 i ng power factor, what is the ' leading or lagging

• in reference to?

QUESTION -5.20 (1.00)

If reactor power increases from 1000 cps to 5000 cps in 30 seconds, what is the SUR?

QUESTION 5.21 (1.00)

A soberitical reactor has a neutron source strength of 20 cps and a source ranSe count rate of 200 cps. What is the reactor's keff? (Assume a detector efficiency of 1.)

~

QUESTION 5.22 (1.00)

The reactor is at 80% power with a core delta T of 48 desress F and a mass flow rate of 100% when a station blackout occurs. Natural circulation is established and core delta T goes to 40 destess F. If decay heat is 2% of of full power, what is the mass flow rate (% of full flow)? Assume specific heat remains constant.

(xxxxx END OF CATEGORY 05 xxxxx)

.~ .

6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 8 QUESTION 6.01 (3.00)

O. What protection signals will generate safety injection actuation for a main steam line rupture outside of the CV upstream of the MSIV's? Setpoints and logic NOT required.

b. What are the TWO major functions performed by the Safety Injection System to miti3 ate the effects of a main steam line rupture?

GUESTION 6.02 (3.00)

a. State FOUR locations that Service Water can be cross-connected.

b. How is the Service Water system affected by an extended loss of power to.the E-2 bus with a SI signal present?

DUESTION 6.03 (2.00)

Indicate WHETHER or NOT each of the following statements concernin3 the Low Temperature Overpressure Protection Subsystem (LTOPS) are correct.

a. Wide range pressure and auctioneered low narrow range temperature are inputs to the control circuitry.

b. If the LTOPS requires the PORV's to open and the isolation valves are shut, the isolation valves automatically open.

c. .The purpose of the LTOPS is to protect the RCS from pressurized thermal shock.

d. In mode 1, a temperature input fails low and the LTOPS is armed the PORV's will fail open.

e r> N . W w facot: -t s .3 c..wr. r % or 7.w eA

(**x'<a CATEGORY 06 CONTINUED ON NEXT PAGE *****)

6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 9 QUESTION 6.04 (2.00)

The following concern the Reactor Vessel Level Indicatin3 System (RVLIS):

c. Where are the RVLIS strap on RTD's installed?

b. What is the purpose / reason for the strap on RTD's?

c. Which input signal is used to compensate the measured reactor vessel D/P when the coolant is saturated?

d. If the instrument loop RCP is not runnin3 the upper range will read approximately ____%, assume the other RCP's are running.

QUESTION 6.05 (1.50)

a. What TWO conditi'ans will trip the Motor Driven Auxiliary Feedwater Pumps? (1.0)

b. TRUE or FALSE?

The motor operated discharge valves receive an open signal and S/G blowdown isolation valves receive a close signal when the Steam Driven AFW pump automatically starts. (0.5)

DUESTION 6.06 (2.00)

Indicate how RCS pressure initially responds (increase, decrease, or no affect) for each of the following actions dith the RCS solid on RHR, consider each separately.

a. Stopping the RHR pump.

b. Start a RCP with the associated S/G temperature 50 F less than RCS temperature.

c. Opening HCV-142.

d. Closin3 PCV-145.

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

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. _ _ _ _ _ ~ . _ _ . , _ , _ _ , __ _

6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 10 QUESTION 6.07 (1.50)

Indicate whether the followin3 statements are TRUE or FALSE concerning the Emergency Diesel Generator.

c. The main lube oil pump and cooling water pump are driven by the diesel's upper crankshaft.

b. When the diesel receives a manual start signale the si3nal will also start the diesel's ventilation equipment.

.c. Three controls on the diesel speed governor are synchronizer, speed droop and load limit.

QUESTION 6.08 (1.00)

Which of the following signals will block AUTOMATIC rod withdrawal but not MANUAL rod withdrawal?

. a. A Power Range channel above 103%.

b. A 2/3 overtemperature Delta T above setpoint (but less than trip setpoint).

c. An Intermediate Range channel above 20%

d. A dropped rod, rod bottom signal from rod position indication.

QUESTION 6.09 (1.00)

Which one of the followine vid NOT be an indication or response associated with removing instrument power fuses on power range NI 41 during normal full e operation?

c. Turbine runback

b. Channel deviation alarm

c. 103% tod stop

d. A full negative indication on the Delta flux meter (on RTGB for NI 41)

(xxxxx CATEGORY 06 CONTINUED ON NEXT PAGE ***xx) i

6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 11 QUESTION 6.10 (2.00)

Indicate whether each of the following statements apply to OT Delta-T only, OP Delta-T only, or BOTH, (OT Delta-T and OP Delta-T) protection instruments.

1. Protects the core from DNB.

2. Backup for the high neutron flux trip.-

3. Circuitry dynamically compensates for piping delays to the loop temperature detectors.

4. Requires RCS pressure within the high and low reactor trip setpoints in order to be valid.

QUESTION 6.11 (1.00)

If power is at 100 % and the Steam Dump is in Tavs mode when the first stage pressure channel 447 fails low, which of the following describes the response?

a. All 5 condenser dump valves and 3 steam generator PORV's arm.

b. All 5 condenser dump valves arm and trip open.

c. All 5 condenser dump valves arm.

d. There will be no effects on the Steam Dump system because there has not been a load rejection nor trip.

QUESTION 6.12 (1.00)

Which of the following malfunctions would cause a pressurizer level indication of 0%?

a. dp cell diaphragm rupture

b. Reference les rupture

c. Impulse line rupture

d. Equalizing valve leaka3e (xxxxx CATEGORY 06 CONTINUED ON NEXT PAGE xxxxx)

6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 12 QUESTION 6.13 (2.00)

For each " CASE' below select the ' CONDITION' of RCS temperature control that most correctly describes the final plant status WITHOUT operator l cetion. Consider each case separately and assume initial normal system lineup for each case. (For example, 5. e.) (NOTE: CONDITIONS may be used core than once or not at all.)

CASE:

1. Steam pressure setpoint is reduced by 92 psi while at stable plant conditions awaiting reactor startup.

2. The Steam Dump selector switch is placed in 'off' while at 5%

reactor power awaitin3 turbine startup.

3. Train B reactor trip breaker fails to open upon a trip from 78% power. NOTE: Train A breaker opens.

4. Reactor power 20% and main turbine trips.

CONDITION:

a. Secondary pressure rises to atmospheric relief valve setpoint, maintainin3 tav3 '560-F.

b. Tav3 decreases to approximately low Tav3 setpoint.

c. Steam dump controlling by load rejection controller.

d. Steam dump controlling by trip controller.

QUESTION 6.14 (1.00) l What does the Rotation Interlock Bypass Switch on the Manipulator Crane Control Console permit?

00ESTION 6.15 (1.00)

What is the normal source of water for the turbine exhaust sprays?

GUESTION 6.16 (1.00)

What are TWO indications on the RTGB that would alert the operator that i en AFW pump control switch was inadvertantly switched to local control?

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

6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 13 QUESTION 6.17 (2.00)

o. What design features minimize the affects of an external severance of the. Spent Fuel Pool Coolin3 Pump:

1. Suction line? (0.5)

2. Discharge line? (0.5) b._ State the flow path used to drain the refuelin3 cavity lower section to the RWST. Include major components in the flowpath. (1.0)

QUESTION 6.18 (2.00)

o. What are THREE of the functions / purposes of the Component Coolins Water (CCW) Surge Tank? (1.0)

b. What are TWO components / devices for indication and/or control of radioactive material in the CCW System? Include location of the component / device in your answer. (1.0)

(xxxxx END OF CATEGORY 06 xxxxx)

+

7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 14

~~~~RkU56L U56AL U TR L'~~~~~~~~~~~~~~~~~~~~~~~

QUESTION 7.01 (1.00)

Select the malfunction which DOES NOT list an orderly reactor shutdown OR a reactor trip as an immediate action step, acording to AOP-01, Malfunction of Reactor-Control System procedure.

c. More than one dropped rod.

b. Failure of a control bank to move in AUTO and MANUAL.

c. More than 1 misali 3 ned control rod.

d. Continuous insertion of a control bank in AUTO and MANUAL.

QUESTION 7.02 (1.00)

If a loss of condenser vacuum is impending, with 23' Hs and decreasin3' which of the following is NOT an immediate operator action accordin3 to AOP-012, Partial Loss of Condenser Vacuum procedure?

a. Reduce Turbine Generator load.

b. Verify the standby vacuum pump running.

c. Start the standby circulatins Pump.

d. Verify the Steam Generator levels not decreasing.

QUESTION 7.03 (2.00)

The following concern EPP-5, Natural Circulation Cooldown procedure

a. When is switchover of AFW pump supply to alternate water sources required?

b. While maintainin3 a cooldown rate of 25-F/hr, what specific indication of temperature is utilized?

c. Why is RCS subcooling >190-F required during RCS cooldown 'depressuriza-tion?

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

7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 15

~~~~~~~~~~~~~~~~~~~~~~~~

~~~~R 565 L 65CdL"C6UTR L QUESTION 7.04 (1.00)

If the Plant Vent monitor (R-14) alarms, one of the required actions is to chift R-11 and R-12 to the plant vent. What must be done prior to shifting R-11 and R-12 according to AOP-005, Radiation Monitoring System procedure?

a. Ensure FCV-1436A is closed from the local panel.

b. Evacuate the containment.

c. Perform a source check on R-11 and R-12.

d. Verify R-15 is operating properly.

QUESTION 7.05 (1.00) 7 E tE NEAT PACE erformins equipment status checks on manual LOCKED valves, which one escribes how their position is verified?

of c.

the fo1mwinJ_A' N _

Verifying the lock is'ir,-p. lace and securely locked.

b. Verifying local valve position fWdicat_ ion is indicating the required position.

~~.,

c. Operating the valve in the open direction. N

d. Operating the valve in the closed direction.

x ~. '

OUESTION 7.06 (1.00)

While performins steps in EPP-1, Loss of All AC Power, a SI signal may be generated. What must be done and why?

a. No action is necessary for the SI signal as it has no effect,

b. Reset the SI to permit manual loading of equipment on the emergency buses after power is restored.

c. Reset the SI to permit the D/G's to energize the emer3ency buses.

d. Place SI in test to prevent an overpressure transient on the RCS.

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

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, Wh:ch cp +k<_ h \\cwog is. -Ws re ascN gr

.47s C AWTi DN ?

a. Prese A cech.3 dewes Rcs +c bp ,wboss a4 wbc.b pressarrted Ae. m( .s b o c.k 13 cu ccnceca.

b, Prece d Tafe b en e-Y csc e umw\ der n'kro ge n i.b % BC_s.

l ess c . T c; m i n i a t e. he RC-6 iM edtory d oe. 4o c.onktuc3;on,

d. Tc >-;ni.-a te +be_ chan e.<_. og I os. n3

, gresvw, u e e \ue \ a nd ras v \% d rewbor ec sse I upe ,- hu.d oc i ch- ,

7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 16 RADIOLOGICAL CONTROL QUESTION 7.07 (1.00)

During a reactor startup, if criticality is attained above the control rod low insertion limit, but below the estimated critical position (ECP) lower band, which one of the following actions must be taken according to GP-003, Normal Plant Startup from Hot Shutdown to Critical procedure?

a. Insert rods to low insertion limit and recalculate ECP.

b. Notify Reactor engineering personnel, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and continue normal startup operations.

c. Reinsert all control banks to the bottom of the core, evaluate condition and recalculate ECP.

d. No special action is required; continue normal startup operations.

QUESTION 7.08 ( .50)

Steam generator blowdown is a potential releases of tritium to the enviornment. TRUE or FALSE?

OUESTION 7.09 ( .50)

Only one tank / system containing radioactive liquid waste may be released at a time. TRUE or FALSE?

QUESTION 7.10 (1.00)

TRUE or FALSE?

a. If while implementing a red Functional Restoration Procedure (FRP), a hi3h er Priority red condition occurs, then the operator should leave the lower priority red FRP and immediately implement the higher priority red FRP.

b. In usinS the End Path Procedures (EPP's), the ri3ht hand column of actions is to be used ONLY if the associated action in the left hand column does not result in the response specified.

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

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7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 17

~~~~~~~~~~~~~~~~~~~~~~~~

~~~~R565 L6556AL"E UTRUL QUESTION 7.11 (1.50)

From the list of indications / characteristics in Column B below, select those which are characteristics / indications for each of the accidents in Column A. Note that indications / characteristics may be used more than once (for example, 4. f'3,h, S. fri).

Column A Column B

1. Large LOCA a. Low S/G pressure

2. SGTR b. Low PZR pressure

3. Steam break in containment. c. Low PZR level

d. High CV pressure

e. HiSh PZR level GUESTION 7.12 (1.50)

List three different conditions that require an operator to emergency borate the Reactor Coolant System in accordance with AOP-002, Emergency

'Boration procedure.

QUESTION 7.13 (1.00)

What is the maximum allowable time a Reactor Coolant Pump can continue to operate after Component Cooling Water flow is lost to it?

QUESTION 7.14 (1.00)

Steam line pressure must be within _____ psis of steam header pressure prior to opening MSIVs.

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

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7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 18

~ ~~~~~~~~~~~~~~~~~~~~~~~~

~~~~Rd65UL66YUdl CUNTRUL QUESTION 7.15 (1.00)

Complete the following statement concerning EPP-9, Transfer to Cold Les Recirculation.

The maximum time between RHR flow termination during the injection phase and reinitiation of flow in recirculation phase must be less than ___(a) ___ minutes to prevent ___(b) ___ damage.

QUESTION 7.16 (1.00)

What is the maximum time that a temporary chan3e may remain in effect cccording to AP-004, Development, Review and Approval of Procedures, Revisions, and Temporary Chan3e5 Procedure?

OUESTION 7.17 (2.00)

0. If an individual has already received a whole body exposure of 1000 mrem this quarter, what would be the maximum additional exposure to skin that is allowed without exceeding 10 CFR 20 limits? (0.5)

b. What are the H.B. Robinson administrative whole body limits according to DP-014, Quarterly Dose Limit Extension Authorization procedure for the following: (1.5)

1. No NRC Form 4?

2. With NRC Form 4?

3. With NRC Form 4 and approved exposure extension?

OUESTION 7.18 (1.00)

During a plant startup to 100% power, how many MWe should be available before transferring the ti, 2, and 4 4160V Busses from the Startup Transformer to the Unit Auxiliary Transformer?

OUESTION 7.19 (1.00)

If there is a fuel assembly in the manipulator crane when a decreasing refueling cavity water level is noted, what two locations are acceptable for storage of the latched fuel assembly?

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

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7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 19

~ ~~~~~~~~~~~~~~~~~~~~~~~~

~~~~ Rd65UE65EEAL CUNTRUL QUESTION 7.20 (1.00)

If the plant was shutdown for greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, at what two power levels is it required to have a Power Range Calorimetric performed during the ensuins startup and power increase to 100% power?

QUESTION 7.21 (2.00)

The followins concern Foldout A of the EPP's

a. What is the RCP trip criteria?

b. What is the SI actuation criteria?

GUESTION 7.22 (3.50)

a. How is a reactor trip verified according to EPP-1, Loss of all AC power procedure? (1.0)

b. What operator actions are required if a manual trip of the reactor fails from the RTGB, according to PATH-1? (FIVE actions required) (2.5)

QUESTION 7.23 (1.50)

List three parameters that would require monitorin3 in order to determine if a Reactor Coolant Pump should be stopped due to a loss of seal injection.

QUESTION 7.24 (1.00)

What is the reason for not exceeding 40% steam flow indication during a cooldown according to OP-001, Reactor Control and Protection System?

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

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8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 20 QUESTION 8.01 (1.00)

Per 10CFR50, Appendix A, each line that connects directly to containment atmosphere and penetrates containment shall have containment isolation valves. Which of the following will NOT meet the requirements of 10CFR50?

a. One manual locked closed isolation valve inside and one manual locked closed isolation valve outside.

b. One automatic isolation valve inside and one check valve outside,

c. One check valve inside and one automatic isolation valve outside.

d. One automatic isolation valve inside and one locked closed manual valve outside.

QUESTION 8.02 (1.00)

The process of determining an instrument's accuracy by visually comparing the indication to other independent instrument channels measurin3 the same parameter is defined in Technical Specifications as a*

o. Channel Calibration

b. Channel Check

c. Channel Functional Test

d. Channel Verification QUESTION 8.03 (1.00)

Which of the followins is the basis for the high pressurizer water level reactor trip?

a. Prevents solid operations while the reactor is critical.

b. Prevents exceeding containment design pressure in event of a LOCA with all RCS fluid flashing to steam.

c. Prevents loss of pressure control due to spray nozzle bein3 submerged.

d. Protects the Pr ussuri=er safety valves against water relief.

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

8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 21 QUESTION 8.04 (1.00)

If a proposed temporary chan3e to an operating procedure does not violate the intended function of the procedure, the change can be_ implemented on a temporary basis following approval by which of the following?

o. Any two members of the Plant or C & A Management Staff.

b. Any two members of the Plant or C & A Management Etaff, at least one which holds an SRO license.

c. Any member of the Plant or C & A Management Staff who holds an SRO license.

d. The Operating Supervisor - Unit 2 QUESTION 8.05 (1.00)

When performing equipment status checks on manual LOCKED valvese which of the following describes how their position is verified?

a. Verifying the lock is in place and securely locked.

b. Verifying local valve position indication is indicating the required position.

c. Operating the valve in the open direction.

d. Operatin3 the valve in the closed direction.

QUESTION 8.06 (1.00)

Redundant RTGB indicators which require operator attention are cheched once a shift. This check is made by ccmparing the highest and lowest channels of redundant indicators for the same parameter on the same scale. Which of the followins is the maximum acceptable deviation?

a. 4% of the full range of the indicator's movement.

b. 4% of the highest readin3 indicator.

c. 4% of the lowest reading monitor.

d. 4% of the averase of the indicator's readin3s.

(**x*x CATEGORY 00 CONTINUED ON NEXT PAGE xxxxx)

__n-_____--________----_--___-----_____--__---__---_-__---_--_--_-_____--_

8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 22 QUESTION 8.07 (1.00)

Concerning the shift complement for hot at power operations, which of the following license requirements is correct?

c. 1 RO, 1 SRO

b. 1 RO, 2 SRO

c. 2 RO, 1 SRO

d. 2 RO, 2 SRO QUESTION 8.08 (1.50)

Answer TRUE or FALSE to the following.

a. If the RCS temperature is at 300 degrees F and the overpressure protection system is INOPERABLE, an acceptable action is to heat up the RCS to above 350 degrees F where the overpressure pro-tection system is not required.

b. Over the temperature range from cold shutdown to hot opersting conditions, the maximum allowable heatup rate of the RCS is 100 degrees F per hour.

c. Above 50% power, the Technical Specifications do NOT allow opera-tion with a positive Moderator Temperature Coefficient.

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

8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 23 QUESTION 8.09 (3.00)

For the following indicate whether the responsibilty specifically cpplies to the SHIFT FOREMAN (SF), SENIOR CONTROL OPERATOR (SCO),

or BOTH.

o. Assume the duties of the Fire Brigade Team Leader durin3 fire emergencies.

b. Ensure tests assigned to shift are completed.

c. Update the status board at least once per shift.

d. Monitor records and evaluate data obtained from installed instrv-mentation and relay information to the load dispatcher.

o. Initiate requests for maintenance or repairs either directly or to the Maintenance Group or by the use of Work Request and Authorization forms, as appropriate.

f. Initiate requests to revise existing operating procedures or develop new procedures.

QUESTION 8.10 (1.00)

Fill in the blanks for the following statements concernin3 Locked High Radiation Areas (LHRA).

a. Each High Radiation Area with radiation intensity greater than

_______ mrem /hr shall be locked with a Controlled Key.

b. Access to Locked High Radiation Areas is controlled by the QUESTION 8.11 (1.00)

The minimum site manning requirements of the Plant Fire Brigade is at least _______ members, e::cluding _______ member s of the minimum shift crew necessary for safe shutdown.

/

QUESTION 8.12 (1.50)

According to the Technical Specifications, what THREE conditions would require that a control rod be declared inoperable?

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

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8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 24 QUESTION 8.13 (1.00)

When a system is determined to be inoperable solely because its normal power supply is inoperable, it may be considered operable for the pur-pose of satisfyin3 the requirement of its applicable LCO provided two conditions are met. List these TWO conditions.

QUESTION 8 14 (1.50)

With the reactor critical with natural circulation flow, what are the POWER, PRESSURE, and TEMPERATURE Technical Specification Safety Limits?

QUESTION 8.15 (1.50)

What are the Technical Specification limits for UNIDENTIFIED, IDENTIFIED, and PRIMARY TO SECONDARY leakage?

QUESTION 8.16 (1.50)

How many of the following will provide sufficient cooling to reduce containment pressure in the event of a Design Basis Accident?

a. Minimum number of containment fan coolers only.

b. Minimum number of containment spray pumps only.

c. Minimum combination of containment fan coolers and spray pumps.

QUESTION 8.17 (1.00)

a. How many operable encore channels must indicate that the axial flux difference is outside the band before the indicated axial flux dif-ference is considered to be outside its limit?

b. If the axial flux difference alarms are out of service, how often MUST the axial flux difference be logged during the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />?

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

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-8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 25 f

QUESTION 8.18 (2.00)

Other than reactor trip and 1 and 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> NRC notifications, list FIVE eituations that require the Shift Foreman to make prompt notification to the Operating Supervisor. ><

QUESTION 8.19 (1.00) (

An RCS cooldown using one train of RHR and one RCP is in progress.

At 300 de3rees, the operatin3 RHR pump trips and can NOT be restarted.

According to the Technical Specifications, what action, if.any, is required?

QUESTION 8.20 (1.00)

What is the maximum allowable extension times for Technical Specificatf ori curveillance intervals. '

QUESTION 8.21 (1 00)

• A#6*iM NA 84 ' /2 '*^ '"8 W

o. Who is responsible for classifying emergencies in accordance witre the Emer3ency Action Levels?

b. If the individual in part a is unavialable, who assumes this responsibility?

DUESTION 8.22 (1.50)

c. When is a Procedure Deviation allowed? (1.0)

b. Who must approve a Procedure Deviation prior to performing it? ~ (0.5)

GUESTION 8.23 (1.00)

How does an individual know that he is using the latest revision of a procedure? ,

i

(***** CATEGORY 00 CONTINUED ON NEXT PAGE *****) i

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8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 26 4

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.GUESTION 8.24 (1.00)

e. How often are control room recorders verified that they are marking clearly and the timin3 is correct?

b. How is this verification documented?

4 h

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

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

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P = Pressure Q = sc,(Tout-Iin) 0 = UA (T ,,.T,g,) 0 = s(h3.h2 )

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delta K = (K,gr-1)/K,gg CRg(1.K,ggg) = CR 2 II*Keff2) CR = 5/(1.K ,gg)

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P* ** liq uid wepo, i.evid ,,,,,

e r *: 'e as ** *e *: *s *e 0 088 54 0 0160 3306 0 00 1075 8 1015.8 0 0000 2 1877 2 1877 32 0 09995 0 0160: 2947 30: 1014 1 1077.1 0 0061 2.l709 :1770 35 0 12170 0 0160 2444 8 05 1071.3 1079.3 0 016: 2.1435 2.1597 40 0 14?5: 0 0160 2036 4 13 0o 1068 4 1081.5 0 026: 'll67 2.1429 45 50 017bil 0 01603 17032 18 J7 1065 6 108)7 00%I 2 0903 2 1264 1088 0 0 0555 2.039) 2.0946 60 0:%) 0 01604 120e 7 28 06 1059 9 1 990: 2.0647 O M)I Or.i606 867.9 38 04 1054.3 1092.3 0 0745 70 001608 63) 1 48 02 1048 6 1096 6 0.093: I9428 20A0 to 0.5069 18972 2.0087 90 0 6962 0 01610 4680 57 99 1042 9 1100.9 01115 350 4 67.97 1037.2 1105: 01295 l.8531 l.9826 100 0 9492 0 01613 001617 265 4 77.94 10316 1109.5 0 1417 1.8106 I9577 110 1.274B 203 27 87.92 10:5.8 1813.7 0 1645 1.7694 1.93)9 120 16924 0 01620 0 01625 157.34 97.90 1020 0 1117.9 0 1816 1.7290 l.9112 130 2 22:5 0 01629 123 01 107 39 1014l 11:2.0 0 1984 16910 1.8894 140 2 8886 3 718 0 01634 91 0' 117.89 1008.2 1126.1 0.2149 l.6!)7 1.8685 150 77.29 127.89 1002.3 1830.2 01311 1.6174 1.8485 160 4 741 0 01639 62 0e 137.90 996.3 1834 2 0.2472 1.582: 1.8293 570 5992 0 01645 50.23 147.92 990.: 1I38 1 0 2630 1.5480 18109 180 7.510 0 01651 0 01657 40 % 157.95 984I 1142 0 0 2785 1.5147 1.79):

190 9.339 0 0166) 33.64 167.99 977.9 1145 9 0.2938 1.4824 1.742 200 11.526 0 01670 27.82 178 05 971.6 1149 7 0.3090 14508 1.7598 210 14 123 0 01672 26 to 180 07 970.3 1850 4 0.3120 1.4446 l.7566 212 14 69e 0 01677 23.15 188 13 %5.2 I1534 0 3239 I4201 1.7440 220 17 186 0 01684 19 382 198 23 958 8 1157.0 0.3387 1.3901 l.7288 230 20 780 16.323 208.34 952.2 1860 5 0.3531 1.3609 1.7140 240 24 % 9 0 01692 13 821 216 48 945.5 1164 0 0 M75 1.3323 1.6998 250 29 825 0 01700 0.01709 11.763 228 64 9 38.7 1167.3 0.3817 1.304) 1.6840 260 35 429 10 06n 2 M 84 931.8 1870.6 0.3958 1.2769 14727 270 4185b 0 01717 8 645 249.06 9247 1173 8 0 4096 1.2501 1.6597 280 49.203 0.01726 7.461 259.31 917.5 1176.8 0 4234 1.2238 1.6472 290 57.5% 0.01735 6 466 269.59 910 1 1179 7 0 4169 1.1980 1.6350 300 67.013 001745 279 92 902.6 1182.5 0 4504 1.1727 1.6231 310 77 68 001755 5.626 l 4 914 290 28 894 9 1885.2 0 4637 1.1478 1.6115 320 89 66 0 01765 300 68 887 0 1187 7 0449 1.1233 1600 330 103 06 00174 4 307 340 118 01 0 01787 3 788 311.13 879.0 11901 0 4900 1 099: 1.5891

a .

6*

TABLE D lb Properties of Dr3 Satursted SteamIcvarmurd4 1 Temperature o, spect .olume E mh ete. E w ee.

Temt "'"

er P'" su so sei E .r se sei E..e sr 1.e.,4 . .por I. ,,, . .no, ,,,,,, ,,,,,

e r ., ., n. A. *, e, ,, s, 350 134 63 0 0i?99 3 34: 3:e e3 s?0 ? 119:) 0 50:9 1.0'54 1.578) 360 153 04 0 01618 2 95* 33: 18 852 : l194 4 0 5156 10519 I M'7

• 370 17) 37 0Oll:) 6:5 34 : 99 85) 5 11963 0 5286 10:8' I3573 380 195 77 0 Ol6k  : 335 353 45 644 6 1196 1 0 5413 10059 i M71 390 220 37 0 0lb50 2 06 % 364 17 8354 1899 6 0 5539 0 983 1.5371 400 247.31 001864 I8633 374 9' B26 0 1201 0 0SM4 0 9006 1527:

410 276 75 0 01876 1 6T00 385 6.1 816 ) I'02 1 0 5788 0 9386 1.5174

. 420 306 8) 0 01894 1.5M10 39e 77 80e 3 12031 0 5912 0 91 % 1.5078 430 343 72 0 01910 1.349(v 407 79; 79e 0 12038 0 6035 0 8947 1496 440 381.59 0 01926 12171 418 90 765 4 1204 3 0 6156 08730 e 4867 450 4:26 0 0194 1099) 4Mi 774 5 1204 6 0 6:80 0 851) i4793 460 466 9 0 0196 0 9944 441 4 76): 1204 6 0 640 0898 14700 470 514 7 0 0198 0 9009 45: 8 751.5 12043 0 65:3 0 8063 ! l 4606 440 5661 00 00 08l*: 464 4 739 4 1203 7 0 6645 0 7868 e i 4513 490 6:14 0 020 0.*4:3 476 0 726 8 1:02 > 06'66 0 7653 1 4419 500 680 6 0 0:04 0 6i49 46* 6 'l39 l 'O l ' 0 668* 0 7438 I43:5 520 812 4 0 0:09 0 5594 511.9 66e 4 Il9b : 0 7:30 0 7006 1.41 %

540 962.5 0 0:15 0 4649 536 6 6%6 1193 2 07374 06%8 1.3942 560 1133 1 0 0:21 0 M66  %:: 6:4 : 1166 4 0 7621 0 61:1 1.374: ,

580 1325 8 0 02:6 0 3217 566 9 566 4 1177.3 0 7872 0 M59 1.353 600 1542 9 00:3e 02666 610 0 546.5 1165 5 0 8131 0 5176 1.3307 6M 1766 6 00:4' 02201 646 7 503 6 1150 3 0 8396 0 4664 1.306 640 2059 7 0 0260 0 1798 674 6 4520 Ii30 5 0 8679 0di10 1.2789 660 2M54 00:76 01442 7140 390 1104 4 0 8987 0.3415 1.24?:

680 27061 0 0305 0.1115 757.3 309 9 1061.2 0 9351 0 2719 120*l 100 3093 7 0 0369 0 0761 823.3 172.1 90 4 0 9905 0 1484 1.1389 705 4 320e: 0 0503 0 0503 902 7 0 902 i 10580 0 1.0580

e b*

TABLE D l. '

Propernes of Dr) Satur.Hal $1 cam

• Prenure semA

%, voi.,m E nimatr> Enitory pren , h*F

p. , i Sai Sai $st Sai f.eved espo. I ev d Eier ,,,,

Sai E=ar Set _

g,,, ,,

a a e, 5, 4, 4, 4, s, a, s, 10 101.74 0 01614 333 6 69 70 1036.3 1106.0 0 1326 1.8456 1.9782 20 126 06 0 01623 173 73 93 99 1022 2 1116.2 0.1749 1.7451 l.9300 30 141 db 0 01630 118 11 109 37 1013.2 1122 6 0.2008 l.6855 l.8463 40 152 97 0 01636 90 63 120se 10004 1827.3 0.2198 1.6427 1.0625 50 16224 0 01640 13.52 130 13 1001.0 1131.1 0.2347 2 6094 1.6441 60 170 06 0 01645 61.98 137 % 996 2 1134 2 0.2472 1.5820 1.8292 7.0 176 85 0 01649 53 64 144 76 992.I 11 % 9 02581 l.5586 l.8161 80 182 86 0 01653 47.34 ISO 79 986 5 1839 3 0 2674 1.5383 18051 90 188.26 0 016 % 42 40 1 % 22 985 2 1141 4 0.2759 1.5203 1.7962 10 193 21 0 01659 38 42 I61.17 9821 1143.3 0.2835 1.5041 1.7876 14 696 212 00 0 016* 26 80 180 07 970 3 1150 4 0 3120 1.4446 1.7h6 IS 213 03 0.01672 26 2<, 161 Il 969.7 l150 8 0.3135 1.4415 1.7549 20 227.96 0 01683 20 089 1 % 16 960l l156 3 0.3356 1.3962 1.7319 25 240 07 0 01692 16 30) 208 42 952I l160 6 0.3533 1.3606 1.7139 30 250 33 0 01701 13 74o 218 82 945.3 1864 1 O M80 1.3313 1.6993 35 259.28 0 01706 11.896 227.91 939.2 1867.1 0 3807 1.3063 1.6470 40 267 25 0 01715 10 498 2M 03 933 7 1169.7 0 3919 1.2844 1.6763 45 274 44 0 01721 9 40i 243.36 928 6 1172 0 0 4019 1.2650 1.6669 50 281.01 0 01727 8 515 250 09 924 0 I l74. I O dil0 1.2474 1.6585 55 28? 07 0 01732 7.787 256 30 919 6 1175 9 0 4193 1.2316 1.65(N 60 29271 0 01736 7.175 262 09 915.5 l177.6 0 4270 1.2168 1.6438 65 297 97 0 01743 6 655 267.50 911 6 II?91 0 4342 1.2032 l.6374 -

70 302 92 0.01748 6 206 27261 907.9 IIS0 6 0 4409 1.1906 1.6315 75 307 to 0 0175) $ 816 277 43 904 5 1181.9 0 4472 1.1787 1.6259 80 312 03 0 01757 5 472 282 02 901.1 l1831 0 4531 1.1676 1.6207 g

85 316.25 0.01761 5.168 286.39 897.8 1884 2 0 4587 1.1571 1.6158 90 320 27 0 08766 48% 290 56 894 7 1185.3 0 4641 1.1471 1.6112 95 324 12 0.0l??0 4 652 294 56 891.7 l186 2 0 4692 1.1376 1.6066 100 321.81 0 0l774 4 432 298 40 8888 l 187.2 0 4740 1.1286 1.6026 110 334 77 001782 4 049 305.66 883.2 1888 9 0 4832 1.1117 1.5946 e.

L*

TABLE D la Properues of Dr) Saturated Sicam econtmad, Prenure Spwrne... Eme.ip tm,op.

o, 7 amp.

press , Sat Sai Sat Sai

• F San Sai topor 14ued b 'E

• epo' lequid II waroe Imved e, 4, 4 4, s, s. s, p # ',

341.25 001789 3 726 31:M 877.9 1190 4 0 4916 1096: 1.5876 120 318 81 872.9 1191 1 0 4995 1.0817 1.5812 D0 347.32 0 01796 3 455 0 0180: 3 :00 3:4 82 868.2 1193 0 0 5069 1 068: 1.5751 140 353 0 150 356 4: 0 01804 3 015 330 51 863 6 1194 1 0 5136 10!M l.5694

834 3359) 859 2 18951 0 5204 1.0436 1.5640 160 3e3 53 001815 348.09 854 9 11 % 0 0 52te 1 03:4 1.5590 170 %8 di 0 018:2 2 675 180 373 06 0 01627 0'53 346 03 850b 11 % 9 0 53:5 1 0217 1.5 54 350 79 846 8 Il97 6 0.5381 1.0816 1.5497 190 377.51 0 01833 2 404 355 % 843 0 1896 4 0 5435 1.0018 1.5453 200 381.79 0 01839 2.286 1.b438 376 00 8:51 1201.1 0.5675 0 9586 1.5263 250 400 95 0 01865 0 01890 1 5433 393 84 809 0 120 8 0.5879 0 92:5 1.5104 300 437.33 409 69 794 2 1203.9 06056 0 8910 14966 350 431.72 001913 1.3260 11613 4:40 780 5 1204.5 0 6214 0 8630 1.48M 400 4M 59 0 0193 437.2 767 4 1204 6 0 6356 0 8378 1.4734 450 456 28 0 0195 1.03:0 467.01 0 0197 0 9:76 M94 755 0 1204 4 0 6487 08 47 1.4634 500 460 8 743.1 1203.9 06608 0 7934 1.4 54:

550 476 94 00199 0 b4:4 0 7734 1.4454

,600_ abll,. 0 0201 _ 07698 4716 73 Lth. 1 '_D.020 I4374 650 494 90 0 0203 0 %8) 481 8 7205 T202.3 068:6 07548 0 6554 491.5 709 7 1201.2 0 69:5 0.7371 1 4296 700 50310 0 0205 4

0 0207 0 609 5008 699.2 1200.0 0 7019 0.7204 142:3 750 510.86 800 518.23 0 0200 0 5681 509.7 688 9 1198 6 07:08 0.7045 1.4153 0 0:10 0 5327 518 3 678 8 1197.1 0.7194 0 6891 14085 850 525.26 00:l 0 500e 526 6 668 8 1195 4 0 7275 0 67M I4020 900 531.98 0 0:14 0 4717 534 6 6591 11931 0.7355 0 660 1.3957 950 53843 0 0:16 O M56 54: 4 649 4 1191.6 0 7430 0 6467 1.3897 1000 SM 61 0 0:20 0 4001 557 4 630 4 1187.7 0 7575 0 6205 1.3780 1100 556 31 0 02 L,DJi9 571.7 60 7 V 83,4 0 7711 0 5956 1.3667 1200 567 22 07640 1.3559 1300 MM7 0.3293 583h '593 :

574 7 l118 6 1173 4 07%3 0 5719 0.5491 1.14 54

• 1400 587.10 0 0:31 0 301 596 7 5%.23 0 0:35 02765 611.6 556 3 1167 9 0 806: 0 5269 1.3351 1500 01878 671.7 463 4 1135.1 08619 0 4230 1.2849 2000 635 82 0 0:57 0 0287 0 1307 730 6 3605 1091 1 0 9126 0 3197 1.232 2500 668 13 11615 0 0346 0 0658 802.5 217.8 1020 3 0 9731 0 1885 3000 695 36 0 0503 90: 7 0 90: 7 1.0580 0 10580 320e.2 705 40 0 0503

Properues of Superhesied Steam

• an. pee.. 7emeerwn. 4

18. Ep .4 i mio aim doo 300 sou 100 8o0 too scoo sion laso laoo

e. 392 6 452 3 512 0 571 4 631.2 690 8 750 4 809 9 849 5 9291 988 7 l107.8 1 &. l130 4 1895 8 1241 7 1288 3 1335f 1383 s 1432.8 1442 7 15335 15852 1637.7 1745.7 (101.74) a. . 2.0512 2.1153 2 1730 2 2233 12.2702 2 3131 2.3542 21921 2 4253 2 4625 2 4952 2.5566

,. . . . 78 16 90 25 102 26 l14 22 126 16 134 10 150 03 161 95 173 87 185 79 197.71 221 4 5 A.. l148 8 1895 0 1241.2 1288 0 1335 4 1383 6 1432 7 14s2 6 .l533 4 1585,1 1637.7 17457 (162.24) s... l.8718 1.9370 1.9942 2 0454 2.0927 21MI 2.1767 2 214m 22509 2.2851 2.3178 ' 2.3792

, , . 3885 45.00 $1.04 57 05 63 03 69 01 74 9s 8u 9% no 92 92 88 98 84 110 77 10 A. 1146 6 1193.9 1240 6 1287.5 13351 1383 4 14325 14 24 154.1 2 15:5 0 1637.6 1745 6 (193.21) s 1.7927 I8595 1.9172 1.9689 2 0160 2.0596 2.1002 21.ta n 2 1744 2.2068 2.2413 2 3028

,. 30 53 34 68 36 78 4286 46 94 51 00 5507 59 13 6) 19 67 25 75 37 14496 &. 1192.8 1239 9 1287.1 1334 8 1343 2 1432 3 14s2 3 1533.1 1554 8 1637.5 17455 (21218)) s. l.8160 1.8743 1.9261 1.9734 2 0170 2 0576 2.0955 2 1319 216e2 2.1989 2.3603

,. 22 36 25 43 28 46 3147 34 47 37 46 40 45 43 44 46 42 49 41 55.37 Jo A. 1891 6 1239.2 1286 6 1334 4 1382 9 1432.1 1482 1 1533 0 15447 1637 4 1745 4 (227.96) s. 1.7808 1.8396 l.8918 l.9392 19829 2 0235 2 0618 2 0973 2.1321 2.1648 2.2263

,. ll 040 12 628 14 168 15 688 17.19s 18 702 20 20 21.70 23 2u 24 69 2748 40 A. 1136 8 12M 5 1284 8 13331 1381.9 1431.3 1481 4 1532 4 1584 1 1637 0 17451 (267.25) S. I6994 17608 I8140 1.8619 l.9058 1.9467 1.9850 2 0212 2.0W 2 0ss) 2.1498

v. 7.259 8.357 9 403 10 427 l1441 12 449 13 452 14 454 15 454 16 451 18 446 60 A. 1881 6 1233 6 1283 0 1331 8 1380 9 1430 5 14s0 8 1531.9 lis t a 16M 6 1744 8 (292.71) s. 14492 1.7135 l.7678 1.8162 1.8605 1.9015 1.9400 1.9762 2 0:00 2 0434 2.1049

e. 6 220 1.020 1 797 8.562 9.322 10 077 10830 11 582 12 332 13.830 to A. 12307 12811 1330$ 1379 9 1429.7 1480 1 1531.3 15N14 16M 2 1744 5 (312.03) s. l.6798 1.7346 1.78 M l.8281 18694 1.9079 8.9442 1.97x7 2.0115 2.0731

e. 4 937 5.589 6 218 6 835 7.446 8 052 86% 9.259 9.860 11.060 100 A. . 1227 6 12791 13291 1378 9 1428 9 1479.5 1530 8 1582.9 1635.7 1744 2 (327.81) s. l.6518 1.7085 1.7581 1.8029 1844) 1.8829 1.9193 1.9538 1.9867 2.0444

,. 4.081 46% 5.165 5483 5195 6702 7.207 7.710 8.212 9.214

13) A. . 1224 4 1277 2 1327.1 1377.8 1428 1 1478.8 1530.2 1582.4 1635 3 1743.9 04t 25) s {. .- . . .

g. . ..{14287 14460

) l .1DO , l.7822 , l.8237 ,2.8625 1.8990 1.9335 1.964me 2.0281

' ' ~

3 468 3 954 4 413 4 861 S 301 5 738 140 &. 6 172 6 604 7.035 7 sv5 1221.1 1275.2 1326 4- 13768 1427.3 1478.2 (353 02) s 1529.7 1581.9 1634 9 1741%

160b7 l6663 17190 1.7645 1.8063 1.8451 1.8817 1.9163 1.9493 2 0110 O i..

3 008 3 443 3 849 4 244 4 638 5 015 5.396 160 A. 1:17 6 12731 1325 0 1375 7 5 775 6 152 6 90b 1426 4 1477.5 15291 1581 4 (M) 531 s. l.590b I6519 17033 1634 5 1743.2 1.7491 1.7911 1.3301 1.8667 , s.9014 1.9344 1.9962 2 649 3 044 3 diI 3 764 4 110 4 452 180 &. 4.792 5 129 5 466 6 136 12140 1271 0 1323 5 1374 7 1425 6 1476 8 1528 6 (37304 s. 1581 0 1634 1 1742 9 1.5745 16373 1 6494 1.7355 1.7776 1.8167 1.8534 1.8882 f.9212 1.9831

,. 2.M i

' 2 726 3 060 3 380 3 693 4 002 4 309 3]O A. 4 613 4.917 5 521 1210 3 1268 9 13221 1373 6 1424 8 1476 2 15280 1580.5 1633.7 1742 6 (381.79) s. 1.5594 I6240 1 6767 1.7232 1 7655 1.8048 1.5415 1.8763 1.9094 1.9783

e. 2.125 2 465 2 772 3 066 3 352 3 634 3.913 4 191 4 467 5 017 220 A. 12065 1266 7 1320 7 1372 6 1424 0 1475 5 1527 5 1580 0 1633 3 1742 3 (38946) s 1.5453 16117 16652 1.7120 1 7545 1 7939 I.830s 1 8656 1.8987 1.9607 e

19276 2 247 2 533 804 3 Oca 3 327 3 584 3 839 240 A. 4 093 4597 1200 5 1264 5 1319 2 1371.5 14:32 1474 a 1526 9 1579 6 1632 9 1742 0 (197 37) s 15319 I6003 1 6546 1.7017 17444 I7839 182(.N IB558 I8889 I.9510

• . 2 063 2 330 2 582 2 427 3 067 3 305 3 541 3 776 4 242 260 A. 12623 1317 7 1370 4 1422 3 1474 2 1526 3 15791 1632.5 1741 7 (404 42) s 1.5897 16447 I6922 1.7352 17748 f.8lls 18467 I8799 1.9420

e. 1 9047 21% 2 392 2 62: 2 645 3 066 3 286 3.504 3 936 22 A. 1260 0 13162 1369 4 1421.5 1473 5 1525 b 1578 6 1632.1 1741 4 (411.0$J s. l.5796 1.6354 1.6434 17265 8.7662 1.b033 1.8383 18716 1.9337

e. l.7675 2 005 2.227 2 442 2 652 2 850 3 065 3 269 3 674 300 A. 1260 0 1316 2 IM83 1420 6 1472B 1525 2 157s i 1631.7 1741 0 (417.33) s. 1.5701 1.6268 I6751 1 7164 17582 l.7954 1.s305 18638 1.9260 l.4923 1 7036 18960 2Ob4 2 266 2 445 2 622 2 798 3147 350 A. 1251.5 1310 9 IMS5 141b $ 1471.1 1523 8 1577 0 1630 7 1740 3 (431.72) s. 1.54b1 Ie070 16%) 1.7002 17403 1.7777 1.8130 18463 1 906t

• . 1.2851 14770 1 6506 I8161 19767 2134 2 290 2 445 2 75:

400 A. 12451 130t, 9 1%:7 1416 4 1469 4 1522 4 1575 8 1624 6 1 % .'

(444 59) s 15281 ,15894 1 6.196 1 6842 1724' l.7623 17977 I8311 I tGk

e * * .

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• N '*'k -! L ,,}

14 M '

y . . '

y b o/s J *YK: %i' I Y./ I , yt/ f

. r: .e/. A MW i/'/1 /Mv/4 Pe L/r A/ vp/ .*!.'

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i Yf

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.r ,* / A // D /IV,'13%. r ' .M 1.

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Entropy l

l l

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

5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 27 ANSWERS -- ROBINSON -

86/03/14-TOM ROGERS ANSWER 5.01 (1.00) b REFERENCE MNS OP-MC-SPS-RT-RP, p.24.

HBR RXTH HO-1, 39, p. 2.

ANSWER 5.02 (1.00) c REFERENCE HBR RXTH-HO-1, 23, p.2.

ANSWER 5.03 (1.00) b REFERENCE MNS OP-MC-SPS-RT-RCO, p.37.

HBR RXTH-H01, 36, p.2.

ANSWER 5.04 (1.00) c REFERENCE MNS Thermo-Core Performance, p.2.

GP HTT&FF, p.270 ANSWER 5.05 (1.00) a REFERENCE MNS Core Performance, p.10.

GP HTT&FF, pp. 243-244.

, , , -, r,--,,.- v, - ,,-w ,,--.w - -w-v-

s s

5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 28-ANSWERS -- ROBINSON -

86/03/14-TOM ROGERS ANSWER 5.06 (1.00) b REFERENCE MNS Thermo, para. 2.6.

GP HTT&FF, pp.102-103.

ANSWER 5.07 (2.00) -

c. INCREASE (0.5)

b. INCREASE (0.5)

c. DECREASE (0.5)

d. DECREASE (0.5)

REFERENCE General Physics, HT & FF - Fluid Flow Applications for Systems and Components 002/000-K5.01 (3.1/3.4)

ANSWER 5.08 (2.00)

a. Decrease

b. Increase

c. Increase

d. Decrease CO.5 each3 (2.5)

REFERENCE .

WNTC Thermo.

General Physics HTFF, p 319-334.

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

5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 29 ANSWERS -- ROBINSON -86/03/14-TOM ROGERS ANSWER 5.09 (3.00)

o. 1. Decrease

2. Increase

3. Increase

4. Increase

5. Decrease

6. Decrease CO.5 each3 (3.0)

REFERENCE Simulator Malfunction 4179.

HBR RXTH-HO-1, Session 48.

ANSWER 5.10 ( .50)

TRUE REFERENCE General Physics, HT & FF, p. 176 002/000-K5.01 ANSWER 5.11 (1.50) 9 0.5 points each for NNS and HBR:

1. Shutdown mar 3i n.

2. Limit + reactivity on a rod ejection and misaligned rod.

3. Acceptable power distrubutiion limits.

9 0.5 points each for CNS: *

1. Shutdown margin.

2. Rod misalignment effects for analyzed accidents,

3. Acceptable power distrubution limits. -

REFERENCE MNS Core Performance, p.31.

CNS TS Bases 3/4.1.3.

HBR RXTH-HO-1, 50, p.2.

o

5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 30 ANSWERS -- ROBINSON -86/03/14-TOM ROGERS ANSWER 5.12 (1.00)

Dry bulb, wet bulb, dew point.

REFERENCE Thermodynamics, K. Mark, p.423.

ANSWER 5.13 (3.00)

c. The initial power drop will be greater at EOL Ed.53. The smaller B, the greater the prompt drop for a given reactivity addition E0.53.

b. The reactor responds faster at EOL E0.53. The smaller B, the higher the SUR for a given reactivity insertion E0.53.

c. Tave will be lower at BOL CO.53. The smaller MTC requires a larger temperature drop to ralance the negative reactivity inserted by the rod CO.53.

REFERENCE CP&L Reactor Theory Chap. 12 p.22 and Chap. 14 p.6 HBR RXTH-HO-1, Session 47.

ANSWER 5.14 (3.00)

a. ACP LOWER than ECP because the lowerin3 of temperature will insert positive reactivity resulting in criticality at a lower rod height. (1.0)

b. ACP HIGHER than ECP because the higher boron concentration inserts negative reactivity, resulting in a higher rod height. (1.0)

c. ACP LOWER than ECP because xenon concentration will be decreasing which inserts positive reactivity therfore a lower rod height. (1.0)

REFERENCE C-E Reactor Theory HBR RXTH-HO-1, Session 51.

u r

5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 31 ANSWERS -- ROBINSON -86/03/14-TOM ROGERS ANSWER 5.15 (1.00)

To overcome the reactivity gnserted 'from doppler and MTC on a trip.

REFERENCE HBR RXTH-HO-1, p.2.

ANSWER 5.16 (1.00)

Following a reactor shutdown Xe will increase and may add more nes.

reactivity than the existing excess reactivity. If this occured, a delay in the startup would result until Xe peaked and then decayed to a value-balow the existin3 excess reactivity.

REFERENCE HBR RXTH-HO-1, 39, p.2.

ANSWER 5.17 (1.00)

a. Sb-Be will decay to levels to low for indication if the reactor is 7hutdown for an extended period of time so a source with a much longer half life is used.[0.5] 0 , >'. / * - d (

b. Any two 9 0.25 points each: >#

, s/

"'As-

,P

1. Californium (252)

2. Americium-beryllium .)

3. Polonium-beryllium g.,Q, REFERENCE P

• u HBR RXTH-HO-1, 40, pp.39-40.

gr-

,)

ANSWER 5.18 (1.00)

Suspended- The bed of resin beads performs as a filter as it is porous for water and catches particulate.EO.5]

Dipsoloved- Ionic exchange of a positive ion (Li) for a positive H ion on the resin compound. (The resin has a higher affinity to Li ions than H ions.)[0.5]

5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 32 ANSWERS -- ROBINSON -86/03/14-TOM ROGERS REFERENCE SHNPP Chem-LP-1.1.

ANSWER 5.19 (1.00)

Whether current leads or lags voltage.

REFERENCE Applied Engineering Principles, Westinghouse Corp., p.1-12.

ANSWER 5.20 (1.00) 1.4 DPM REFERENCE MNS OP-MC-SPS-RT-RK, p.7.

HBR RXTH-HO-1, 43,p.3.

ANSWER 5.21 (1.00) 0.9 REFERENCE HNS OP-MC-SPS-RT-SMep.11.

HBR RXTH-HO-1, 42, p.2.

ANSWER 5.22 (1.00) 3%

From G=mt.

REFERENCE MNS Thermo, Sec. 8.

GP HTT&FFr p.14.

6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 33 ANSWERS -- ROBINSON -86/03/14-TOM ROGERS ANSWER 6.01 (3.00)

. 35 44 CC

c. PZR low pressure High steamline differential E9-5 each]

b. -Inj tbo$ raDdbo$cacidtocom nsate f for the positive reactivity caused by the cooldown. CO 3 .h cu

-Provide makeup to restore PZR level from the ' shrinkage" caused by the cooldown. [0.%3 g 4 3 REFERENCE -

HBR SD-002, p 28; exam bank 2-6-25.

s av g h ANSWER 6.02 (M60)

a. -Turbine bids supply

-SW booster pump suction

-SW booster pump discharge

-Aux bids hallway (above booster pumps

-A diesel room

-Intake structure of SW pump discharge

-Intake structure of SW to cire. water pump seals. Efour required 341-0)

b. Supply to the turbine bids. shuts E0.53, and only two SW pumps have power available.EO.53 REFERENCE HBR SD-004; -006.

~

ANSWER 6.03 (2.00)

a. No .

b. No

c. Yes ,

d. Yes (CAF) E0.5 each3 REFERENCE SHUPP PZRPC-HO-1.0, p 22, fig. PZRPC-TP-5.0.

HBR DWG No HBR2-8643.

L-

6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 34 ANSWERS -- ROBINSON -86/03/14-TOM ROGERS CL ANSWER 6 04 (2.00) ./* je T

o. The impulse lines (inside CV) F 3d </g pc eget

b. To compensate the D/P measurement for temperature changes inside the CV (i.e. accident conditions inside CV).

c. Wide range RCS pressure.

d. 90.

REFERENCE HBR SD-051, p 7,11,13.

ANSWER 6.05 (1.50)

a. 1. Electrical fault (0.5)

2. Low dischar3e Pressure (0.5)

b. TRUE (0.5)

REFERENCE HBR SD-027, p 16,29.

ANSWER 6.06 (2.00)

a. Increase

b. Decrease

c. Decrease

d. Increase CO.5 each] (7.0) ,

REFERENCE HBR SD-003, p 8-10. .

h

60 PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 35 ANSWERS -- ROBINSON -86/03/14-TOM ROGERS ANSWER 6.07 (1.50)

a. F

b. T

c. T REFERENCE HBR SD-005, p 2-3.

ANSWER 6.08 (1.00) d (1.0)

REFERENCE HBR SD-011, p 26.

ANSWER 6.09 (1.00) d (1.0)

REFERENCE HBR exas b:r.h 3-14.

ANSWER 6.10 (2.00)

1. OT Delta-T (0.5)

2. OP Delta-T (0.5)

3. BOTH (0.5)

4. OT Delta-T ,

(0.5) 4 REFERENCE -

HBR SD-011, p 5-7.

60 PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 36 ANSWERS -- ROBINSON -

86/03/14-TOM ROGERS ANSWER 6 (1.00)

C l.11 Y r REFERENCE HBR/SD-025, p. 16.

ANSWER 6.12 (1.00) c.

REFERENCE MNS MC-IC-ILE-5 Component pressure transmitters (2.4/2.5)

ANSWER 6.13 (2.00)

1. b

2. a

3. d

4. d E0.5 each] (1.0)

REFERENCE HBR DWG No. CP-300-5379-3692.

il ANSW 6.14 \ (1.00)

Allows ,

tio of the mast when gripper tube is not at top limit.

REFERENCE HBR SD-008, p.30.

o ANSWER 6.15 (1.00)

Condensate System (disc. of pump).

REFERENCE HBS SD-033, p.9.

x- --

r ,-r-.-- , -.-- , . , , , , c y --.v- --g - . - - , , . - - - - - , , , . - .- - - - - - - - - - -

60 PLANT SYSTEMS DESIGN, CONTROL,'AND INSTRUMENTATION PAGE 37 ANSWERS -- ROBINSON -86/03/14-TOM ROGERS ANSWER 6.16 (1 00)

1. Shutdown equipment in local control annunciator. (0.5)

2. Loss of affected pump indication on RTGB. (0.5)

REFERENCE HBR exam bank 2-6-65.

ANSWER 6.17 (2.00) ,

a. 1. Suction penetration location (4 feet below normal water level).

2. Discharge vacuum breaker (1 in line prevents siphoning).

[0.5 each3 (1.0)

b. Drain valve to the RCDT opened E0.23, pumped by refueling purification pump E0.43 thru the demineralizer and filter E0.43 to RWST. (1.0)

REFERENCE HBR SD-014, p 4,12.

ANSWER 6.18 (2.00)

a. 1. Maintain NPSH for CCWP's

2. Provide makeup water for CCW system

3. Provide for thermal expansion of fluid

4. Provide for contraction of fluid

5. Provide for inleakage of water [3 required, 0.33 each]

b. Device [0.25 each3 Lo, cation E0.25 each3 4 ______________________________

1. R-17 CC Heater Room CCW return line

2. RCV-017 Surge tank room

, 3. CVC 626 Pipe alley RCP thermal barrier water i return

6. PLANT SYSTEMS DESIGNr CONTROL, AND INSTRUMENTATION PAGE 38 ANSWERS -- ROBINSON -86/03/14-TOM ROGERS REFERENCE HBR SD-013, p 2,3.

4 0

1 6

I D

,,.,,n,--r n--aen,,-e-,,,,,--n.wn . . . -

7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 39

~~~~R I6 EUU5UhE~6 UNTRUE ~~~~~~~~~~~~~~~~~~~~~~~~

ANSWERS -- ROBINSON -86/03/14-TOM ROGERS ANSWER 7.01 (1.00) b (1.0)

REFERENCE HBR AOP-001.

ANSWER 7.02 (1.00) d REFERENCE HBR AOP-012, p 4-5.

ANSWER 7.03 (2.00)

c. If CST level drops below 10%.

b. RCS wide range cold les temperature.

c. Prevent steam voiding in the reactor vessel. [0. each3 REFERENCE HBR EPP-5, p 5,6,10.

ANSWER' 7.04 (1.00) b.

REFERENCE '

HBR:AOP-005, p 15.

ANSWER 7.05 (1.00)

.46 t< 8

7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 40

~ ~~~~~~~~~~~~~~~~~~~~~~~~

~~~~R d656L66E6IL 56 TR6L ANSWERS -- ROBINSON -86/03/14-TOM ROGERS REFERENCE HB R ^ ^ ^ 27 er- 6 . . ; 35p t rt~ t , y. t a ANSWER 7.06 (1.00) b (1.0)

REFERENCE HBR EPP-1, p 6.

ANSWER 7.07 (1.00) c REFERENCE HBR GP-003, p 25.

ANSWER 7.08 ( .50)

TRUE.

REFERENCE HBR EMP 11, p.6.

ANSWER 7.09 ( .50)

FALSE.

REFERENCE HBR EMP 11, p.3.

ANSWER 7.10 (1.00)

a. T. -

b. T.

REEERENCE HBR OMM 22, p 6,7,12,13.

7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 41

~ ~~~~~~~~~~~~~~~~~~~~~~~~

~~~~R5656E6656dL 66UTR6L ANSWERS -- ROBINSON -86/03/14-TOM ROGERS ANSWER 7.11 (1.50)

1. beced.

2. bec.

3. arbeced,(e). [0.5 each3 REFERENCE HBR SD-002, p 27. ,

ANSWER 7.12 (1.50) 9 0.5 points each, any three of the followinst

1. Excessive control rod insertion (below limit).

2. Uncontrolled cooldown following a reactor trip.

3. Unexplained or uncontrolled reactivity increases.

4. 2 or more RPIs fail to indicate rods fully inserted after a trip or normal shutdown.

REFERENCE HBR AOP-002, pp.3-4.

ANSWER 7.13 (1.00) 2 min.

REFERENCE HBR Loss of CCW, p. 5.

ANSWER 7.14 (1.00) ,

e 50 REFERENCE GP-005, p.12.

7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 42

~~~~Rd656[6656kE~66 TRUE~~~~~~~~~~~~~~~~~~~~~~~~

ANSWERS -- ROBINSON -

86/03/14-TOM ROGERS ANSWER 7.15 (1.00)

a. 10 (0.5)

(0.5) b.

fuelfCxd" REFERENCE HBR EPP-9, p 5.

ANSWER 7 16 (1.00) 21 days.

REFERENCE HBR AP-004, p 30.

ANSWER 7.17 (2.00)

a. 6500 mrem. [0.53

b. 1. M*J mrem \1 5*

2. 1250 aren

3. 3000 mrem E0.5 each3 REFERENCE 10 CFR 20; HBR DP-014, p 5; HPP-001, p 5.

ANSWER 7.18 (1.00) 100 MWe REFERENCE .

HBR'GP-005, p.25.

ANSWER 7.19 (1.00)

1. In a core location.EO.53 2.'In the upender with the upender subsequently lowered.EO.53 7 -e.- - - - , - - - , , p---,..,_e,---gw--,-e -m-,n -

,m-_g-, , - . - - p. -4 ,y-e,an,...,.-4,,.o . , - - . . . __,- , .,r- , - - , - , , , . - - . , -- . , .

e

7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 43

~~~~EA656E66565L 66UTE6L~ ~"'" ''

ANSWERS -- ROBINSON -86/03/14-TOM ROGERS REFERENCE HBR FHP-035, p.10.

ANSWER 7.20 (1.00) 9 0.5 points each!

50% and 90%.

REFERENCE HBR GP-005, p.28. -

ANSWER 7.21 (2.00)

o. At least one SI pump running Less than 25-F subcooling (C35-F3)

b. Less than 25-F subcooling (E353)

Cannot maintain >10% PZR level E0.5 each3 REFERENCE HBR EPP Foldout A.

ANSWER 7.22 (3.50)

'a. RX trip and bypass breakers open Neutron flux decreasing

b. Manually insert control rods Manually trip the turbine Start AFW or FW pumps Initiate emergency boration of the RCS iDispatch operator to trip the rod drive MG sets E0.5 each3 REFERENCE .

HBR EPP-1, p 3; PATH-1.

. , _ , , , . . . . _ _ . , - , . . . . - , - . . . . , , _ _ . . _ , - . . . ~ _ _ , , , . _ , _ _ . _ _ , , , , . . . , _ _ , _ . . _ . , -,,~,___% , _ , _ _ __ . , - . _ . . _ - = . -

7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 44

~~~~Ed65UEU5EUAE~66UiR5E---------~~-------------

ANSWERS -- ROBINSON -86/03/14-TOM ROGERS ANSWER 7.23 (1.50)

Any 3 0 0.5 points each

1. CCW flow to thermal barrier (<25 spm)

2. CCW inlet temp (>105F)  ;

3. Pump bearing temp (>180F)

4. No. 1 seal leakoff temp (170F)

REFERENCE ,

HBR AOP 18, p.14.

ANSWER 7.24 (1.00)

This in conjunction with low steam line pressure or low tav3 will initiate SIS and steam line valve closure. (1.0)

REFERENCE HBR OP-001, p 5.

s A

e

e D. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 45 ANSWERS -- ROBINSON -86/03/14-TOM ROGERS ANSWER 8.01 (1.00) b REFERENCE 10CFR50, Appendix A, Criterion 56 ANSWER 8.02 (1.00) b REFERENCE McG, TS, p. 1-1 Surry, TS 1.0-3 CAT, TS, p. 1-1 WBN, TS, p. 1-1 VCS, TS, p. 1-1 HBR, TS, p. 1-3 ANSWER 8.03 (1.00) d REFERENCE Surry, TS 2.3-7 WBN, TS, p. B 2-5 HBR, TS, p. 2.3-5 VCS, TS, p. B 2-6 ANSWER 8.04 (1.00) b ,

REFERENCE HBR, AP-004, p. 29 -

ANSWER 8.05 (1.00) d

e

8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 46 ANSWERS -- ROBINSON -86/03/14-TOM ROGERS REFERENCE HBR, AP-027, p. 6 ANSWER 8.06 (1.00)

D REFERENCE HBR, OMM-1006, p. 2 ANSWER 8.07 (1.00) d REFERENCE HBR, TS, p. 6.2-1 ANSWER 8.08 (1.50)

a. TRUE (0.5)

b. FALSE (0.5)

c. FALSE (0.5) 1 HBR, TS, pp. 3.1-4 and 3.1-11 ANSWER 8.09 (3.00)

~

c. SCO (0.5)

b. SF '

(0.5)

c. eSF (0.5)

d. SCO (0.5)

e. SF (0.5)

f. 3F (0.5)

REFERENCE HBR, OMM-001, pp. 6- 12

e- v

. i. .

0 l

1

___ _ __ _ _____ ___ __5__ __ _ ___$___ __ _ _ _ __

ANSWERS -- ROBINSON -86/03/14-TOM ROGERS ANSWER 8.10 (1 00)

o. 1000 (0.5)

b. RC Foreman (0.5)

REFERENCE HBR, AP-027, p. 21 ANSWER 8.11 (1.00)

1. FIVE (0.5)

2. THREE (0.5)

REFERENCE HBR, TS, p. 6.2-2 ANSWER 8.12 (1.50)

1. Misaligned (> 15 inches) (0.5)

2. Can not be moved by its drive mechanism (0.5)

3. Drop time is not met (> 1.8 seconds) (0.5)

REFERENCE HBR, TS, p. 3.10-8 ANSWER 8.13 (1.00)

1. Its emergency power source is operable (0.5)

2. Its redundant system is operable (0.5)

REFERENCE HBR, TS, p. 1-2

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

8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 48 ANSWERS -- ROBINSON -86/03/14-TOM ROGERS ANSWER 8.14 (1.50)

1. POWER -

< 12% (0.5)

2. PRESSURE -

> 2135 psig (0.25) & < 2400 psis (0.25) (0.5)

3. TEMPERATURE -

< 620 degrees F (0.5)

REFERENCE HBR, TS, P. 2.1-1 ANSWER 8.15 (1.50)

1. UNIDENTIFIED -

1 spa (0.5)

,,2. IDENTIFIED -

10 spa (0.5)

3. PRIMARY TO SECONDARY - 0.35 spa any generator (0.25) or 1 spa total from all generators (0.25) (0.5)

REFERENCE HBR, TS, p. 3.1-16 ANSWER 8.16 (1.50)

1. FOUR (coolers) (0.5)

2. TWO (spray pumps) (0.5)

3. TWO coolers and ONE spray pump (0.5)

REFERENCE HBR, TS, p. 3.3-13 .

ANSWER 8.17 (1.00) a.s> 1 (2 or more) (0.5)

b. hourly (0.5)

REFERENCE HBR, TS, p. 3.10-7a

. .. o

8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 49 ANSWERS -- ROBINSON -86/03/14-TOM ROGERS ANSWER 8.18 (2.00)

ANY FIVE AT 0.4 POINTS EACH:

1. Inadvertant radioactivity release (liquid or gaseous)

2. Major equipment malfunction

3. Unexplained reactivity changes

4. Loss of offsite power

5. Employee injury

6. Radiation exposure

7. Accidents occurring on or near plant ,

REFERENCE HBR, OMM-001, p. 57 ANSWER 8.19 (1.00)

~ ~

Nee-eet-iowis-regyyed4(as lon as RCP continues to dperatet 4 t44 A S W 'ce A (1.0) a c H ,5 $ / A i ' i ,3 . p . 3 co// Sf# +' N ^ 4??Arr REFERENCE Fr HBR, TS, p. 3.1-2 ANSPER 8.20 (1.00)

Plus or minus 25% (0.5), not to exceed 3.25 times the specified inte val for any 3 consectutive intervals (0.5). (1.0)

REFER,INCE HBR, YS, p. 4.1-1 ANSWER 8.21 (1.00)

a. SHIFT FOREMAN [5T( (0.5)

b. SENIOR CONTROL OPERATOR (0 5)

REFERENCE HBR, PEP-101, p. 1

r a ..o e

8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 50 ANSWERS -- ROBINSON -86/03/14-TOM ROGERS ANSWER 8.22 (1.50)

O. When action is immediately needed to protect the public health and safety (0.7) and no procedure that can provide adequate protection is immediately apparent (0.3). (1.0) b.

SHIFTFOREMANf980 (0.5)

REFERENCE HBR, AP-006, pp. 5&7 ANSWER 8.23 (1.00)

By verifying the revision number against the Revision Status List. (1.0)

REFERENCE HBR, OMM-001, p. 39 ANSWER 8.24 (1.00)

n. Once per shift (0.5)

b. By marking recorder with time and initials (0.5)

REFERENCE HBR, OMM-001, p. 33 a

.