ML20210C735
| ML20210C735 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 12/29/1986 |
| From: | Casto C, Munro J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20210C684 | List: |
| References | |
| 50-261-OL-86-02, 50-261-OL-86-2, NUDOCS 8702090450 | |
| Download: ML20210C735 (99) | |
Text
I ENCLOSURE 1 EXAMINATION REPORT 261/0L-86-02 Facility Licensee: Carolina Power and Light Company P. O. Box 1551 Raleigh, NC 27602 Facility Name: H. B. Robinson Facility Docket No.: 50-261 Written and oral 2xaminations were administered at H. B. Robinson near Hartsville, South Car ina.
Chief Examiner: b_o, u A- bd f 2 - / - Er C C. E Cas'tb ' Date Signed Approve by: Sk // fu /2-27_gg Jo F. MuntyfSe on Chief Date Signed Summary:
Examinations on H. B. Robinson Oral examinations were administered to eight candidates; eight of whom passed.
Written examinations were administered to seven candidates; five of whom passed.
Based on the results described above, three of four R0's passed and three of four SR0's passed.
8702090450 870112 PDR V ADOCK 05000261 PDR
l REPORT DETAILS
- 1. Facility Employees Contacted:
- C. Bethea, Director-Training
- S. Allen, Project Specialist-License Training
- 0. Neal, Specialist, License Training 4
- Attended Exit Meeting
- 2. Examiners:
- C Casto.-
P. Isaksen F. Victor l K. Parkinson 4 H. Krug (SRI) I d
- Chief Examiner
- 3. Examination Review Meeting At the conclusion of the written examinations, the examiners provided Steve Allen with a copy of the written examination and answer key for-rev ew. The comments made by the . facility reviewers are included as Enci isure 3 to this report and the NRC Resolutions to these comments -are listed below.
- a. -SRO Exam Section 5
! (1) Question 5.06 NRC Resolution Comment:
l Concur. Answer key revised accordingly.
l (2) Question 5.09, Part a.1 NRC Resolution:
Do not concur. SD-0001, page 29 states that delta T is used to calculate RIL. The- question asked for the parameter that necessitates changing RIL, not what parameter is used to compute i RIL. Power Defect is the parameter that necessitates changing RIL. Answer key not revised.
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i (3) Question 5.10 i
F NRC Resolution:
Do not concur to delete the question. Sufficient information was given within , the question for the candidates to ascertain a i correct response. No reference material was provided for this
, comment.
Section 6 i
(4) Question 6.01, Part b i NRC Resolution:
Concur. Answer key revised accordingly.
(5) Question 6.02, Part b i
NRC Resolution:
i l Concur. ' Answer Key revised accordingly, i
l (6) Question 6.03, Part a i
! Concur. Answer Key revised accordingly.
(7) Question 6.03, Part b Concur. Answer key revised to correspond to updated reference L material.
i-(8) Question 6.06 NRC Resolution:
l Concur. Answer key revised accordingly.
(9) Question 6.08 1 =
l NRC Resolution:
Concur. Answer key revised accordingly.
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(10) Question 6.09, Part a NRC Resolution:
Concur. Answer key revised to accept other reasonable sources.
(11) Question 6.12 NRC Resolution:
Concur. Answer key revised accordingly.
(12) Question 6.13, Part b Concur. Answer key revised accordingly.
Section 7 (13) Question 7.02, Part a NRC Resolution:
Do not concur. The reference provided with the facility comment states that each operator should be generally familiar with each E0P. Knowledge of the E0P entry conditions demonstrates familiarity with the E0P. The operator (s) must be cognizant of entry conditions at all times throughout E0P usage.
(14)_ Question 7.02, Part c NRC Resolution:
Do not concur. The reference provided with the facility comment states that each operator should be generally familiar with each E00 Knowledge of the criteria used to verify adequate core cooiing demonstrates familiarity with the E0P.
(15) Question 7.05 NRC Resolution:
Do not concur. The reference provided with the facility comment states that each operator should be generally familiar with each E0P. Knowledge of components to check if the RCS is isolated demonstrates familiarity with the E0P. In addition, vendor background documentation indicates a need for operator memoriza-tion of these steps. These steps are not contained on flow chart procedures.
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4 (16) Question 7.14 NRC Resolution:
Concur. Answer key revised accordingly.
Section 8 (17) Question 8.05, Part f Do not concur. The reference provided with the facility comments specifies the workers immediate supervisor. Answer key was not revised.
(18) Question 8.08, Parts a and b NRC Resolution: l Do not concur. The time requirements specified in technical specifications are an -integral part of the specified action.
(19) Question 8.12, Parts a and b l
NRC Resolution: ,
Concur. Answer key was revised to require an answer of 1 and 3 for part a and an answer of 1 and 2 for part b.
- b. R0 Exam j Section 1 (1) Question 1.01, Part a l
. NRC Resolution:
Concur. Answer key changed accordingly.
(2) Question 1.04, Part a NRC Resolution:
Concur. Answer key changed accordingly.
(3) Question 1.07, Parts and b NRC Resolution:
Concur. Answer key changed accordingly.
5 (4) Question 1.13 NRC Resolution:
. Concur. Answer key' changed accordingly.
(5). Question 1.15 NRC Resolution:
Concur. Answer key changed accordingly.
.Section 2 (6) Question 2.08 NRC Resolution:
Concur. Answer key changed accordingly.
(7) Question 2.09, Part a NRC Resolution:
Concur. Answer key changed accordingly,
- i. (8) Question 2.13 NRC Resolution:
l Concur. Answer key changed .to accept any two of three answers (Temperature, Boron Concentration, Pressure).
(9) Question 2.14, Parts a and b NRC Resolution:
Concur. Answer key changed accordingly.
(10) Question 2.15 NRC Resolution:
Concur. Parenthesis placed around " transformed to 118V A.C." to
! indicate not required as part of the answer.
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6 (11) Question 2.16, Part b NRC Resolution:
Concur that failed valve position should be deleted. The second part -asked for the flow path on loss- of power. The facility's
- response provided flow path on loss of instrument air. The portion of the question dealing with the failed valve position was deleted and the point value for the question was reduced by a corresponding 0.5 points.
Section 3 (12) Question 3.03 NRC Resolution:
Concur. Answer key changed accordingly.
(13) Question 3.04 NRC Resolution:
Concur. Points were not taken off for P10 additional information.
(14) Question 3.05 NRC Resolution:
Answers were evaluated based on the candidates assumptions and using the guidance - provided by the facility. It should be noted that neither reference OST-005 nor the material originally provided support changing the answer. Rod Control Handout 1, page 11 cited by the facility supports changing the answer; however this material was not provided in the facility's original reference material.
(15) Question 3.07 NRC Resolution:
Concur. Answer key changed accordingly.
(16) Question 3.08 NRC Resolution:
Based on the facility's comments, the answer key was modified to give credit for " pressure less than 465 psig" and deleted that part of answer dealing with the RWST flow path to the RHR Pumps.
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7 (17) Question 3.09
.NRC Resolution:
Concur. Answer key changed accordingly.
(18) Question 3.10 NRC Resolution:
Concur. Answer key changed accordingly.
(19) Question 3.11 NRC Resolution:
Concur. Answer key. changed accordingly.
(20) Question 3.13, Part b NRC Resolution:
Lube Oil holds the valve closed against spring pressure, whether the turbine is tripped or not tripped the system design is unchanged. Answer stands as originally stated.
(21) Question 3.15, Part b NRC Resolution:
Concur. Answer key changed accordingly.
Section 4 (22) Question 4.01 Part b NRC Resolution:
! Concur. -Answer key changed accordingly.
(23) Question 4.05 NRC Resolution:
t Concur. Answer key changed accordingly.
l (24) Question 4.11 NRC Resolution:
Concur. Answer key changed accordingly.
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12 (25)-Question 4.12, Part a NRC Resolution:
Concur. Answer key changed accordingly.
(26) Question 4.12, Part b NRC Resolution:
Answer changed to be consistent with Technical Specifications since the question specifically addressed Technical Specification.
(27) Question 4.13 NRC Resolution:
Concur. Answer key changed accordingly.
- 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.
There were no generic weaknesses noted during the oral examination.
The cooperation given to the examiners and the effort to ensure an atmosphere in the control room conductive 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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MASTER-U. S. NUCLEAR REGULATORY C0tNISSION
.' 00P11 REACTOR OPERATOR LICENSE EXAMINATION FACILITY: ROBINSON REACTOR TYPE: PWR-WEC3 DATE ADMINISTERED: 86/09/30 EXAMINER: VICTOR,F.
CANDIDATE:
INSTRUCTIONS TO CANDIDATE:
Uso separate paper for the answers. Write answers on one side only.
Staple question sheet on top of the answer sheets. Points for each qu stion are indicated in parentheses after the question. The passing grade requires at least 70% in each category and a final grade of at 1:ast 80%. Examination papers will be picked up six (6) hours after the examination starts.
% OF CATEGORY % 0F CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY 25.00 25.06 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW 24.50 24.56 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS L S , i-
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-2h2S~ 25.31 3. INSTRUMENTS AND CONTROLS vs .s' 25.00 25.06 4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL 99.75 Totals Final Grade All work done on this examination is my own. I have neither given nor received aid.
Candidate's Signature l
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NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules apply:
- 1. Cheating on the examination means an automatic denial of your application and could result in more severe penalties.
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- 2. Restroom trips are to be limited and only one candidate at a time may leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.
- 3. Use black ink or dark pencil only to facilitate legible reproductions.
- 4. Print your name in the blank provided on the cover sheet of the examination.
- 5. Fill in the date on the cover sheet of the examinaticn (if necessary).
- 6. Use only the paper provided for answers.
- 7. Print your name in the upper right-hand corner of the first page of each section of the answer sheet.
- 8. Consecutively number each answer sheet, write "End of Category " as appropriate, start each category on a new page, write only on ond side of the paper, and write "Last Page" on the last answer sheeE
- 9. Number each answer as to category and number, for example,1.4, 6.3.
- 10. Skip at least three lines between each answer.
- 11. Separate answer sheets from pad and place finished answer sheets face down on your desk or table.
- 12. Use abbreviations only if they are commonly used in facility literature.
- 13. The point value for each question is indicated in parentheses after the question and can be used as a guide for the depth of answer required.
! 14. Show all calculations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or not.
- 15. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLANK.
- 16. If parts of the examination are not clear as to intent, ask questions of the examiner only.
- 17. You must sign the statement on the cover sheet that indicates that the work is your own and you have not received or been given assistance in completing the examination. This must be done af ter the examination has been completed.
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- 18. When you complete your examination, you shall:
- a. Assemble your examination as follows:
(1) Exam questions on top.
(2) Exam aids - figures, tables, etc.
(3) Answer pages including figures which are part of the answer,
- b. Turn in your copy of the examination and all pages used to answer the examination questions.
- c. Turn in all scrap paper and the balance of the paper that you did not use for answering the questions,
- d. Leave the examination area, as defined by the examiner. If after leaving, you are found in this area while the examination is still in progress, your license nay be denied or revoked.
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- 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 2 THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW QUESTION 1.01 (2.50)
- a. -Define DNBR. (0.5)
- b. What is the DNBR limit for your plant? (0.5)
- c. Since the DNBR is not a directly observable parameter, name SIX parameters the operator monitors and/or controls to ensure the DNBR limit is not violated. (1.5)
QUESTION 1.02 (1.00)
The reactor is operating at 100% power at BOL when a steam dump valve OPENS. State what happens to the following parameters. (Increases, Decreases or Remains The Same) (Assume all Control Systems in MANUAL)
- 1. Tavg
- 2. Reactor Power
- 3. Steam Generator Pressure
- 4. Core DELTA-T 1
QUESTION 1.03 (2.00)
Compared to other control rods,would the center control rod worth be a smaller or larger value under the follow conditions? Why?
- a. The rod is partially ejected during a reactor startup. (1.0)
- b. The rod drops while the plant is operating at full power. (1.0)
QUESTION 1.04 (1.00)
- a. The latent heat of vaporization for water at 2235 psig is (include units). (0.5)
- b. If pressure is reduced from 2235 psig to 100 psig, will latent heat of vaporization INCREASE, DECREASE, or REMAIN THE SAME (0.5)
(***** CATEGORY 01 CONTINUED ON NEXT PAGE *****)
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- 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 3 THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW QUESTION 1.05 (1.50)
Does critial heat flux INCREASE, DECREASE, or REMAIN THE SAME for the following conditions: (consider each separately)
- a. Reactor coolant flow rate increases.
b.' Reactor coolant average temperature increases,
- c. Reactor coolant pressure increases.
QUESTION 1.06 (1.00)
During a Xenon-free reactor startup, critical data was inadvertently taken two decades below the regt: ired Intermediate Range (IR) level (1xE-10 amps).
The critical data was takcn again at the proper IR level (1xE-8 amps).
Assuming RCS temperatures and bcron concentrations were the same for each set of data, how will the control rod position data compare?
.QUESTION 1.07 (1.00)
- a. If the reactor is operating in the power range, how long will i
it take to raise power from 20% to 40% with a +0.5 DPM Start-up rate? (0.5)
- b. How long will it take to raise power from 40% to 60% with the same +0.5 DPM Startup rate? (0.5) l l
QUESTION 1.08 (1.50)
TRUE or FALSE?
l a. Volumetric flow rate for a positive displacement pump increases in the same proportion as the speed increases. (0.5)
- b. As VCT temperature decreases, net positive suction head of the Charging Pump decreases.
(0.5)
- c. Pump runout is the term used to describe the condition of a centrifugal pump were maximum flow is recirculating to the pump suction. (0.5)
(***** CATEGORY 01 CONTINUED ON NEXT PAGE *****)
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- 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 4 THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW QUESTION 1.09 (1.50)
- a. Steam exitSing the HP turbine is at 785 psig, 90% quality. Steam entering the LP turbine is superheated by 100 F. What is the enthalpy change of the steam? (1.0)
- b. During the process in part "a", how much is steam enthalpy changed by mechanical moisture separation in the MSR assuming that the steam quality after separation is 100%. (0.5)
QUESTION 1.10 (1.50)
An ECC has been calculated for a startup following a reactor trip from 100%
power with equilibrium xenon (BOL). Indicate if the actual critical rod position will e HIGHER, LOWER or the SAME from the calculated position for each of the following situations. Use attached curves as appropriate and treat each case individually.
- a. Xenon reactivity curve for trip from 60% is used to calculate (0,5) conditions to startup 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> after the trip.
- b. The Samarium reactivity curve is used instead of the xenon reactivity curve for startup 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> after trip. (0.5)
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- c. The power defect curve for 750 ppm is used instead of the 1100 ppm curve. (0.5) l 1
QUESTION 1.11 (2.00)
- a. Define shutdown margin. (1.0)
- b. List FOUR of the reactivity effects which must be considered l when calculating shutdown margin. (1.0) l I
(***** CATEGORY 01 CONTINUED ON NEXT PAGE *****)
- 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 5 THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW QUESTION 1.12 (1.50)
Match the heat' transfer process in Column A to the equation or equations that applies to that process in Column B.
COLUMN A COLUMN B
- a. _Across the core 1. Q = m Cp AT
- 2. Q= MAT
- b. Across S/G tubes (primary to .
secondary) 3. Q = U AAT
- c. Across S/G (feedwater to steam) 4. Q = m Cp A h
- 5. Q = mah QUESTION 1.13 (1.00)
Using the attached steam tables, what is the amount of primary subcooling at the core exit if the pressurizer is at 2235 psig and Tavg is 575 degrees? (assume normal operating conditions)
QUESTION 1.14 (1.00) f Equilibrium samarium conditions are reached when production rate of l Sm-149 equals the removal rate of Sm-149. For the MOST part, production rate is achieved by the (0.5) process, while removal rate depends on the - (0.5) process.
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QUESTION 1.15 (1.00)
_ Explain how a venturi can be used to measure flow.
l QUESTION 1.16 (2.00)
If the Source Range (SR) instruments indicate 50 cps with Keff equal to 0.9, what would the SR instrument indicate if rods were withdrawn to bring Keff equal to 0.95? How much reactivity was added?
(Show all work)
I (***** CATEGORY 01 CONTINUED ON NEXT PAGE *****)
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~1. PRINCIPLES OF' NUCLEAR POWER PLANT OPERATION, PAGE 6 THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW QUESTION 1.17 (2.00) .
Give two characteristics of doppler coefficient that make it a prime-olements in reactor safety.
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- 2. ' PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS QUESTION 2.01 -(1.00)
What is the basis for the Condensate Storaga Tank minimum level requirement listed in Technical Specifications.
QUESTION 2.02- (1.00)
Name FOUR locations where water collected in the Blowdown Flash Tank may be sent.
QUESTION 2.03 (2.00)
Monitors R-11 and R-12 (C.V.8 PLANT VENT) and R-20 and R-21 (Fuel Handling -
Building) are similar but Monitor R-11 has an additional alarm light. What is being detected by each monitor and why does Monitor R-11 have an additional alarm?
QUESTION 2.04 (2.00)
- a. If a main steam line should rupture just prior to exiting the Containment Vessel, what TWO main steam line design related features would mitigate the consequences of this accident? (1.0)
- b. Describe the events which occur to shut an MSIV when the control switch is placed in the CLOSE position. (1.0) l l
I QUESTION 2.05 (1.00)
State the system and what parameters are measured to detect leakage -
through-the reactor closure head "0" RING SEALS.
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(***** CATEGORY 02 CONTINUED ON NEXT PAGE *****)
- 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 8 QUESTION 2.06 (1.50)
Indicate which of the Excore Nuclear Instrumentation Ranges (SOURCE, INTERMEDIATE, POWER or NONE), apply to each of the following statements.
- a. Uses an opposing current technique to compensate for gamma radiation.
- b. Operates in the Proportional region of the Gas-filled Detector curve.
- c. Covers eight (8) decades of neutron flux.
- d. Provides -input to P-10.
- e. Detector location is lowest outside the core.
' QUESTION 2.07 (1.00)
Explain why an operator would select the ALTERNATE DILUTE mode instead of the DILUTE mode.
QUESTION 2.08 (1.50)
At what pressure are the following components designed to begin providing water to the RCS during a SAFETY INJECTION.
- a. Safety Injection Pumps
- b. Safety Injection Accumulators
- c. Residual Heat Removal Pumps QUESTION 2.09 (3.00)
- a. List FOUR conditions which will automatically trip the Diesel Engine.
- b. Indicate whether the following statements about the Diesel Generator are TRUE or FALSE.
- 1. The synchronizer control is not used if the Diesel Generator is the sole emergency bus power supply.
- 2. If a Diesel Generator shutdown sequence has been initiated in local control and a start signal is received, the Diesel Generator will return to a ready for service condition.
- 3. When the diesel is started and stopped the diesel's ventilation system is automatically started and stopped.
- 4. Prelube pump is not run for automatic diesel start; only for manual starts.
(***** CATEGORY 02 CONTINUED ON NEXT PAGE *****)
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- 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 9 l
l QUESTION 2.10 (3.00)
- a. Describe the normal electrical flow path to the 480V busses E-1 and E-2 starting from the appropriate 4160V bus. (2.0)
- b. Explain what conditions cause the DEGRADED GRID V0LTAGE sensors to actuate to protect safeguards systems from the detrimental effects of reduced voltage. What actions occur when the sensors actuate? (1.0)
QUESTION 2.11 (1.50)
List the THREE pressurization system (s) th" rat supply the Containment Penetration System and indicate for each if it is the normal or backup supply.
QUESTION 2.12 (1.00)
(TRUE or FALSE)
- a. Placing the circuit breakers for the circulating water pump motor in the OPEN position prevents the pump discharge valve from opening when the valve control switch is placed in the OPEN position.
- b. Auxiliary feedwater backup supply comes from the SERVICE WATER system and connects to the pumps suction through two solenoid valves with a tell-tale drain in between.
QUESTION 2.13 (1.00)
Prior to placing the RHR system into operation for plant cooldown, the (0.5) and the (0.5) differences between the RCS and RHR systems must be minimized.
QUESTION 2.14 (2.00) l a. Describe the runback process that occurs with the Main Turbine when l the OT Delta-T setpoint is exceeded? (1.0)
If the Power Range " ROD DROP AUTO TURBINE RUNBACK" is bypassed, b.
what other conditions and what other system could initiate a turbine runback? (1.0) 1 i
(***** CATEGORY 02 CONTINUED ON i1 EXT PAGE *****)
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- 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 10 QUESTION 2.15 (1.00)
What is the NORMAL power supply for Instrument Bus No.l.
QUESTION 2.16 (1.00)
- a. Which of the following is NOT a function of the Volume Control Tank:
- 1. Protide NPSH to charging pumps
- 2. Add hydrazine for oxygen scavenging
- 3. Strip fission gases
- 4. Used for dilution and boration of RCS (0.50)
- b. On loss of power to LCV-115A (VCT/ HOLDUP TANK DIVERSION) flow is directed to .
(0.50)
(***** END OF CATEGORY 02 *****)
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- 3. INSTRUMENTS AND CONTROLS PAGE 11 QUESTION 3.01 (2.50)
When a Reactor Trip signal is initiated, explain how the control. circuits function to open TRAIN A Reactor Trip Breakers and their associated Reactor Trip Bypass Breakers. Include the power sources for the control circuits.
QUESTION 3.02 (1.00)
What level will the Steam Generator Water Level Control System maintain as power changes from 0% to 100%?
QUESTION 3.03 (2.00)
List the automatic signals that will cause Main Steam Line Isolation.
Setpoints are not required.
QUESTION 3.04 (1.00)
After a Reactor trip what conditions must be met for the Source Range Detectors High Voltage to automatically reenergized.
QUESTION 3.05 (3.00)
The plant is operating at 100% power with all control systems in automatic.
Given the following conditions, how will rod height be affected (INCREASE, DECREASE, NO CHANGE)? Assume no operator action and consider each case separately. Assume the Reactor does NOT trip. Briefly explain your l
answer.
- a. A safety valve on B steam generator fails open. (0.75)
- b. One power range detector fails high. (0.75)
- c. C loop narrow-range Tcold instrument fails low. (0.75)
- d. Turbine load is ramped to 80% power. (0.75)
QUESTION 3.06 (1.50)
List ALL the sensors that provide an input to the CORE SUBC00 LING MONITOR.
(***** CATEGORY 03 CONTINUED ON NEXT PAGE *****)
- 3. INSTRUMENTS AND CONTROLS PAGE 12 QUESTION 3.07 (2.00)
What FOUR conditions will ONLY block MANUAL R00 WITHDRAWAL. Include setpoints and required coincidence for each.
QUESTION 3.08 (1.75)
Explain how the valve interlocks in the RHR system function to prevent the system from being overpressurized.
QUESTION 3.09 (1.50)
With the plant at NORMAL operating conditions list the events that would occur if Pressurizer Level Channel 459 FAILED HIGH. Cover the period from initiation of the casualty until the plant is stable or the Reactor Trips.
QUESTION 3.10 (1.00)
In which position (s) of the Service Water Strainers Switch (CONTINUOUS, 0FF, or INTERMITTENT) will an alarm be received at the RTGB when a HIGH DIFFERENTIAL PRESSURE exists across the strainer?
QUESTION 3.11 (1.00)
Explain the function of the LOAD BISTABLE and the TEMPERATURE BISTABLE used in the Steam Dump Control System.(Setpoints not required)
QUESTION 3.12 (1.00)
List the TWO conditions which must be satisfied before the Dedicated Shutdown Diesel air start solenoid valve will open.
(***** CATEGORY 03 CONTINUED ON NEXT PAGE *****)
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- 3. INSTRUMENTS AND CONTROLS PAGE 13 J l
I QUESTION 3.13 (1.50)
Indicate whether the following statements concerning the Main Turbine and Turbine Control System are TRUE or FALSE.
- a. The reheat stop valve and interceptor valve will close if the governing and intercept valve close on loss of load.
- b. Lube oil supplied to the interface trip valve will hold the valve closed.
- c. When the discharge pressure for the D.C. motor driven oil pump is above 25 psig the pump will stop if the switch is in the AUTO position.
QUESTION 3.14 (1.00)
What TWO type of instrumentation are used to provide leak indication for the Pressurizer Safety Valves?
QUESTION 3.15 (2.00)
- a. List FOUR Signals that cause automatic closure of the Steam Generator blowdown isolation valves. (1.0)
- b. What are FOUR Conditions which cause automatic closure of the CVCS orifice isolation valves? (1.0)
QUESTION 3.16 (1.50)
List SIX Reactor trips which are blocked by the Reactor Protection system interlock P-7.
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(***** END OF CATEGORY 03 *****)
- 4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 14 RADIOLOGICAL CONTROL QUESTION 4.01 (1.00)
- a. In EPP-1, Loss Of All AC Power, it states that the SI SIGNAL should be reset. Why is this action important? (0.5)
- b. Another requirement in EPP-1 is to VERIFY Phase A Isolation. How is this step accomplished? (0.5)
QUESTION 4.02 (2.50)
- a. In automatic rod control, one reason for a Continuous Withdrawal of a Control Bank is a malfunction or problem with the Rod Control System.
What is another problem or malfunction that could also cause CONTINUOUS WITHDRAWAL of a Control Bank and name TWD systems that could cause this problem. (1.0)
- b. If a CONTINU0US WITHDRAWAL of a Control Bank causalty had been initiated list FIVE Automatic actions that could prevent a Reactor Trip. (1.5)
QUESTION 4.03 (1.50)
In accordance with A0P-18 what FOUR parameters are required to be monitored if Coolant Pump is to continue operating without Seal Water Injection?
l l
(1.00)
QUESTION 4.04 If DEPRESSURIZATION of the RCS is required, list the THREE methods to be used in their preferred order.
l l
l QUESTION 4.05 (1.00) l With the plant above 400 degrees F, ONE Safety Injection Pump becomes inoperable. In accordance with Technical Specifications, what action is required prior to initiating repairs to the pump?
(***** CATEGORY 04 CONTINUED ON NEXT PAGE *****)
-4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 15 RADIOLOGICAL CONTROL QUESTION 4.06 (3.00)
- a. List FIVE TREND VALUES used to verify that Natural Circulation has been established. (2.5)
- b. What action is required if Natural Circulation is NOT verified? (0.5)
.UESTION Q 4.07 (1.50)'
- a. Explain the process for implementation and approval of a TEMPORARY CHANGE which does NOT violate the intended function of the original procedure. (1.0)
- b. What is the MAXIMUM time period until a Temporary Change must be cancelled? (0.5)
QUESTION 4.08 (2.00)
List THREE reasons why the Control Banks are maintained above their respective insertion limits while the Reactor is critical.
QUESTION 4.09 (2.00)
- a. Prior to transferring from MANUAL to AUTOMATIC Rod Control what are the limitations on temperature? Why? (1.5) l
' b. Inaccordance with GP-006 during a Reactor Shutdown, when should the
! operator shift to MANUAL Rod Control? Why? (0.5) l QUESTION 4.10 (1.00)
With the Low Temperature Overpressure Protection System in operation and l
BOTH PORVs 'become inoperable, what action should be initiated?
'j QUESTION .4.11 (1.50)
In accordance with A0P-012 what THREE Immediate Operator Action are required if a Partial Loss Of Condenser Vacuum occurs?
(***** CATEGORY 04 CONTINUED ON NEXT P AGE *****)
~.. - .- - - - _ . -
- 4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 16 RADIOLOGICAL CONTROL QUESTION 4.12 (2.00)
- a. List the location of the following Facilities:
Operations St,:90rt Center (OSC)
Techinical Support Center (TSC) (0.5)
Emergency Operations Facility (EOF)
- b. With the plant at normal temperature, by Technical Specifications what personnel comprise the minimum on shift organization? (1.5)
QUESTION 4.13 (1.50)
Under what conditions would it be necessary to use DSP-001 (Hot Shutdown Procedure Using The Dedicated / Alternate Shutdown System)?
QUESTION 4.14 (1.00)
Explain the process for the removal of a Jumper or Wire Removal Tag from a Safety Related System and the return of the system to service.
QUESTION 4.15 (1.50)
List the SIX Critial Safety Functions in order of importance.
QUESTION 4.16 (1.00)
When changing plant conditions from Cold Solid to Hot Subcritical at No-load T-avg, it may be necessary to start and stop the Reactor Coolant Pumps at frequent intervals. If THREE starts and stops or attempted starts have been made within a two-hour period (pumps are not running),
what action is required by OP-101 if it is necessary to start a RCP again?
(***** END OF CATEGORY 04 *****)
I************* run AF FYAMINATTOM ***************)
\
(4 <'
EQUATION SHEET f = ma .v = s/t C w = mg a = v,t + at 2 Cycle efficiency =
Energy (in) if E = mC 2
, a = (vg - v,)/t i-KE = g v v A = AN A=Ae g
= v, + a t PE = agh m = 0/t. A = In 2/t;s = 0.693/t g W = VAP AE = 931Am t q(eff) = (ti:)(tu)-
(t, +t) b Q = mC oT -EX P I=Ie
, o Q = UAAT I=Ie -MX Pwr = Wg m I=I
~
10
- o P=P 10 SUR(t) TVL = 1.3/p P=P O
et /T HVL = 0.693/u SUR = 26.06/T T = 1.44 DT SCR = S/(1 - Keff)
/A 8 p)
SUR = 26 1 g CR x = S/(1 - K gg )
J T = '(1*/p ) + [(f _' p) /Aeff) D CR 1 (1 - Keff)l = CR 2 (1 - Keff)2 T = 1*/ (p - D M = 1/(1 - K gg) = CR g/CR0
~
~P eff" M = (1 - K gg)0 ( ~ eff}1 P " ( eff~I)! eff " 0 effI eff SDM = (1 - K fg)/K gg p= [1*/TKfgg -] + [B/(I + Aggg)] T ,
t* = 1 x 10~ seconds P = I4V/(3 x 1010) A,gg = 0.1 seconds ~
I = No Idg =Id 22 WATER PARAMETERS Idg =1d2 1 gal. = 8.345 lbm R/hr = (0.5 CE)/d (meters)
I gal. = 3.78 liters R/hr = 6 CE/d (feet)
I ft = 7.48 gal. MISCELLANEOUS CONVERSIONS .
3 10 Density = 62.4 lbm/ft 1 Curie = 3.7 x 10 dps Density = L gm/cm i kg = 2.21 lbm lleat of va;orizations = 970 Etu/lbm 1 bp = 2.54 x 10 BTU /hr 6
, IIcat of fusica = 144 Btu /lbm 1 Mw = 3.41 x 10 Btu /hr
- k. 1 Atm = 14.7 psi = 29.9 in. Ig. I Btu = 778 ft-lbf 2
I ft. H O 2
= 0.4333 lbf/in 1 inch = 2.54 cm F = 9/5 C + 32 "C = 5/9 ( F - 32)
- ~ _ _ _ .
t 8 IMW;. StW/lb (Mf 0py. Stu/lb a F Vehime.ft/lb Twp h ss. g,,, gg,,, w ,,,, g,,, go. w,,,, g,,, g,,
, s, s,
"' "8s "a s,,
't '8s 's
-0.02 1075.5 1075.5 0.0000 2.1873 2.1873 32 0.01602 3305 3305 32 0.048 %
3.00 1073.8 1076.8 0.00f.1 2.1706 2.1767 35 0.01602 2948 2948 0.0162 2.1432 2.1594 40 35 0.09991 8 03 1071.0 1079.0 0.01602 2446 2446 0 0262 2.1164 2.1426 45 40 0.12163 13.04 1068.1 1081.2 0.14744 0.01602 2037.7 2037.8 0.0361 2.0901 2.1262 50 45 3704.8 18.05 1065.3 1063.4 50 0.17796 0.01602 1704.8 1067.7 0.05$5 2.0391 2.0946 60 1207.6 28.06 1059.7 60 0.2561 0.01603 1207.6 38.05 1054.0 1092.1 0.0745 1.9900 2.0645 70 0.3629 0A1605 868.3 868.4 0.0932 1.9426 2.0359 80 70 433.3 48.04 1048.4 1096.4 0.5068 OA1607 633.3 0.1115 1.8970 2.0006 90 80 458.1 E02 1042.7 1100A 0.6981 0.01610 468.1 0.1295 1A530 1.9825 100 90 350.4 68 00 1037.1 1105.1 0.9492 0.01613 350.4 0.1472 1.8105 1.9577 110 100 265.4 77.98 1031.4 1109.3 110 1J750 041617 265.4 87.97 1025.6 1113.6 0.1646 1.7693 1.9339 120 041620 203.25 203.26 1.9112 130 120 1A927 97.96 1019A 1117A 0.1817 1.7295 0.01625 157.32 157.33 1.8895 140 130 2.2230 107.95 1014.0 1122.0 0.1985 1.6910 0.01629 122.98 123.00 1.8686 150 140 2.8892 117.95 1008.2 1126.1 0.2150 1.6536 0.01634 97.05 97.07 1A447 160 150 3.718 127.96 1002.2 1130.2 0.2313 1.6174 4.741 OA1640 77.27 77.29 150 17tr-996.2 1134.2 0.2473 1.5822 1.8295 62.04 62.06 137.97 170 5.993 0.01645 990.2 1138.2 0.2631 1.5480 1A111 las 0.01651 50.21 50.22 148.00 190 1e0 7.511 984.1 1142.1 0.2787 1.5148 1.7934 041657 40.94 40.96 158.04 200 190 9.340 977.9 1146.0 0.2940 1.4824 1.7764 0.01664 33.62 33.64 168.09 200 11.526 971.6 1149.7 0.3091 1.4509 1.7600 210 0A1671 27.80 27.82 178.15 210 14.123 970J 1150.5 0J121 1.4447 1.7568 212 0.01672 26.78 26.80 180.17 212 14.696 965.2 1153.4 0.3241 1.4201 1.7442 220 0.01678 23.13 23.15 188.23 220 17.186 958.7 1157.1 OJ388 1.3902 1.7290 230 19.364 19.381 198.33 230 20.779 0.01685 952.1 1160.6 OJ533 1.3605 1.7142 240 0.01693 16.304 16.321 208.45 250 240 24.968 945.4 1164.0 OJ677 1.3323 1.7000 l
0.01701 13.802 13.819 218.59 250 29225 938.6 1167.4 0.3819 1.3043 1.6862 260 ,
0.01709 11.745 11.762 228.76 270 260 35.427 931.7 1170.6 0.3960 1.2769 1.6729 0 01718 10.042 10.060 238.95 230 270 41.856 924.6 1173A 0.4098 1.2501 1.6599 0.01726 8.627 8.644 249.17 290 200 49.200 917.4 1176.8 0.4236 1.2238 1.4473 0.01736 7.443 7.460 259.4 300 230 57.550 910.0 1179.7 0.4372 1.1979 1.6351 0.01745 6.448 6.466 269.7 300 67.005 1182.5 0.4506 1.1726 1.6232 310 5.609 5.626 280.0 902.5 310 77.67 0.01755 1185.2 0.4640 1.1477 1.6116 320 4.896 4.914 290.4 894.8 320 89.64 0.01766 1190.1 0.4902 1.0990 1.5892 340 3.77U 3.788 311.3 878.8 '
340 117.99 0.01787 1194.4 0.5161 1.0517 1.5678 360 2.939 2.957 332.3 862.1 360 153.01 0.01811 1198.0 0.5416 1.0057 '1.5473 330 2.317 2.335 353.6 844.5 340 195.73 0.01836 1201.0 0.5667 0.9607 1.5274 400 1.8444 1.8630 375.1 825.9 400 247.26 0.01864 806.2 1203.1 0.5915 0.9165 1.5080 420 1.4808 1.4997 396.9 420 303.78 0.01694 419.0 785.4 1204.4 0.6161 02729 1.4890 440 0.01926 1.1976 1.2169 1.4704 460 440 381.54 0.9942 441.5 763.2 1204.8 0.6405 0.8299 460 466.9 0.0196 0.9746 0.6648 0.7871 1.4515 480 0.8172 464.5 739.6 1204.1 480 566.2 0.0200 0.7972 487.9 714.3 1202.2 0.6890 0.7443 1.4333 500 680.9 - 0.0204 0.6545 0.6749 0.7013 1.4146 520 500 0.5596 512.0 687.0 1199.0 0.7133 520 812.5 0.0209 0.5386 536.8 657.5 1194.3 0.7378 0.6577 1J954 540 0.0215 0.4437 0.4651 0.6132 1.3757 560 540 962.8 562.4 625.3 1187.7 0.7625 0.0221 0.3651 0.J871 1.3550 580 SE0 1133.4 0.3222 589.1 589.9 1179.0 0.7876 0.5673 580 1326.2 0.0228 0.2994 550.6 1167.7 0.8134 0.5196 1.3330 FAO 0.2438 0.2675 617.1 600 1543.2 0.0236 646.9 506.3 1153.2 0.8403 0.46S9 1.3092 620 0.0247 0.1962 0.2208 0.4134 1.2621 640 620 1786.9 679.1 454.6 1133.7 0.8666 2059 9 0.0260 0.1543 0.1802 0.3502 1.2498 660 640 714.9 392.1 1107.0 OA995 0.0277 0.1166 0.1443 1.2086 680 640 2365.7 g 0.1112 758 5 310.1 1060.5 0.9365 0.2720 640 2708.6 0.0304 0.0608 822.4 172.7 995.2 0.9901 0.1490 1.1390 700 3094.3 0.0366 0.0386 0.0752 0 1.0612 705.5 7C0 906.0 0 906.0 1.0612 0.0508 0 0.0508 705.5 3208.2 I
TABLE A.2 PROPERTIES OF SATURATED STEAM AND SATURATED WATER (TEMPERATURE)
A.3 l
I
I l
l l
EMha9y. Stu/lb EMropy Stu/it a F Eq. Stufig Voivme. ft'/tb P5ees.
Temp g,,, gg,,, g g,, Lymp Steam Water Evap Steem Water Steam pele Press. ,,,,,
P638 I A A s, sg s, e, y Af ls s
', 'q, 's 0.00 1075.5 1075 5 0 2.1872 2.1872 0 1021.3 e.Ose6 32.016 0.01602 3302.4 33024 e.0446 3 03 10738 10768 0 0061 2.1705 2.1766 3A3 1022.3 e.10 0.01602 2945 5 2945.5 13.50 1025.7 e.15 e.10 35.023 0.01602 2004.7 20047 13.50 1067.9 1081.4 0 0271 2.1140 2.1411 0.15 45.453 21.27 1063 5 1084 7 0 0422 2.0778 2.1160 21.22 1028.3 0.20 53.160 0.01603 1526.3 1526.3 32.54 1032 0 0.30 E20 32.54 1057.1 1089 7 0.0641 2.0155 2.0009 e.30 64 484 0 01604 1039.7 1039.7 ' 40.92 1052.4 1093.3 0.0799 1.9762 2.0562 40.92 1034.7 0.40 0.01606 792.0 792.1 e,40 72.869 47.62 1048 6 1096.3 0.0925 1.9444 2.0370 4742 1036.9 S.5 79.586 0.01607 641.5 641.5 53.24 1038.7 0.6 0.5 540.2 53.25 1045 5 1098.7 0.1028 1.9186 2.0215 e.6 85.218 0 01609 540.0 0.3 1.3966 2.0083 58.10 1040.3 0.7 0.01610 466.93 466 94 SS 10 1042 7 11008 0.4 e.7 90 09 62.39 1040.3 1102.6 0.1117 1A775 1.9970 42.39 1041.7 OA 94.38 0.01611 41147 41149 6624 1042.9 at SES 43 46.24 1038.1 1104.3 0.1264 1A606 1.9870 0.9 98.24 0.01612 368.41 69.73 1036.1 1105.8 0.1326 1A455 1.9781 69.73 1044.1 1.0 0.01614 333 59 333 60 2A 1.0 101.74 173.74 173.76 94.03 1022.1 1116.2 0.1750 1.7450 1.9200 94A3 10512 2.0 126.07 0.01623 0.2009 1.6854 1.8864 109.41 1056.7 8.e 141 47 0.01630 118.71 118.73 109.42 1013.2 1122.6 4.0 3.0 120.92 1006.4 1127.3 0.2199 1.6428 1A626 120.90 1060.2 4.0 152.96 0.01636 90 63 90 64 SA 73.515 73.53 130.20 1000.9 1131.1 0.2349 1.4094 13443 130.18 1063.1 8.0 162.24 0.01641 138 03 996.2 1134.2 O_2474 1.5820 1A294 138A1 1065.4' EA 4.0 170.05 0A1645 41.967 61.98 7A 53 634 53.65 144.83 992.1 1136 9 0.2581 1.5587 1A168 14431 1067.4 7A 176 84 0.01649 0.2676 1.5384 1A060 15034 1089.2 SA 142.86 0.01653 47.328 47.35 150.87 988.5 1139.3 Ss0 188.27 0.01654 42.385 42.40 156.30 985.1 1141.4 0.2760 1.5204 1.7964 156.28 10704 9.C.
9.0 193.21 0.01659 38.404 38 42 161.26 982.1 1143.3 0.2836 1.5043 1.7879 16L21 1072.3 le 10 212.00 0.01672 26.782 26.00 180.17 9703 1150.5 0.3121 1.4447 1.7568 130.12 1077.6 14AS6
! 14.496 969.7 1150.9 0.3137 1.4415 1.7552 181.16 1877.9 15 0.01673 26.274 26.29 131.21 15 213.03 19621 1m2A 30 20.070 20.087 196.27 960.1 1156.3 0.3358 1.3962 1.7320 20 227.96 0.01683 13.7266 13.744 218.9 945.2 1164.1 0.3682 1.3313 1AB95 2143 137.9 30 30 250.34 0.01701 236A 1082.1 40 10.4794 10.497 236.1 933.6 1169A 0.3921 1.2844 1.6765 40 267.25 0.01715 8.4967 S.514 250.2 923.9 1174.1 0.4112 1.2474 JA586 250.1 INL3 to 50 281.02 0.01727 0.01738 715C2 7.174 262.2 915.4 1177.6 0.4273 1.2167 1A440 282A 10SSA GB 60 292.71 907A 1130.6 0 4411 1.1905 1A316 272.5 1100J 70 0.01748 6.1875 6205 272.7 80 70 302.93 900.9 1183.1 0.4534 1.1675 1A208 291.9 1102.1 j
0.01757 5 4536 5.471 232.1 90 So 312.04 894.6 1185.3 0.4643 1.1470 1A113 290.4 1103.7 0.01766 4.8777 4.895 290.7 to 320.29 088.6 1187.2 0.4743 1.1284 1.4027 298.2 1105.2 100 0.01774 4.4133 4.431 298.5 100 327A2 0.01789 3.7097 3.728 312.6 8772 1190.4 0.4919 1A960 1.5879 312.2 1107.6 120 l 120 341.27 0 01803 3 2010 3 219 325.0 368.0 1193.0 0.5071 1.0681 1.5752 324.5 1109.6 140
' 140 353 04 0.01815 2.8155 2.334 336.1 859.0 1195.1 0.5205 1.0435 1.5641 335.5 1111.2 180 363 55 850.7 1196.9 05328 1.0215 1.5543 3454 1112.5 180 160 0.01827 2.5129 2.531 346.2 180 373 08 842A 1198.3 0.5438 1.0016 1.5454 3543 1113.7 aos l
0 01829 2.2683 2.287 355.5 t 200 351 40 1A432 376.1 825.0 1201.1 0.5679 0.9585 1.5264 375.3 1115A 250 250 400,97 0.01865 1.8245 392.9 1117.2 300 0 01889 1.523S 1.5427 394 0 806.9 1202.9 0.5682 0.9223 1.5105 300 417.35 794 2 1204 0 0 6055 08909 1.4968 408.6 1118.1 350 0 01913 1.3064 1.3255 409.3 400 350 421.73 424.2 780 4 1204 6 0.6217 0.8630 1.4847 422.7 1112 7 400 44440 0.0193 1.14162 1.1610 435.7 1118.9 450 0 0195 1.01224 1.0318 437.3 767.5 1204.8 0.6360 04378 1.4738 450 4M.28 755.1 1204 7 0.6490 0.814S 1.4639 447.7 1118A 900 0 0196 0 90787 09276 449.5 5M ~ 46701 460.9 743.3 1204 3 0.6611 0.7936 1.4547 458.9 1118 6 550 550 47494 _00199 0 82183 0.8418 469.5 111E.2 Eco 400 44523 10201 0.74962 0.7698 471.7 732.0 1203 7 0.6723 0 7738 1.4461 710.2 1201.3 0.6928 0.7377 1.4304 488.9 1116.9 700 700 .503 08 0.0205 0.63505 0.6556 491.6 800 689.6 1199 4 0.7111 0.7051 1.4163 $5.17 1115.2 803 514 21 0 0209 0.54809 0.5690 509.8 0 7279 0.6753 1.4032 523.7 1113.0 900 0.02i2 0 4796s 05009 526 7 669 7 1196 4 1000 900 Si345 650 4 1192.9 0.7434 0.6476 1.3910 5316 1110.4 ,
1000 8544.53 0.0216 0 42435 04460 542.6 1100 -
0 37503 0 4006 557.5 631.5 11891 0 757S 0.6216 1.3794 5531 1107.5 1100 l 555.2d 0.0220 07714 0.5%9 1.3653 566 9 1104.3 1200 1200 e g67.19 0 0223 0 340!3 0.3625 571.9 613.0 1184 8 1300 0 0227 0 30722 0.3299 585.6 594.6 1180 2 0.7843 0.5733 1.3577 580.1 1100 9 1300 57142 517,07'8BC 0231 0778/1 0 3018 598 8 5765 1175.3 0.7966 05507 1.3474 592.9 1037.1 1400 14C0 1%0 0 0235 025372 0.2772 611.7 $50 4 !!70 1 0.8035 0 ?253 1.3373 605 2 1093.1 1500 2000 5 % 20
- 635.80 0.02'7 0162% 0 1883 672.1 465.2 1133.3 0 8625 0 4256 1.7841 662.6 106S6 2000 2500 0 0266 010209 0 1307 731.7 361.6 1093 3 C.9139 0 3206 1.2345 718.5 1032.9 2500 65d.11 973.1 3000 3000 695.33 0 0343 0 050/3 0.0850 801 8 218.4 1070 3 0 9723 01891 1.1619 782 3 0 906 0 1.0612 0 1.0612 875.9 875.9 370s.
32082 70M7 00*03 0 0 050d 906 0 TABLE A.3 PROPERTIES OF SATURATED STEAM AND SATURATED WATER (PRESSURE)
A.4
T*** 'EF mm 700 a00 900 1000 1100 1200 1300 3400 33ag D/s4 8L 3 300 400 900 a00 (sa4asapf 100 200 511.9 571.5 631.1 690 7
, 0 0161 3925 452.3 3 4 65 00 1150 2 11951 1241 8 1288 6 13361 1384 5 (10134) s 0.1295 20609 2.1152 2.1722 J.2237 22708 2.3144 e 0.0161 78.14 90.24 102.24 114.21 126 15 138 08 150 03 161.94 173 86 185 7s 197.70 209 62 1148A 1194 8 1241.3 1288 2 1335 9 1384 3 1433 6 1483 7 1534.7 1586 7 1639 6 1693 3 17440 Ig33 $
6 4 68 01 (162.24) s 0.3795 1A716 1.9369 3.9943 2.0460 2.0932 2.13G3 2.lH6 2 2159 2 2521 2.2466 2.3194 2.3509 2 38 84 44 95 51.03 57.04 63.03 69 00 74 98 30 94 36 91 9287 94 34 104 to 110.76 116 72 e 00161 to 6 68 02 1146 6 11937 1240 6 1287J 1335.5 1364 0 14334 1453 5 1534 6 ISM 6 1639 5 1693.3 1 (197.21) s 0.1295 1.7928 13593 1.9173 1.9692 2.0166 2.0603 2.1011 2.1394 2.1757 2.2101 2.2430 2.274 e 0.0161 0.OlM 29JB99 13.M3 37.985 41.986 45.978 49 964 53 946 57.926 61.905 65.882 69455 73A33 3s a 68.04 14809 1192.5 1239.9 12s7.3 1335.2 13838 1433.2 1483 4 1534.5 1506.5 1639 4 les3J 17473 1e0 (213.03) o 0.1295 0.2940 1A134 1A720 1.9242 1.9717 2A155 2.0563 2AS46 2.1309 2.1653 2.1982 2.2297 2.2599 2
, 0.0141 0.0166 22.356 25.428 28.457 31.466 34.465 37.458 40 447 43 435 44 420 49.405 52.385 55.370 30 4 65.05 les 11 1191.4 1239.2 1206.9 1334.9 1383 5 1432.9 1483.2 15343 1586.3 1639.3 1693.1 17472 (227.96) s 0.1295 0.2940 1.7005 1A397 1A921 1.9397 1.9836 2.0244 2.0628 2AD91 1.1336 2.1465 2.1979 2.2282 s 0 4161 0 0164 11.035 12.624 14.165 15 685 17.195 18.699 20 199 21 697 23.194 24.639 2Els3 27AM 40 m 68.10 168.15 1186 6 1236A 1285.0 1333.6 1382.5 1432.1 1482.5 15333 15852 163BA 1992 7 1747 (267.25) e 0.1295 0.2940 1.6092 1.7608 1A143 13624 1.S065 1.9476 1.9060 2.0224 2.0549 2.0099 2.1224 2.1 7.257 8.354 9.400 10.425 11.438 12.446 13A50 14.452 15.452 1&d50 17A48 18,445 19.441
, 0.0161 0.0156 40 a 48.15 168 20 1181 6 1233.5 1283.2 1332.3 1381.5 1431 3 1481.8 1533.2 1505J 1638.4 18e2.4 17 (292.71) s 0.1295 0.2939 1.6492 1.7134 1.7641 13168 13612 1.9024 1.9410 1.9U4 2A120 2.0450 2A765 2.10 i
e 0.01'61 0 0166 0.0175 6.218 7.018 7.794 8.560 9319 10.075 10 829 11.581 12.331 13ABI 13329 14.577 1233.5 1281.3 1330.9 1380.5 1430.5 1481.1 1532 6 1584.9 163EA legEA 17464 1302.5 30 6 64.21 168.24 269.74 (312.04) s 0.1295 0 2939 0.4371 1.6790 1.7349 1.7842 1A289 14702 1.9039 1.9454 1.9000 2.0131 2A446 2AF50 e 0.0161 0.0166 0.0175 4.935 5.588 6.216 4233 7.443 S.060 8455 9.258 SJB60 18A60 11 AID 11A99 100 h 44.26 168.29 269 77 1227.4 1279.3 1329.6 1379.5 1429.7 1480.4 1532.0 1584.4 1437A 1891A 174E5 1 14516 1.708S 1.7586 13036 1A451 1A339 1.9205 1.9552 1.9383 2A199 2ASSE 2.
(327A2) e OL1295 0.2939 0.4371 e 0.0161 0.0166 0.0175 4 0786 4.6341 5.1637 5.6C31 6.192S 6.7006 7.2060 7.7096 S.2119 S.7130 9.2134 9.
120 4 48.31 les 33 269 51 1224.1 1277.4 1328.1 1378.4 1428.8 1479 8 1531A 1583.9 1837.1 18D1J 1746.1 1 (341.27) e 0.1295 0.2939 0.4371 1.6286 1.6872 1.7376 1.7829 1A246 13635 1.9001 1.9349 1.9600 1.9996 2.0300 2 3.4661 3.9526 4.4119 4A585 5.2995 5.7364 E1709 E4036 7.0349 7Ag52 7A948 8.3233 o 0.0141 0 0166 0 0175 140 6 68.37 165 38 269 85 12208 1275 3 1326.8 1377.4 1428.0 1479.1 1530.8 15834 16361 1890.9 1745.9 (353 04) s 0.1295 0.2939 04370 1.6085 1.6686 1.7196 1.7652 1.8071 13461 1.8828 1.9176 1.9508 1.9825 2Al29
, 0.0161 0 0166 0 0175 3.0060 3 4413 3.8430 4.2420 4.6295 5.0132 5.3945 5.U41 6.1522 6.5293 '4.9056 100 n 68 42 168 42 269.89 1217.4 1273.3 1325.4 1376.4 1427.2 1478.4 1530.3 1582.9 1636.3 1990.5 1746 (363.55) s 0.1294 0.2938 0.4370 1.3306 1.6522 1.7039 1.7499 1.7919 1A310 1A678 1.9027 1.9359 1.9676>.1.93 e 0 0161 0 0166 0 0174 2 6474 3.0433 3.4093 3.7621 4.1084 4.4505 4.7907 5.1289 5.4657 SA014 11363 180 h 6847 168 47 264 92 12139 1271.2 1324.0 1375.3 1425.3 14U.7 15297 1582.4 1635.9 1990.2 17453 (373 081 s 0.1294 0.2538 0 4370 1.5743 1.6376 1.6900 1 7362 1.UB4 1.8176 15i45 1JIS94 1.9227 1.9545 1.954 e 0 0161 0 0166 0 0174 2 3598 23247 3.0583 3.3783 3 6515 4.0006 4.3077 4.6128 4.9165 5.2191 5320 200 a 6832 108 51 269 96 1210 1 1269.0 1322.6 1374.3 1425.5 14U.0 1529 1 1551.9 1635.4 1609 8 1745 (331A0) s 0 1294 0 2938 04359 1.5593 1A242 1.6MG 1.7239 1.7653 13057 1A426 1.SU6 1.9109 1.9427 1.9732
~
2.1504 2,4662 2.6G72 2.9410 3.1909 3.4382 3.6337 3 3278 4.1709 4.4131 4.6544 e 00161 0 0166 0 0174 0 0186 250 a 68.66 16863 270 05 3/5.10 1263.5 1319.0 1371.6 1423 4 1475.3 1527.6 1580.6 1634.4 1688.9 1744.2 (400 97) e 0.1294 0.2937 0 4368 0.5567 1.5951 1.0502 1.6976 IJ405 IJE01 1.8173 13524 1.8458 1.91H 1.9402 1.9 e 0 0161 0 0165 C J174 0.0186 1.7665 2.0344 2.2263 2.4407 2.6509 2 5585 3 0643 3.2588 3.4721 34746 3 300 m M 79 1M 74 27u lo 375.15 1257 7 13152 1368 9 1421.3 1473.5 1526.2 1579.4 1633 3 1688 0 1743 4 17 1417.35) s 0.1294 02937 0 4737 C5665 1.5703 1.6274 1.6753 1J192 1.7591 IJS64 1A317 1A652 1A972 1.9278 1.9 e 0 0161 0 0106 0 0174 0 018G l.4913 1.7028 1.S971 2.0332 2.2652 2 4445 2.6219 2.7950 2.9730 3.1471 3.
350 6 08t90m l&S 85 270 74 375.21 1251.5 1311.4 13662 1419.2 1471.8 1524.7 1578.2 1632.3 1687.1 1742A 17 (43133) = 01293 0 2935 043G7 0.5664 1.5483 3.6077 1.6571 IJ009 13431 1.7787 1.8141 1A477 1J795 1.9105 1.940 e 0 0161 0 0106 0 0174 0 0162 12841 1.4763 1.6499 1.0151 1.9759 7.1339 2.2901 2A450 2.5987 2.7515 2.90 400 a 69 05 168 97 270 33 375.27 1245 1 1307.4 1363 4 1417.0 14701 1523 3 1576.9 1631.2 1686.2 1741.9 179 (444 60) s 51293 0 2935 0 43M 0 5663 1.5282 1.5T01 1.6405 1.6850 1.7255 13632 1J988 1.3325 1J647 1A955 1.925 e 00161 0 0106 0 0174 0 0186 0 9919 1.1584 13037 1.4397 1.5708 1 6992 1A256 1.9507 2.0746 2.1977 2.3200 500 h 09 32 1t919 270 51 375 38 1231.2 1239.1 1357.7 1417 7 1466 6 1$20 3 1574 4 1629.1 1684 4 1740 3 179 (457.01) s 0 1292 0 2934 04354 O u6o 14971 1 5593. 1.6123 1 65/8 1.6990 1.7371 13730 1.8069 1A393 14702 IJ994 1
I TABLE A.4 PROPERTIES OF SUPERHEATED STEAM AND COMPRESSED WATER (TEMPERATURS AND PRESSURE)
A.S
'-- Ternperature, F Abe pose.
Inh & 400 500 600 700 800 900 1000 1100 1200 1300 3400 3g00 100 200 300 Jest.essel e 0 0161 0 01M 0 0174 0 0186 0 7944 0 9456 10726 1 1892 1.300s 1 4093 1 5160 1 6711 13252 182s4 1.9309 1215 9 1290 3 1351 8 1408 3 1463 0 1517 4 15789 1627.0 1642 6 17348 1795 6 Gee & 69 54 169 42 270 70 375 49 14590 1.5329 15844 1.63b1 1 6769 1.7155 17517 1.7e59 IAlse 1 3494 1.3792 (406.20) s 0.1292 02933 04362 0.% 57 0 7978 0 9072 1.0102 1,1078 1 2023 1.2948 1.3e58 3.4757 1 % 47 16530 e 0.0161 0 0364 00174 00186 0 0704 1781 0 1345 6 14033 1459 4 1514 4 15694 1624 8 1660 7 37372 3794 3 7eo n 69 84 149.65 27009 375 61 487 93 1.5090 1.5673 16154 1.6580 1.6970 1 7335 1.7679 1 00 % 1alla 18617 (503 Cs) s 0.1291 0.2932 04360 0 % 55 0 6889 0.6774 0 7025 0.0759 0 % 31 1 0470 1.1289 1.2093 1.2335 13gg 1.4446 e 0 0161 0 0166 0 0174 0 0186 0 0204 10.11 169 88 271.07 375 73 487As 1271.1 1339 2 1399.1 1455R 1511 4 15 % 9 16227 1678 9 1715 0 1792.9 See a 1.4669 1.5484 1.5580 1.6413 1 6807 13175 1 7522 13551 18164 1.8464 (513.2.). 0.1290 0 293C 0.4350 0. % 52 0.6865 0 5869 0 6858 0 7713 0 8504 0.9262 0 9996 1 0720 1.1430 1.2131 1.2325 e 0.0161 0.01 % 0 0174 0 0186 0 C234 ges a 70.37 170.10 271.26 375A4 487.83 1.4659 1260 6 13323 1394 4 1452 2 15065 15644 M20 6 16U 1 17341 1791 6 0.1290 0.2929 0.4357 0. % 49 0.6881 15311 15522 14263 1.662 13033 1.7382 1.7713 1.8028 18329 (531.95) s e 0.0161 0.0146 0.0174 0 0186 0 0204 0 5137 0 6050 0.6875 0.7603 0 4295 0.4966 0.M22 1.0966 1.0901 1.1529 lege 6 70.63 170 33 271.44 375.96 487.79 1249.3 1325.9 13894 1448.5 1504.4 1%I.9 1618 4 1675.3 1732.5 1790.3 1.4457 1.5149 1.5477 1.6126 1.6530 1.6905 1.72 % 1.7509 1.7905 1A207 (544.56) a 0.1289 0.2928 0.4355 0.5647 0.6476 e 00161 0.0166 0.0174 0.0385 0 0203 0 4531 0 5440 0.61E3 0 6865 0.7505 0 8121 0 8723 0.9313 09894 1.0468 1237.3 1310 3 1334 7 1444 7 1502.4 1559.4 1616 3 1673.5 1731.0 !?89.0 .
1100 4 70 90 170. % 271.63 376.08 487.75 1.4259 1.4995 15M2 3.0000 1.6410 1.6787 1.7141 IJ475 1.7793 1A007 (556.231 s 0.1289 0J927 0.4353 0. % 44 0.6872 e 0 0161 0.0166 0.0174 0.0185 0.0203 0.4016 04505 0.5615 0.G250 0.6845 0 7418 C.7974 0 8519 0.9055 0.9584 71.16 170.78 271A2 376.20 487.72 12242 1311.5 13791 1440.9 1449 4 15 %.9 1614.2 1671.6 1729.4 1787.6 .
1300 6 1.40G1 1.4351 1.5415 15683 1.6293 1.6679 13035 1.7371 1.7601 IJDOS .
(567.19) s 0.1288 0.2926 0.4351 0.5642 0 4363 Q3176 0.4059 0.4712 0.5282 0.5809 0.6311 0.6798 03272 E7737 08195 e 0.01(,1 0.0166 0.0174 0.0185 0 02C3 1194.1 1296.1 1369.3 1433 2 1493.2 1551.8 1609.9 1668.0 1726.3 1785.0 ,
14e0 a 71.48 171.24 272.19 376 44 487.65 1.3652 1.4575 1.5182 1.5670 1.6096 1.6484 1.6845 1.7185 1.753 1JS15 (587A7) s 0.1287 0.2923 0.4348 0.5636 0.6859 i 03415 0.4032 0.4555 0.5031 0.5482 0.5915 0.5336 0.4748 0,7153 e 0.0161 0.0166 0.0173 0.0185 0.0202 0.C236 1600 4 72.21 171.69 272.57 376 69 487.60 616.77 1279.4 1355.5 1425.2 1486.9 1546.6 1605.6 1864.5 1723.2 17323 1
1.C12 1.4963 1.5473 1.5916 1.6312 1.6678 1J022 1.7344 1.7657 (60LS7) s 0.1206 02921 0.4344 0.M 31 0.6851 0.8129 e 0.0160 0.0165 0 0173 0.0185 0 0202 0.0235 0.2005 C.3500 03968 0 4426 0.4436 0.5229 0.5409 0.5900 0 6?63 '
1800 a 72.73 172.15 272.95 376.93 48755 615.53 1261.1 13472 1417.1 1480.6 1541.1 1601.2 166R7 1720.1 Int.7 '
1.40M 1.476C 1.5302 1.5753 1.6156 1A528 1.6876 1.7204 1J516 4621/J2) s 0.1284 0.2918 0.4341 0.5626 0.EW3 0.8109 e 0 0160 0.0165 0.0173 0.0154 0.0201 0.0233 0.2483 0 3072 0 3534 0.3942 0 4320 0.4600 OL5m7 0.5365 0.5895 73.26 172.60 273.32 377.19 487 53 634.48 1240.9 1353.4 1408 7 1447.1 1536.2 1596.9 1657.0 1717.0 1777.1 l
2000 6 l 1.3794 1.4578 1.5138 1.5603 1.6014 14391 1.6743 IJ075 1.7389 t635 80) s 0.1283 0.2916 0.4337 0 5621 0.6834 0A091 e 0.0160 0.0165 0.0173 0.0184 0.0200 0.0230 0.1681 0.2293 0.2712 0.3068 .0.3390 0.3692 03900 0.4259 0.4529 2500 6 74 57 173.74 274.27 377 82 487.50 612.08 1176.7 1303.4 1326.7 1457.9 1522.9 1545.9 16472 1709.2 1770.4' 1.207G 1.4129 1.4766 1.5259 1.5703 1.6094 1.4466 .1.6796 1.7116 (448.11) s 0.1280 0 2910 0.4329 0.5609 04315 02043 e 0 0160 0 0165 0.0172 00183 0.0200 0.0223 OCG32 0 1755 02161 0.2484 0.2770 0.3033 0.3282 0.3522 0.3753 3000 h 7583 17e88 27522 378.47 487.52 G10.03 10h0.5 12670 1353.2 1440.2 1503.4 1574.8 1615.5 1701.4 17t1.8 (69'.33) s 0.1277 0.29c4 0.4320 0.5597 0.6724 02009 1.1MS 1.3592 1.4429 1.4975 1.5434 1.5841 1A21' 1 4 :61 1.6488 e 0 0160 CoI65 0.0177 0.0183 0.0199 0.0227 0.0335 0.15ES 0.1587 0.2301 02576 0 327 03065 0.3291 0.3510 3200 A 76.4 1753 275 6 378.7 487.5 034 COD.S 1250 9 1353.4 1433.1 1503.8 1570.3 16342 1698.3 1761.2 1.3515 1.4300 1.4 46 1.5335 1.5743 1A126 1 A477 1.8006 f705.041 a c1276 0 2902 0.4317 0.5592 0.6703 DJ%4 0.9703 e 0 0160 3 0164 0.0172 0.0123 0 0199 0.0225 0.0207 0.13i4 0.1K4 0.2056 0.2326 01553 0.2784 02995 0.31 3500 a 77.2 176.0 276.2- 379.1 sS7.6 603.4 779.4 1224 6 1333.2 1422.2 1455.5 15633 1629.2 1693.6 1757.2 s 0.1274 02899 0.4312 0 5555 0.6777 03973 0.950S 13242 1A112 1.4709 1.5194 1.5618 1.6032 1A358 1.64 e 3 0159 0.0164 0.0172 0.0182 0.0193 0 0223 00207 0.1052 0.1453 0.1752 0 1994 0.2210 0.2411 0.2601 0 4000 6 73.5 177 2 277 1 379.8 437.7 6C4.5 732.0 1174.3 1311.6 1403 G 1431.3 1552.2 1619.8 16853 1750 6 s 01271 0.2e93 0.4304 05573 0.6760 0 7940 0.9343 12755 1.;007 I.4461 1.4976 1.5417 1.5812 1.6177 1.6516 e 0 0159 0 0164 0 0171 0 0181 0.0193 0 0219 0.0253 0.0131 0.1033 0.1312 0 1529 0.1718 01690 0.2050 0.2 5000 a 83 L 179 5 279 1 381.2 483.1 604 6 745 0 IC42.9 1252S 1364 G 1452.1 1529.1 160J9 1670.0 1737.4 a 0.126N 2861 0 4287 0.5550 0 6725 OJc80 0.9153 1.1593 1.2207 1.4001 t.4532 1.5051 ISASI 1.5863 I.621
- 0 0159 0.0163 0 0170 C.01W 00195 0.021G 0.0256 0.0337 0.0757 J.1020 0.1221 0.1391 0.1544 0.1684 0.181 6000 4 83.7 181.7 281.0 362 7 4P3 6 602 9 73G 1 E 45.1 IIS S 1323 6 1422.3 1503.9 1562 0 16S4.2 1724.2 s 0.1258 0.2670 0 4271 0.5523 0 6693 0 7025 0.9026 1.0176 1.2515 1.3574 1.4229 1.4743 1.5194 1.5593 15962 e 0.0158 0.0163 0 0170 0.01t0 0 0193 0.c713 00243 00 34 O M73 0 03 r- 0.10')4 0.1160 0.1296 0 1424 0.1542 7c00 6 86 2 184 4 233 0 334 2 ca9 3 Q17 72M GL3 1124 9 128I 7 IM22 14S2.6 1553.1 16396 1711.1 i s 01252 0 28'r9 04256 0 % 37 0 6563_0.7f 77_ 04:25
-- - . _ . 1050
_ _ , IND
, , 1.31i1
_ I MG4 1.4406 1.4533 1.53-5 1.5735 TABLE A.4 PROPERTIES OF SUPERHdATED STEAM AND COMPRESSED I WATER (TEMPERATURE MD FRZSSURE) (CONTINUED)
A.6
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.1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 17 1 THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW ANSWERS -- ROBINSON -86/09/30-VICTOR,F.
ANSWER 1.01 (2.50)
- b. Greater than or equal (0.2 pts) to 1.17 (0.3 pts) (0.5)
- 3. RCS flow 4. Rx power
- 5. AFD 6. QPTP
- 7. Rod sequencing 8. Rod overlap
- 9. Rod position (any 6 at 0.25 pts each) (1.5)
CONSIDER OTHERS ON CASE-BY-CASE BASIS
. REFERENCE HBR TS SEC 2.1; SEC 3.10.8.3 pp3.10-13,3.10-14.
ANSWER 1.02 (1.00)
- 1. Decreases 2. Increases 3. Decreases 4. Increases (0.25 each)
REFERENCE HBR RXTH Session 48 ANSWER 1.03 (2.00)
- a. Larger value since fully withdrawing rod substantially increases the flux in the area of the rod. (1.0)
- b. Value decreases since flux in the area of the rod decreases. (1.0)
REFERENCE HBR RXTH Session 35 pp3 84.
ANSWER 1.04 (1.00)
- a. At 2235 psig h-stm = 1118, h-w = 701, h-stm minus h-w = 417 (+/- 43 BTU /lbm (0.5)
- b. Increases (0.5)
REFERENCE HBR HTT & FF pp 44.
- 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 18 THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW ANSWERS -- ROBINSON -86/09/30-VICTOR,F.
ANSWER 1.05 (1.50)
- a. Increases b. Decreases a. Increases (0.5)each REFERENCE HBR HTT & FF pp226 ANSWER 1.06 (1.00)
The critical rod position taken at the proper IR level is THE SAME AS the critical rod position taken two decades below the proper IR level.
REFERENCE HBR, Reactor Theory, Sessions 20.
ANSWER 1.07 (1.00)
- a. 36 SECONDS (+/- 1sec)
- b. 21 SECONDS (+/- 1sec) (0.5)each REFERENCE HBR RXTH Session 43, pp3.
ANSWER 1.08 (1.50)
- a. True
- b. False
- c. False (0.5 each)
REFERENCE HBR HTT & FF Part B Sect 1.
ANSWER 1.09 (1.50) a.155 (Plus or Minus 4) BTU /lbm (1.0)
- b. 71 (Plus or Minus 4) BTU /lbm (0.5)
_.. ___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ )
- 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 19 THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW ANSWERS -- ROBINSON -86/09/30-VICTOR,F.
REFERENCE HBR HTT & FF Part A, chapter 2 pp85-96.
ANSWER 1.10 (1.50)
- a. Higher
- b. Lower
- c. Higher (0.5 ea)
REFERENCE HBR FMP 0125,HBR TOC (Curve Book).
ANSWER 1.11 (2.00) a Shutdown margin is the % reactivity by which the reactor is maintained or could be made instantaneously subcritical assuming the most reactive rod is fully withdrawn. (1.0)
- b. Control Rods, Xenon, Samarium, Power Defect, Boron.(any 4 at 0.25 each)
REFERENCE HBR FMP-012; HBR RXTH Session 50 TS 3.10.8 p.3.10-11a ANSWER 1.12 (1.50)
- a. 1, 5 (0.50)
, b. 3 (0.50)
I c. 5 (0.50)
REFERENCE HBR HTT & FF, pp 101-105.
ANSWER 1.13 (1.00) for 2250 psia, sat temp = 652 (+/- 2 degrees) (0.25) with Tavg = 575, Th = (Delta T=57/2) + 575=603.5 (+/- 2 degrees) (+.5)
Answer 652-603.5=48.~5 (+/- 4 degrees) (0.25)
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- 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 20 j THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW i ANSWERS -- ROBINSON -86/09/30-VICTOR,F.
REFERENCE Steam Tables, HBR SD-001.
ANSWER 1.14 (1.00)
Decay (0.5)
Burnout or Neutron Absorbtion (0.5)
REFERENCE HBR RXTH Session 37.
ANSWER 1.15 (1.00)
Flow through a venturi causes a pressure decrease in the throat area.
The high pressure side of a D/P cell is connected upstream of the throat and the low pressure side is connected at the throat. ThefifTTference in prgssure is proportf oral to the flow. (Reasonably worded answers accepted) yy of ((f (.Q G ttl2/VL REFERENCE HBR HTT & FF pp313,314.
ANSWER 1.16 (2.00)
CR1(1-Kef f1)=Cr2(1-Kef f2); 50(1-0.9)=CR2(1-0.95) Ans.100 cps Rhol=(Keff1-1)/Keffl Rho 2=(Keff2-1)/Keff2 Rho added= Rho 2-Rhol Rhol= .1111 Rho 2= .0526 Rho added= .0526(-) .1111 Ans. 0585 Delta-K per K (Partial credit for wo. J (1.0 each)
REFERENCE HBR RXTH Session 42 pp3-4.
- 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 21 THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW ANSWERS -- ROBINSON -86/09/30-VICTOR,F.
ANSWER 1.17 (2.00)
It is always negative and therefore will reduce fission rate as fuel temperature increases. (1.0)
It acts immediately to inhibit power increases. (1.0)
REFERENCE HBR RXTH Sesion 29 4
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- 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 22 ANSWERS -- ROBINSON -86/09/30-VICTOR,F.
ANSWER 2.01 (1.00)
The amount of water needed for at least 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> operation at hot standby.
REFERENCE HBR TS p.3.4-3 ANSWER 2.02 (1.00)
Condenser Hotwell Circulation Water System Waste Disposal System (0.25 each)
Condensate Storage Tank REFERENCE HBR SD-020 p.22.
ANSWER 2.03 (2.00)
Monitors R-20 and R-21 are radioactive gas monitors.(0,5) Monitor R-11 collects particulate matter (0.5) and then passes the sample on to the R-12 gas monitor.(0.5) Filter paper is not used for gas monitoring.(0.5)
REFERENCE
, HBR SD-019 p. 14,20.
i l
ANSWER 2.04 (2.00)
- a. Steam flow limiting devices in the S/G outlet nozzle chokes steam flow should a steam line break.(0.5) Each steam line contains a venturi for flow instrumentation which will provide a resistance to steam flow should a rupture occur downstream.(0.5) (1.0)
- b. Placing the control switch in the CLOSE position causes the closing solenoid valve to energize and admit air pressure to the upper volume of a double acting air cylinder, open air is vented from the lower volume and the valve closes with a spring assist. (1,0) l
\
- 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 23 ANSWERS -- ROBINSON -86/09/30-VICTOR,F.
REFERENCE HBR S0-025 p.1,2a.,9.
ANSWER 2.05 (1.00)
A leak is detected by noting an increasing temperature on the TEMPERATURE MONITORING SYSTEM for the flange leakoff connection.
REFERENCE HBR SD-001, p.6.
ANSWER 2.06 (1.50)
- a. Intermediate
- b. Source
- c. Intermediate
- d. Power
- o. Source (0.3 each letter)
REFERENCE HBR SD-010, p.6-8,13,19,22,41,42.
ANSWER 2.07 (1.00)
The delay time for injecting a portion of primary unborated water is reduced.
REFERENCE HBR SD-021 p.25 l
l ANSWER 2.08 (1.50)
- a. 1500 (+/-25) psig b. 600 to 700 psig c.130 (+/-25) psig (0.5 each) l REFERENCE HBR SD-002 p.29,30.
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- 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 24 ANSWERS -- ROBINSON -86/09/30-VICTOR,F.
ANSWER 2.09 (3.00)
- a. Trips are: High Crankcase Pressure, Engine Overspeed,LO Lube Oil Pressure,LO Jacket Water Pressure (coolant),HI Jacket Water Temperature (coolant), Overcrank(Start Failure). (any 4 at 0.25 each)
~b. 1. FALSE; 2. FALSE; 3. FALSE; 4. TRUE (0.5 each)
REFERENCE HBR SD-005 p.2,3,8.
ANSWER 2.10 (3.00)
- a. Normal supply for E-1 is 4160V Bus No.2 via Station Service Transformer 2F.(1.0) Normal supply for E-2 is 4160V Bus No.3 via Station Service Transformer 2G.(1.0)
- b. If bus voltage decreases (below 412V) (0.25) for longer then 10 seconds (0.25) the bus supply breaker trips.(0.25) Emergency Diesel Generators will auto start and pick up E-1 and E-2 loads.(.25)
REFERENCE HBR SD-016 p.27,46.
ANSWER 2.11 (1.50)
Instrument Air System, normal; Station Service Air, backup; Nitrogen, backup. (0.5each) l REFERENCE HBR SD-037 p.4,5.
ANSWER 2.12 (1.00)
- a. FALSE b. FALSE (0.5)each REFERENCE HBR SD-004 p.22. S0-027 p.6.
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- 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 25 ANSWERS -- ROBINSON -86/09/30-VICTOR,F.
ANSWER 2.13 (1.00)
Temperature, Boron Concentration, Pressure. (any two at 0.5 each).
REFERENCE HBR SD-003 p.11.
ANSWER 2.14 (2.00)
- a. Tubine is runback at 200%/ min for 1.5 seconds, stops for 30 seconds
(+.5) then repeats cycle if condition still exists (+.5) or 5% runback at 30 second intervals until condition clears.
- b. The rod position indicating system initiates the runback (+.5) as long as a dropped rod is sensed.(+.5), or OP/0T DELTA T runback.
REFERENCE HBR SD-011 p.27,28; Dwg No.5379-2760.
ANSWER 2.15 (1.00)
From MCC-5 (480V AC) (transformed to 118 Y a.c.)
REFERENCE HBR/SD-016, p.15, 29.
ANSWER 2.16 (1.00)
- a. 2 (0.5)
- b. the holdup tank. (0.5)
REFERENCE HBR SD-021 p.12,16; DWG No. 5379-685 sheet 2.
- 3. INSTRUMENTS AND CONTROLS PAGE 26 ANSWERS -- ROBINSON -86/09/30-VICTOR,F.
ANSWER 3.01 (2.50)
The undervoltage coil and trip coil for Trip Breaker A and Trip Bypass Breaker B are powered from the "A" 125 VDC Distribution Panel.(0.5) Manual and automatic trip signals deenergize the under voltage coils (0.5)which mechanically trip the A Trip Breaker (0.5) and B Bypass Breaker.(0.5) The automatic Shunt Trip Relay is deenergized at the same time which energizes the trip coil for Trip Breaker A.(0.5)
REFERENCE-HBR SD-011 p.12 & 35.
ANSWER 3.02 (1.00)
From 0% to 20% Power the S/G Level is 39% to 52%. (0.5)
From 20% to 100% Power the S/G Level is 52%. (0.5)
REFERENCE HBR SD-027 p.19 ANSWER 3.03 (2.00)
- 1. Spray Actuation, or P-Signal (0.5)
- 2. Hi Steam Flow coincident (0.5) with Low S/G pressure (0.5) or Low Tavg (0.5) (1.5)
REFERENCE I HBR SD-006 p.16.
ANSWER 3.04 (1.00)
When both Intermediate Range detectors indicate below P-6.
REFERENCE HBR SD-010 p.9.
l
- 3. INSTRUMENTS AND CONTROLS PAGE .27 ANSWERS -- ROBINSON -86/09/30-VICTOR,F.
ANSWER 3.05 (3.00)
- a. INCREASE because Tavg decreases creating a Tavg-Tref mismatch.
- b. DECREASE since NI increase creats a rate mismatch with P-NI & P-ref, if N-44 fails. If assumption is that another detector fails NO Change.
c.-N0 CHANGE since low Tc would not affect auctioneered high Tavg which is the input to Rod Control.
- d. DECREASE since a power mismatch exists between turbine power (Pref) and Reactor power. (0.75 each)
REFERENCE HBR SD-007 p.20,21, Attachment 2.
ANSWER 3.06 (1.50)
Input comes from the core outlet thermocouples,(0.3) from each RCS hot (0.3) and cold (0.3) leg wide range (0.3) RTDs and system pressure.(0.3)
REFERENCE HBR SD-001 p.28 ANSWER 3.07 (2.00)
Power Range NI 1/4(0.25) above 103% power.(0.25)
Intermediate Range NI 1/2(0.25) above 20% power.(0.25)
Overtemperature DELTA-T 2/3(0.25) above calculated setpoint.(0.25)
Overpower DELTA-T 2/3(0.25) above calculated setpoint.(0.25) ti REFERENCE HBR SD-011 p.26.
ANSWER 3.08 (1.75)
Loop 2 Hot Leg isolation valves (.25) cannot be opened (.25) unless RCS pressure is less than 465 psig (.25) and RHR Recirc to RWST (.25) is closed (.25) and RHR Pump Suction valves (.25) are closed.(.25)
REFERENCE HBR SD-002 p.13, HBR DWG 5379-1082 sheet I and 1484.
- 3. INSTRUMENTS AND CONTROLS PAGE 28 ANSWERS -- ROBINSON -86/09/30-VICTOR,F.
g ,'1 f ANSWER 3.09 (h50)
Charging pumps would slowdown,(.25) Pressurizer level would decrease,(.25)
Letdown would isolate,(.25) Heaters would deenergize,(.25) Level would cscillate around the sgtpoin .(.25) until Reactor trips on low RCS pressure. (.25) Sej4 Lm cc p /' t/ 7C, ,t(
REFERENCE HBR SD-001 p.34; SD-021 p.27,28 ANSWER 3.10 (1.00)
All positions.
REFERENCE HBR SD-004 p.8,9.
ANSWER 3.11 (1.00)
The Load Bistable provides the arming signal for the Steam Dump valves (0.5)
The Temperature Bistable will trip open the steam dump valves after they are armed.(0,5)
REFERENCE HBR SD-025 p.15.
ANSWER 3.12 (1.00) P
- a. Turbocharger lube oil pump running with output pressure (above 10 psig).(0.5)
- b. Engine Speed Control set to idle.(0,5)
REFERENCE HBR SD-056 p.12.
ANSWER 3.13 (1.50)
- a. False b. True c. False (0.5 each)
- 3. INSTRUMENTS AND CONTROLS PAGE 29 ANSWERS -- ROBINSON -86/09/30-VICTOR,F.
REFERENCE HBR S0-033 p.15.
ANSWER 3. p/ (1.00)
Acoustic accelerometers (0.5)
Temperature detectors (0.5)
REFERENCE HBR S0-001 p.35.
ANSWER 3.15 (2.00)
- a. Loss of power supply AFW Pump auto start Containment Phase A Isolation signal Loss of both Main Feedwater Pumps High radiation signal (any 4 at 0.25 each)
- b. Manual safety injection High containment pressure High DELTA pressure between any steam generator and the steam line header Pressurizer low pressure High steam flow in 2/3 steam lines coincident with low Tavg or low steam pressure Phase A containment isolation signal Loss of air Loss of electrical power Manual (any 4 at (0.25 each)
REFERENCE HBR SD-020 Section 5.0 and 5.1; S0-021 p.18: TS Tables 3.5-3 84 ANSWER 3.16 (1.50)
-PZR high water level
-PZR 10 pressure
-Lo primary coolant flow
-RCP breakers open
-Under voltage
-Under frequency
-Turbine trip ( Any 6 of 7 at 0.25 each) 1
~3. INSTRUENTS AND CONTROLS PAGE 30:
IANSWERS -- ROBINSON -86/09/30-VICTOR,F.
. REFERENCE H8R SD-011 p.24.
I
- 4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 31 RADIOLOGICAL CONTROL ANSWERS -- ROBINSON -86/09/30-VICTOR,F.
ANSWER 4.01 (1.00)
- a. Resetting the SI Signal permits manual loading of equipment on E-1 and E-2. (0.5)
- b. The Operator should refer to EPP Supplement A for a listing of those valves that should have closed and compare them to actual valve position or by checking safeguards status panel lights. (0.5)
REFERENCE HBR EPP-1 pp17, SD-006 ppil.
ANSWER 4.02 (2.50)
- a. Continuous addition of Boric Acid Solution (0.5) from CVCS,(0.25) or Safety Injection System.(0.25)
- b. Actuation of PRZ Spray,(0.3) or PORY,(0.3) Over Temperature (0.3) or Over Power (0.3) Rod Withdrawl Stop with Turbine Runback,(0.3) NI Rod Withdrawl Stop.(0.3) (any five)
REFERENCE HBR A0P-001 pp12,14.
ANSWER 4.03 (1.50)
Must monitor Component Cooling Water flow and temperature for the RCP Thermal Barrier.(0.5) Must monitor Pump Bearing temperature.(0.5)
Must monitor No.1 Seal leakoff temperature.(0.5)
REFERENCE HBR A0P-18 p.14,16.
ANSLER 4.04 (1.00)
First--Normal Spray;(0.25) Second--Aux Spray with Letdown;(0.25) Third--
PZR PORVs.(0.25) (0.25 for correct order)
REFERENCE HBR Table 1 for Path 1.
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- 4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY ANO PAGE 32 RADIOLOGICAL CONTROL ANSWERS -- ROBINSON -86/09/30-VICTOR F.
ANSWER 4.05 (1.00)
The remaining SI Pumps must be tested to ensure that they are operable.
REFERENCE HBR TS p.3.3-10 ANSWER 4.06 (3.00)
- a. RCS Subcooling greater than 25 degrees F.(0.5) Steam' Pressure stable or Decreasing.(0.5) RCS hot leg temperature stable or decreasing.(0.5)
Subcooling Monitor T/C stable or decreasing.(0.5) RCS cold leg temperature trending to or at saturation temperature for steam pressure.(0.5)
- b. Increase dumping steam.(0.5)
REFERENCE HBR EPP-4 p.12 ANSWER 4.07 (1.50)
- a. Implemented on a temporary basis following approval by two members (0.25) of the Plant (0.25) (or C&A Management) Staff,at least one must hold a SR0 license.(0.5)
- b. Not to exceed 21 days.(0.5)
REFERENCE HBR AP-004 p.28,29 ANSWER 4.08 (2.00)
Ensure adequate shutdown margin in the event of a Reactor trip.(1.0)
Ensure that the maximum possible ejected rod reactivity limits are maintained.(0.5) Ensure acceptable core power distrubition.(0.5)
REFERENCE HBR GP-003 p.11
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- 4. PROCEDURES - NORMAL, ABNORMAL, EERGENCY AND PAGE 33 RADIOLOGICAL CONTROL ANSWERS -- ROBINSON -86/09/30-VICTOR,F.
ANSWER 4.09 (2.00)
- a. Should adjust T-AVG to within plus .5 degrees F (0.25) and minus 2.5 degrees F (0.25) of T-REF (0.25) to avoid a transient after transfer.(0.25)
- b. Shift'to Manual as Turbine load decreases below P-2 setpoint(0.5)
(15% Turbine Load) since Automatic Control Rod Withdrawal is now blocked.(0.5)
REFERENCE HBR GP-005 p.6,8 GP-006 p6 ANSWER 4.10 (1.00)
Cooldown and depressurize the RCS or heatup the RCS above 350 degrees F.
-!1.0 M
( )cctt//of<Yu REFERENCE HBR OP-006 P.5 TS p.3.1-4 ANSWER 4.11 (1.50)
Start the Standby Circulating Pump;(0,5) Verify that the Standby Vacuum Pump is running;(0.5) Verify that the Conderser Vacuum Breaker Valves are closed.(0.5) Reduce turbine load if vacuum is approaching low vacuum trip.(0.5) (any three answers)
REFERENCE HBR A0P-012 p.4 SD-026 p.19 i
ANSWER 4.12 (2.00) I
- a. OSC is located in the Plant Maintenance Shop.
TSC is located in the Training, EOF /TSC Building.
E0F is located in the Training,E0F/TSC Building. (need all three 0.75)
- b. One Shif t Foreman)$RO)';(.25) Two Control Room Operators (R0 licensed)'
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(.25) Two additional Shif t Personnel;(.25) One Senior Control Operator JSR0licensef)(.25);OneShiftTechnicalAdvisor.(.2p) ul" '
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^ 4.- PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 34 RADIOLOGICAL CONTROL ANSWERS -- ROBINSON -86/09/30-VICTOR,F.
REFERENCE HBR TS p.6.2-1
\
ANSWER 4.13 (1.50)
To safely bring the Reactor Plant to a hot shutdown condition af ter a severe fire (0.75) when the use of E0Ps is precluded.(0.75)
REFERENCE HBR DSP-001 P.29 ANSWER 4.14 (1.00)
The Operating Supervisor authorizes removal of the tag.(0.25)
- The Shift Foreman approves the removal.(0.25) A functional test is performed (0.25) or the SCO,CO,or A0 verifies that the tag has been removed.(0.25)
REFERENCE HBR OMM-012 p9 ANSWER 4.15 (1.50)
- 1. Subcriticality, 2. Core Cooling, 3. Heat Sink, 4. RCS Integrity
REFERENCE HBR CSFST i
/
ANSWER 4.16 .(-1 W 'b A fourth start can not be attempted until the motor has cooled by standing idle for at least one hour.
j REFERENCE
- HBR OP-101 p.11 1
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. loi .a U. S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR. OPERATOR LICENSE EXAMINATION FACILITY: ROBINSON REACTOR TYPE: PWR-WEC3 p DATE ADMINISTERED: 86/09/30
)
uP 4)3 - ,h EXAMINER: KEITH PARKINSON ,
CANDIDATE:
INSTRUCTIONS TO CANDIDATE:
,, Use separate paper for the answers. Write answers on one side only.
> ' .-Staple question sheet- on top of the answer sheets. Points for each s
question are indicated in parentheses after the question. The passing T, grade requires at least 70% in each category and a final grade of at least 80%. Examination papers will be picked up six (6) hours after the examination starts.
% OF CATEGORY % OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY 25.00 25.51 5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND THERMODYNAMICS 25.00 25.51 6. PLANT SYSTEMS DESIGN, CONTROL,-
AND INSTRUMENTATION 23.00 23.47 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL 25.00 25.51 8. ADMINISTRATIVE PROCEDURES, 4
CONDITIONS, AND LIMITATIONS 98.00 Totals Final Grade All. work done on this examination is my own. I have neither given nor received aid.
Candidate's Signature
)
f 4 NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules apply:
- 1. Cheating on the examination means an automatic denial of your application and could result in more severe penalties.
- 2. Restroom trips are to be limited and only one candidate at a time may leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.
- 3. Use black ink or dark pencil only to facilitate legible reproductions.
- 4. Print your name in the blank provided on the cover sheet of the examination.
- 5. Fill in the date on the cover sheet of the examination (if necessary).
- 6. Use only the paper provided for answers.
- 7. Print your name in the upper right-hand corner of the first page of nash section of the answer sheet.
- 8. Consecutively number each answer sheet, write "End of Category __" as appropriate, start each category on a new page, write 2nlE 2n 2na side of the paper, and write "Last Page" on the last answer sheet.
- 9. Number each answer as to category and number, for example, 1.4, 6.3.
- 10. Skip at least three lines between each answer.
- 11. Separate answer sheets from pad and place finished answer sheets face down on your desk or table.
- 12. Use abbreviations only if they are commonly used in facility literature.
- 13. The point value for each question is indicated in parentheses after the question and can be used as a guide for the depth of answer required.
- 14. Show all calculations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or not.
- 15. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLANK.
- 16. If parts of the examination are not clear as to intent, ask questions of the examiner only.
- 17. You must sign the statement on the cover sheet that indicates that the work is your own and you have not received or been given assistance in completing the examination. This must be done after the examination has been completed.
18.- When you complete your examination, you shall:
- a. Assemble your examination as follows:
, (1) Exam questions on top.
(2) Exam aids - figures, tables, etc.
1 (3) Answer pages including figures which are part of the' answer.
- b. Turn in your copy of the examination and all pages used.to answer the examination questions.
- c. Turn in all scrap paper and the balance of the paper that you did not use for answering the questions.
- d. Leave.the examination-area, a's defined by the examiner. If after leaving, you are found in this area while the examination is still in progress, your license may be denied or revoked.
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- 5. THNORYOFNUCLEARPOWERPLANTOPERATION, FLUIDS. AND PAGE 2 IEEBMODYNAMICS QUESTION 5.01 (1.50)
A motor driven centrifugal pump is operating at a low flow condition. You then start opening the upstream throttle valve on the discharge side. How will each of the following be affected? [ INCREASE, DECREASE,OR NO CHANGE]
- a. Pump Discharge Pressure [0.5]
- b. Available NPSH [0.5]
- c. Motor Amps [0.5]
QUESTION 5.02 (2.50)
- a. How does DNBR change [ INCREASE, DECREASE, NO CHANGE] as the following are increased? [ Consider each separately].
- 1. Tavg [0.5]
- 2. RCS pressure [0.5]
- 3. RCS flow [0.5]
- 4. Reactor power [ Constant Tavg] [0.5]
- b. What adverse fuel assembly condition could result if actual heat flux exceeds the critical heat flux in a PWR core? EXPLAIN. [0.5]
QUESTION 5.03 (2.00)
- a. The plant has been operating at 100% reactor power power for several weeks. Power is reduced to 75% using rods only. What ROD MOTION would be required to maintain the plant at 75% power over the next 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> assuming no change in boron concentration? Include applicable TIME FRAMES. [1.5]
- b. The equilibrium [at power] value of samarium reactivity is
[ DEPENDENT ON or INDEPENDENT OF] power level. [0.5]
(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)
- 5. THEORY OF NUCLEAR POWER PLANT OEERATION. FLUIDS. AND PAGE 3 IHEBdQDYNAMICS QUESTION 5.04 (2.00)
- a. Does Beta bar effective INCREASE, DECREASE, OR REMAIN THE SAME from BOL to EOL? EXPLAIN your answer. [1.5]
- b. For two equivalent positive reactivity additions to a critical reactor, will the SUR be the SAME, LARGER, OR SMALLER at EOL as compared to BOL? [No explanation is necessary] [0.5]
QUESTION 5.05 (2.00)
- a. Primary system flow rate is many times greater than secondary system flow rate while the heat transferred by the two systems is essentially the same. EXPLAIN how this is possible. [1.5]
- b. Which of the following describes the changes to the steam that occur between the inlet and outlet of a real [not ideal] turbine? [0.5]
- 1. Enthalpy decreases, entropy decreases, quality decreases.
- 2. Enthalpy increases, entropy increases, quality increases.
- 3. Enthalpy constant, entropy decreases, quality decreases.
- 4. Enthalpy decreases, entropy increases, quality decreases.
QUESTION 5.06 (2,00)
Given the following, CALCULATE the required boron change to increase reactor power from 75% to 100% while maintaining constant rod position.
[SHOW WORK) [2.0]
Moderator Temperature Coefficient -15 pcm/ degree Doppler-only Power Coefficient -12 pcm/% power Void Reactivity change -25 pcm Xenon change -50 pcm Boron Coefficient -10 pcm/ ppm
(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)
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- 5. THEORY OF NUCLEAR POWER PLANT OPERATION FLUIDS. AND PAGE 4 THERMODYNAMICS QUESTION '5.07 (1.00)
The reactor.is' operating at 85% power at BOL when a steam dump valve OPENS. State what happens to the following paramters. [ INCREASES, DECREASES or REMAINS THE SAME] [ assume all control systems in MANUAL]
- a. .Tave [0.25]-
- b. Reactor Power [0.25]
- c. Steam Generator Pressure [0.25]
- d. Core DELTA-T- [0.25]
QUESTION 5.08 (2.00)
With all systems in manual and no operator action, what effect [ INCREASE, DECREASE, NO CHANGE] will decreasing the circulating water temperature have on the following?
- a. Condenser vacuum [0.5]
- b. Condensate temperature -[0.5]
- c. Steam generator pressure [0.5]
- d. Reactor power ' [io . 5]
I QUESTION 5.09 (3.00)
- a. 1. State the core PARAMETER that necessitates changing rod insertion l limits [RIL] as reactor power increases. [0.5]
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- 2. EXPLAIN why the RIL is changed as reactor power increases [1.5]
- b. A control rod, located near the center of the core, is withdrawn and inserted under the following conditions:
Condition 1. All rods are in and the rod is fully withdrawn.
Condition 2. All rods are out and the rod is fully inserted.
! Under which condition [1. or 2.] will the rod have the LARGER ROD WORTH? [1.0]
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(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)
i
, 5. THEORY OF NUCLFAR POWER PLANT OPERATION. FLUIDS.' AND PAGE g5 t
THERMQDYNAMIES-l QUESTION 5.10 (3.00)
- a. How does the initial: source range level [ cps] affect critical rod position? EXPLAIN. [1.0]
i
- b. How does the positive reactivity insertion rate affect'the source -
range count level at which criticality is achieved? EXPLAIN. -[1.0]
- c. During a reactor startup, count rate is 250 CPS with a corresponding K-eff of 0.95. The count rate increases to 500 CPS. WHAT IS THE RESULTANT K-eff? [SHOW WORK] -[1.0]
QUESTION 5.11 (2.00)
The reactor is operating at 30% power when one RCP trips'.
Assuming.
no reactor trip or turbine load change occur, indicate whether the following parameters will INCREASE, DECREASE, or REMAIN THE SAME.
- a. Flow in operating reactor coolant loops [0.5]
- b. --Core delta T [0.5]
- c. Reactor vessel delta P [0.5]
- d. Operating loop steam generator pressure ,
[0.5]-
-QUESTION 5.12. (2.00)
For.each change in the parameter listed in column A, select the correct change in Moderator Temperature Coefficient [MTC] from column B.
[ Consider each parameter' change separately]
COLUMN A COLUMN B
[ parameter change] [MTC change]
- a. Moderator temperature increases 1. More Negative [0.5]
- b. Boron concentration increases 2. Less Negative [0.5]
- c. All rods in vs. all rods out 3. No Effect [0.5]
[ temperature and boron remain the same]
- d. Flux shape shifting towards [0.5]
edge of core
(***** END OF CATEGORY 05 *****)
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- 6. PLANT SYSTEMS DESIGN, CONTROL. AND INSTRUMENTATION PAGE 6 QUESTION 6.01 (2.50)
The following concern the DIESEL GENERATORS:
- a. List two Diesel Engine COMPONENTS supplied [ cooled] by the Service Water System. [0.5]
- b. LIST five ENGINE trips. [1.25]
- c. List three GENERATOR trips. [0.75]
QUESTION 6.02 (2.00)
- a. LIST four [4] SIGNALS that cause automatic closure of the Steam Generator blowdown isolation valves. [1.0]
- b. WHAT are four CONDITIONS which cause automatic closure of the CVCS orifice isolation valves ? [1.0]
QUESTION 6.03 (1.75)
- a. WHAT are the TWO INPUTS to the Reactor Control System variable gain circuitry? [1.0]
- b. STATE the ROD SPEEDS for the following temperature deviations:
1.Tave 4.0 F above Tref [0.25]
2.Tave 6,0 F above Tref [0.25]
3.Tave 1.5 F below Tref [with Tave increasing] [0.25]
QUESTION 6.04 (1.00)
- a. HOW is complete DRAINING of the spent fuel pit via the spent fuel cooling loop lower suction line PREVENTED? [0.5]
- b. How is SIPHONING of the spent fuel pit via the spent fuel cooling i discharge line PREVENTED? [0.5]
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(***** CATEGORY 06 CONTINUED ON NEXT PAGE *****)
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- 6. PLANT SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION PAGE 7 QUESTION 6.05 (1.50)
The plant is operating at 45% power with all systems in automatic control. For each condition listed below, STATE the INITIAL DIRECTION of rod motion, and STATE the REASON for this initial rod motion.
- 1. Loop 3 Tc fails high. [0.5]
- 2. A main steam power operated relief valve fails open. [0.5]
- 3. The turbine is ramped to 100% power at 5% per minute. [0.5]
QUESTION 6.06 (1.00)
What TWO SIGNALS can cause turbine runbacks? [1.0]
QUESTION 6.07 (1.00)
Which of the following statements is CORRECT with respect to a Load Limit Reduction? [1.0]
- a. The Load Limit Reduction is a cyclic load reduction at the 200%/ min rate for 5 seconds and a 30 second wait.
- b. The Load Limit Reduction is a cyclic load reduction at the 70%/ min rate for 5 seconds and a 30 second wait.
- c. The Load Limit Reduction is a continuous load reduction at the 200%/ min rate.
- d. The Load Limit Reduction is a continuous load reduction at the 70%/ min rate.
(***** CATEGORY 06 CONTINUED ON NEXT PAGE *****)
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- 6. PLANT SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION PAGE 8 !
QUESTION 6.08 (2.50)
For the following RPS trips, LIST the SETPOINT [where applicable], required COINCIDENCE, and the BASIS for each trip.
- a. Power range high flux trip - Low setpoint [0.5]
- b. Overtemperature delta T trip [0.5]
- c. Overpower delta T trip [0.5]
- d. Steam generator Low-Low water level trip [0.5]
- e. High pressurizer water level trip [0.5]
QUESTION 6.09 (2.50)
- a. List THREE SOURCES of water that may be injected into the reactor to provide core cooling. [1.5]
- b. Give TWO REASONS for mixing the spray additive tank chemical with safety injection water. [1.0]
QUESTION 6.10 (1.00)
What is the BASIS for the Condensate Storage Tank minimum level requirement listed in Technical Specifications? [1.0]
QUESTION 6.11 (2.00)
- a. If a main steam line should rupture just prior to exiting the Containment Vessel, what TWO main steam line DESIGN FEATURES would mitigate the consequences of this accident? [1.0]
- b. DESCRIBE the EVENTS which occur to shut an MSIV when the control switch is placed in the CLOSE position. [1.0]
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(***** CATEGORY 06 CONTINUED ON NEXT PAGE *****)
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- 6. PLANT-SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION PAGE 9 QUESTION 6.12 (1.50)
With the plant at NORMAL operating conditions LIST the EVENTS that would occur if Pressurizer Level Channel 459 FAILED HIGH. Cover the period from initiation of the casualty until the plant is stable or the Reactor Trips
[1.5]
QUESTION 6.13 (2.50)
- a. Relief valves are installed in the CCW System to provide over pressure protection for the CCW System.
- 1. What is the CCW surge tank relief valve designed [ sized] for? [0.5]
- 2. What is the excess letdown heat exchanger CCW down stream relief valve designed [ sized) for? [0.5]
- b. STATE two different INDICATIONS of Reactor Coolant leakage into the CCW System [1.5]
QUESTION 6.14 (2.25)
- a. WHY is the operability of the steam generator code safety valves important during power operation? [0.5]
- b. What is the BASIS for the requirement for'the MSIVs to close during a steam line rupture? [0.5]
- c. List 4 SIGNALS that will close the MSIVs. [setpoints are not required] [1.25]
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(***** END OF CATEGORY 06 *****)
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- 7. PROCEDURES' _HQRMAL. ABNORMAL EMERGENCY AND PAGE 10 RADIOLOGICAL CONTROL QUESTION 7.01 (1.00)
The shift foreman is responsible for c3asifying events in accordance with the Emergency Action Levels [EALs]. LIST the four EALs IN ORDER of severity [with 1 being least severe and 4 being most severe] [1.0]
QUESTION 7.02 (3.00)
- a. What-are the TWO ENTRY CONDITIONS to FRP-H.1, " Response . tx) Loss of Secondary heat Sink"7 [1.0]
- b. What TWO CONDITIONS [ include applicable criteria], caused by a loss of-secondary heat sink, call for tripping the RCPs and initiating feed and bleed? [1.0]
- c. In.FRP-C.1," Response To Inadequate Core Cooling", _ what TWO system PARAMETERS [ include applicable CRITERIA] are checked to verify adequate core cooling? -
[1.0]
QUESTION 7.03 (1.00)
The plant is in the Cold Shutdown Condition conducting Refueling Operations. What are the operator IMMEDIATE ACTIONS if the R-2 containment monitor alarms 7 [1.0]
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(***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)
- 2. PROCEDURES - NORMAL. ABNORMAL. EMERGENCY AND PAGE 11 RADIOLOGICAL CONTROL QUESTION -7.04 (1.00)
During an accident. recovery procedure, the operator who has been monitoring the Critical Safety Functions reports the following information.
- a. Suberiticality - green
- b. Core cooling - orange
- c. Integrity orange
- d. . Heat sink red
- e. Containment - yellow Rank the CSFs according to their importance in numerical order.
from 1 to five. [1.0]
QUESTION 7.05 ( .00)
EPP-1, LOSS OF ALL AC POWER, operator action instructions include the statement " check if RCS is isolated". What FOUR things does the operator check to satisfy this step?-[ question deleted - see exam report]
QUESTION 7.06 (2.00)
List FOUR possible CAUSES [ excluding channel failure] for receiving a PZR PROTECTION HI LEVEL ALARM? [2.0]
QUESTION 7.07 (1.00) .
Answer TRUE or FALSE for the following statements concerning the Low Temperature Overpressure Protection System: [1.0]
j a. The Low Temperature Overpressure Protection System shall be operable whenever the RCS temperature is below 350 F and not vented to containment. [0.5]
1
- b. Operation of the Low Temperature Overpressure System to relieve a i
pressure transient must be reported to the NRC. [0.5]
(***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)
- 7. PROCEDURES - NORMAL, ABNORMAL. EMERGENCY AND PAGE 12 RADIOLOGICAL CONTROL QUESTION 7.08 (2.00)
A startup is in progress with reactor power at aprroximately 8-10%.
What are the operator IMMEDIATE ACTIONS if the turbine trips? [2.0]
QUESTION 7.09 (2.50)
Match the following column A limits with the appropriate temperature in column B. The temperature selections may be used more than once.
Column A Column B
[ LIMITS] [ TEMPERATURES]
- 1. Maximum allowable reactor coolant a. 25 degrees F [0.5]
system heatap rate limit per hour
- 2. Maximum allowable pressurizer b. 60 degrees F [0.5]
heatup rate limit per hour
- 3. The maximum allowable reactor coolant c. 100 degrees F [0.5]
system cooldown rate limit per hour
- 4. The maximum allowable temperature d. 120 degrees F [0.5]
differential between the pressurizer and the pressurizer spray water
- 5. The maximum SG pressure is limited to e. 200 degrees F [0.5]
200 psig when the RCS temperature is below this limit
- f. 320 degrees F QUESTION 7.10 (2.00)
What is the procedure for BORATION during normal operations.[ ASSUME that the total volume of boric acid required has been determined and DESCRIBE HOW you will inject the volume of boric acid into the RCS] [2.0]
(***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)
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-7 . PROCEDURES - NORMAL'. ABNORMAL. EMERGENC AND 'PAGE 13 RADIOLOGICAL CONTROL QUESTION 7.11 (1.00)
-A normal plant startup from hot shutdown to critical is being conducted in accordance with GP-003.
ja. what is the MAXIMUM allowed Startup Rate? [0.5]
- b. -What is the MAXIMUM allowable difference between the estimated-critical rod position and the actual critical rod position? [0.5]:
QUESTION 7.12 (2.00)
During power operation in accordance.with GP-005, Power Operation, the turbine is manually tripped for the Turbine Valve Test. What-VALVES close when the turbine is tripped for the Turbine Valve Test? -[2.0]
QUESTION 7.13 (1.00)
With the' Low-Temperature Overpressure Protection System in operation and BOTH-PORVs become inoperable, what ACTION should be initiated? [1.0]-
QUESTION 7.14 (1.50)
Under what conditions would it be necessary to use DSP-001 " Hot Shutdown Procedure Using The Dedicated / Alternate Shutdown System"? [1.5]
4 i
i-i l (***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)
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. _ , - , , . . _ - , _ . - . , _ , _ - , - _ - ~ . . , _ _ _ , . _ _ ._ . _ _ . . _ , _ _ . - - _ _ _ _ - . . - , . _ .
- 7. PROCEDURES - NORMAL. ABNORMAL, EMERGENCY AND PAGE 14 RADIOLOGICAL CONTROL QUESTION 7.15 (2.00)
When changing plant conditions from Cold Solid to Hot Suberitical at No-load Tave, it may be necessary to start and stop the Reactor Coolant Pumps at frequent intervals.
- a. If THREE starts and stops or attempted starts have been made within a two-hour period [ pumps are not running], what ACTION is required by OP-101 if it is necessary to start an RCP again? [0.5]
- b. What is the TIME LIMIT for RCP motor operation without component cooling water flow to the motor oil coolers? [0.5]
- c. HOW LONG is the Oil Lift Pump required to be running after an RCP is started? [0.5]
- d. Prior to starting an RCP, WHAT OPERATION is performed on Emergency Buses E-1 and E-2? [0.5]
i l
l l (***** END OF CATEGORY 07 *****)
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- 8. ~ ADMINISTRATIVE PROCEDURES < CONDITIONS. AND LIMITATIONS ~ PAGE 15 QUESTION 8.01 (2.00)
.The plant..is in the Cold Shutdown Condition conducting Refueling Operations.
- a. What are COLD SHUTDOWN CONDITIONS as defined in the TECHNICAL SPECIFICATIONS? [1.0]
B. What are REFUELING OPERATIONS as defined in the TECHNICAL SPECIFICATIONS? [1.0]
QUESTION 8.02 (1.50)
List the three conditions stated in the Technical Specifications which make a control rod INOPERABLE. [1.5]
QUESTION 8.03 (1.00) 101at is the Technical Specification BASIS for the following refueling operation condition?.
" ~
Movement of fuel within the core shall not be initiated prior to 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> after shutdown." [1.0]
QUESTION .8.04 (2.00)
The concentration of the boric acid solution in the Refueling Water Storage Tank must be verified once a week in accordance with Technical Specification Table 4.1.2. The chemist sampled the boron concentration on the following schedule. [All samples taken at 1200 hour0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br />s].
AUG 31 --- SEP 7 --- SEP 15 --- SEP 23 --- SEP 30
- a. Explain why surveillance time interval requirements WERE or WERE NOT exceeded on SEP 15. [1.0]
- b. Explain why surveillance time interval requirements WERE or WERE NOT exceeded on SEP 23. [1.0)
J
(***** CATEGORY 08 CONTINUED ON NEXT PAGE *****)
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- 8. ADMINISTRATIVE PROCEDURES. CONDITIONS, AND LIMITATIONS PAGE 16 QUESTION 8.05 (3.00)
The following questions pertain to Operations Management Procedure,OMM-005, Clearance and Test Request:
- a. WHAT does clearance mean? [0.5]
- b. WHAT is a test request? [0.5]
C. WHO issues station clearances? [0.5]
- d. WHO can issue a Local Clearance? [0.5]
- e. MAY equipment be operated when it is under a clearance? [0.5]
- f. WHO may cancel a clearance if a worker to whom the clearance was issued to is not available to cancel a clearance? [0.5]
QUESTION 8.06 (1.50)
- a. What is the MINIMUM TECHNICAL SPECIFICATION SHIFT COMPLEMENT during cold operations? [0.9]
- b. What is the MAXIMUM NUMBER of conscutive days an individual may work without having two consecutive days off? [0.3]
- c. WHO may authorize deviations from the overtime policy stated in the Technical Specifications? [0.3]
QUESTION 8.07 (2.50)
- a. When is a component OPERABLE? [1.0]
- b. The plant is operating at 50% reactor power. All electric buses are being supplied from their normal supplies. Diesel Generator "A" is removed from service for surveillance testing. What is the OPERABILITY STATUS of Safety Injection Pump "A"? EXPLAIN. [1.5]
(***** CATEGORY 08 CONTINUED ON NEXT PAGE *****)
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- 8. ADMINISTRATIVE PROCEDURES. CONDITIONS. AND LIMITATIONS PAGE 17-EQUESTION- 8.08 (2.00)
For the following situations, WHAT ACTIONS ARE REQUIRED 7
[ consider each situation independently]
- a. A diesel generator is loaded and can not be shutdown. The CO2 fire protection system for the diesel generator is determined to be inoperable. [1.0)
- b. The north cable vault CO2 fire protection system is determined to be inoperable. [1,03 QUESTION 8.09 (2.50)
To maintain critical operations, what electrical power is required
[without entering a Technical Specification action statement] to be operable? [2.5]-
QUESTION 8.10 (1.50)
' Administrative Procedure, AP-006, Procedure Adherence, provides for deviation from a procedure under emergency conditions. What APPROVALS and NOTIFICATIONS are required to deviate from a procedure? [your answer should include who grants the approval, time, consultations, who is notified, method of notification, and criteria for notification] [1.5]
QUESTION 8.11 (1.50)
STATE two reasons for locking a valve in position. [1.5]
(***** CATEGORY 08 CONTINUED ON NEXT PAGE *****)
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-8. ADMINISTRATIVE PROCEDURES. CONDITIONS. AND LIMITATIONS PAGE 18 QUESTION 8.12 (1.50)
As Shift foreman, during an. outage requiring extensive maintenance on highly radioactive-components, you determine that the situations listed in column 2 have occurred. Consider each. situation separately and SELECT the appropriate required action from column 1. [1.5]
Column 1 Column 2
[ ACTIONS] [ SITUATIONS]
- 1. advise RC Foreman or higher line a. worker received 400 rems management as soon as possible to the extremeties [0.5]
- 2. notify the NRC within 24-hours b. worker received 40 rems to the skin [0.5]
- 3. .immediately notify-the NRC c. worker may have exceeded more than 5 rem in a calendar-year
[0.5] i QUESTION 8,.13 (2.50)
Special Hazards areas are Locked High Radiation Areas in which there. exists or potentially exists whole body exposure rates in-excess of 120R/hr. LIST three Special Hazards areas in the plant. [ include'any qualifying conditions] [2.5] 1
(***** END OF CATEGORY 08 *****)
(************* END OF EXAMINATION ***************)
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- 5. :
THEORY OF NUCLEAR POWER PLANT OPERATION.' FLUIDS. AND. PAGE 19 THERMODYNAMICS
' ANSWERS --1 ROBINSON -86/09/30-KEITH PARKINSON ANSWER 5.01 (1.50)
- a. Decrease [0.5]
- b. Decrease [O.5]
c.- Increase [0'.5]
REFERENCE HBR[GPC] HEAT TRANSFER THERMODYNAMICS AND FLUID FLOW FUNDAMENTALS SECTION III-PART B CHAPTER 1 COMPONENT: PUMPS-CENTRIFUGAL [2.6/2.6]
ANSWER- 5.02 (2.50)
- a. 1. ~ Decrease [0.5]
- 2. Increase [0.5]
- 3. Increase [0.5];
- 4. Decrease- [0.5]
- b. ' Clad failure [ melting, burnout] probability is greatly increased [0.25]
because film boiling will reduce the heat-being transferred from the fuel [0.25]
[ reasonably worded answers accepted]
. REFERENCE HBR[GPC] HEAT TRANSFER THERMODYNAMICS AND FLUID FLOW FUNDAMENTALS SECTION-II PART B CHAPTER 4 AND PART C 003/000-K5.01[3.3/3.9]
i J
- - ,. ,,. . . . , - - - ~ . , . , , , _ , , , , . , , , - , . ~ - - - . - - . , , , - - . . - -
r
- 5. THEORY OF NUCLEAR POWER PLANT OPERATION. FLUIDS. AND PAGE '20 THERMODYNAMICS
~
. ANSWERS -- ROBINSON -86/09/30-KEITH PARKINSON-
' ANSWER. 5.03' (2.00)
- a. - Withdraw rods _[0.375]
for about 5 [4-6]-hours [0.375].
Insert rods- [0.375]
for the next 35 [34-36] hours [0.375]
'b. INDEPENDENT OF [0.5]
REFERENCE HBR RXTH-HO-1 SESSION 39 001/000-K5.13[3.7/4.0]
-KS.35[2.1/2.3].
' ANSWER- 5.04 (2.00)
- a. l}ver core life Pu-239 concentration increases [0. 5]-
As the Pu-239 concentration increases Pu-239 fission rate increases
-[0;5]
Pu-239 beta is less than U-235 beta; consequently beta-bar-effective DECREASES with increased Pu-239 fission rate [0.5]
~b. LARGER [0.5]
-[ reasonable wording accepted]-
i . REFERENCE 1
HBR RXTH-HO-1 SESSION 44, 47 ~
001/000-K5.47[2.9/3.4]
[1 l
. . - - - ~ - - . _ , . , _ , - _ . - - -.,_ .---- -- - ._. ~ .. - - - . _. - - ._. _.. .. , . - . - . - _ . _ . ~ . . - _ - _ .
g
?$. iMEORF OF NUC MAR POWER PLANT OPERATION. FLUIDS. AND - PAGE THERMODYNAMICS ANSWERS -- ROBINSON' -86/09/30-KEITH PARKINSON LANSWER: 5.05 (2.00)
.a. .In the secondary system there is a phase change. [0.5].
A phase change requires'a large delta h. [0.5]
With the larger delta h of the secondary,-the same heat can be-transferred with a lower' flow rate. [0.5]-
- b. -4. . [0.5].
[ reasonable wording' accepted]
REFERENCE HBR[GPC] HEAT TRANSFER THERMODYNAMICS AND FLUID FLOW FUNDAMENTALS SECTION II PART B CHAPTER 1&2 002/000-K5.01[3.1/3.4]
ANSWER 5.06 (2.00)
-Tave : 28.5 X 0.25 X -15 = -107 pcm [0.4]
Power: - 25 X -12 = -300 pcm [0.4]-
Void : - 25 pcm Xenon: - 50.pcm Total: -482 pcm [0.4]
' Boron: -482 / -10 =~ 48.2 ppm [46-51] [0.4]
Dilution [0.4]
' REFERENCE HBR RXTH-HO-1 SESSION 51 001/000-K5.28[3.5/3.8]
I t r'-' et 7 --*i--rw -
---wr ---'
.g~.- r--- -------ve - - - - - m +--- - - * - - + ~---=-- --e-- --- - - - - - - ---e - --e
( .
s- -
- 5. THEORY OF NUCLEAR POWER PLANT OPERATION. FLUIDS. AND PAGE 22 IHERMODYNAMICS ANSWERS - ~ ROBINSON -86/09/30-KEITH PARKINSON ANSWER- 5.07 (1.00)
- a. DECREASES [0.25]
- b. INCREASES [0.25]
- c. DECREASES [0.25]
- d. INCREASES [0.25]
REFERENCE <
HBR RXTH-HO-1 Session 48
[041/020]-A2.01[3.6/3.9]
ANSWER 5.08 (2.00)
- a. Increase [0.5]
- b. Decrease [0.5]
- c. Decrease [0.5]
- d. Increase [0.5]
REFERENCE HBR[GPC] UEAT TRANSFER THERMODYNAMICS AND FLUID FLOW FUNDAMENTALS SECTION II PART B CHAPTERS 1&2 039/000-A1.05[3.2/3.3]
002/000-K5.11[4.0/4.2]
F ]
4
- 5. THEORY OF NUCLEAR POWER PLANT OPERATION. FLUIDS. AND PAGE 23 IHEBdQDYNAMICS l
. ANSWERS -- ROBINSON -86/09/30-KEITH PARKINSON ANSWER 5.09 (3.00)
.a. 1. POWER DEFECT [0.5]
- 2. As reactor power increases, power defect inserts negative reactivity. [0.5]
On a reactor trip this negative reactivity is removed [0.5]
thus more negative reactivity must be available from control rods to ensure adequate shutdown margin. [0.5]
- b. Condition 1. [1.0]
[ reasonable wording accepted]
REFERENCE HBR RXTH-H0-1 SESSION 35, 50 001/000-K5.02[2.9/3.4]
001/000-K5.04[4.3/4.7]
ANSWER 5.10 (3.00)
- a. It doesn't.[0.5] The critical rod position reflects the positive
. reactivity necessary to bring the reactor critical and is independent of source magnitude.[0.5] Also accept higher initial count rate would have lower ECP [0.5] because suberitical multiplication reflects the condition of being closer to critical [0.5].
- b. The faster the rate, the lower the source range counts at criticality
[0.5]
due to the reduced time for suberitical multiplication. [0.5]
- c. CR2/CR1 = [1-Keff1]/[1-Keff2]
500/250 = 1 .95/[1-Keff2]
Keff2 = 0.975 [1.0]
[ reasonable wording accepted]
REFERENCE HBR RXTH-HO-1 SESSION 41, 42, 51, 52 001/000-KS.18[4.2/4.3]
004/000-K5.08[2.6/3.2]
F ,
- 5. THEORY'OF NUCLEAR POWER' PLANT OPERATION. FLUIDS. AND PAGE 24 THERMODYNAMICS
~
LANSWERS -- ROBINSON -86/09/30-KEITH PARKINSON ANSWER 5.11 (2.00)
- a. INCREASE [0.5]
- b. INCREASE [0.5].
- c. DECREASE [0.5]
- d. DECREASE [0.5]
REFERENCE
-HBR[GPC] HEAT TRANSFER THERMODYNAMICS AND FLUID FLOW FUNDAMENTALS i 002/000-K5.01[3.1/3.4]-
ANSWER 5.12 (2.00)
- a. 1. ~r CN [0.5]
- b. 2. [0.5]-
- c. 1. [0.5]
- d. 1. [0.5]
REFERENCE HBR[GPC]RXTH-HO-1 SESSION 26 001/000-KS.15[3.4/3.7]
-K5.26[3.3/3.6]
-K5.49[3.4/3.7) 001/010-K5.29[2.9/3.4]
r; -
- 6. PLANT SYSTEMS' DESIGN. CONTROL AND INSTRUMENTATION -PAGE 25-
- ANSWERS - -ROBINSON -86/09/30-KEITH PARKINSON ANSWER 6.01 (2.50)
- a. 1. Air-Cooler
- 2. Lube Oil Cooler
- 3. Water Jacket Heat' Exchanger [any 2, 0.:25 each]-
- b. 1. Manual
- 2. Overcrank [ Start Failure]
- 3. Overspee'd
- 4. High Crankcase Pressure
- 5. Low Lube Oil Pressure
- 6. : Low Jacket Water Pressure-
- 7. High Jacket' Water Temperature [any~5,-0.25 each]'
- c. 1. 1 Reverse Power [0.25]
2.
~
Over Current [0.25]
- 3. Over. Voltage
[0.25]
l l REFERENCE i'
HBR SD-005 DIESEL GENERATORS para. 2 .
HBR SD-004 CIRCULATING WATER, SERVICE WATER & HYPOCHLORITE SYSTEMS para, 1.
.064/000-K4.01[3.9/4.1]
', -K4.02[3.9/4.23-i l'
l r
f l
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- 6. PLANT SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION 'PAGE 26 ANSWERS -- ROBINSON -86/09/30-KEITH PARKINSON ANSWER 6.02 (2.00)
- a. 1. Loss of power supply
- 2. AFW Pump auto start
- 3. Containment Phase A Isolation signal 1
- 4. Loss of both Main Feedwater Pumps
- 5. High radiation signal [any 4, 0.25 each]
- b. 1. Manual safety injection
- 2. High containment pressure
- 3. High differential pressure between any steam generator and the steam line header
- 4. Pressurizer low pressure
- 5. High steam flow in 2/3 steam lines coincident with low Tave or low steam pressure
- 6. Manual
- 7. Loss of air
- 8. Loss of electrical power [any 4, 0.25 each]
- 1. Phase A isolation signal
- 2. Loss of electrical power
- 3. Loss of air
- 4. Manual [all 4, 0.25 each]
REFERENCE HBR SD-020 STEAM GENERATOR BLOWDOWN / WET LAYUP SYSTEM para 2.
HBR SD-021 CHEMICAL AND VOLUMS CONTROL SYSTEM para 3.
HBR TECHNICAL SPECIFICATIONS Tables 3.5-3 & 4 035/010-K4.03[2.6/2.8]
l 004/000-A3.2[3.6/3.6]
t I
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FD ,
'6. PLANT SYSTEMS DES'IGN CONTROL. AND INSTRUMENTATION' PAGE 27
- ANSWERS -- ROBINSON- -86/09/30-KEITH PARKINSON f
ANSWER. 6.03 (1.75)
- a. Output of-the nonlinear gain unit'
~
[0. 5] ~
' turbine first stage impulse pressure [0.5]
b.1. 40'spm
[0.25]
- 2. 72 spm' [0.25]
f 4 ,
- 3. O er- 6 6rd [eIther answer accepted) --- -[0.25]
REFERENCE, , .
HBR SD-007 ROD CONTROL SYSTEM Figure 4 & para 4 001/000-K6.02[2.8/3.3] .
-K4.08[3.2/3.4]
3 a-ut g.
ANSWER 6.04 (1.00)
~
- a. 'A valve'inside the spent fuel pit is closed and, locked. [0.5]
- b. A_ vacuum. breaker is installed in the.; discharge line. [0.5]
REFERENCE HBR SD-014 SPENT FUEL' PIT SYSTEM para '1.
033/000-K4.01[2.9/3.2]
~
-K4.03[2.6/2.9]
.i ,
ANSWER 6.d5 e (1.50)
- 1. Rods move IN, because Tavg is higher than Tref. [0.5]
[ '
2 '. rods' move OUT, because Tavg becomes less than Tref. [0. 5]-
- 3. Rods move OUT, because the power mismatch circuit sees turbine-power [as sensed by Pimp] increasing above Rx power. [0.5]
I t
REFERENCE HBR SD-007 ROD CONTROL SYSTEM para 2. & 4.
-016/000-A2.01[3.0/3.1]
039/000-K1.02[3.3/3.3]
045/010-K4.21[3.1/3.2]
L
P . .
-6. PLANT SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION PAGE 28
- ANSWERS -- ROBINSON -86/09/30-KEITH PARKINSON 001/000-K4.03[3.5/3.8]
ANSWER' 6.06 -(1.00) 1.-Rod' drop.NIS 3. OT delta T
- 2. Rod drop / bottom from RPI 4. OP delta T
[ reasonable wording accepted] [any 2, 0.5 pach]
REFERENCE HBR SD-011 REACTOR PROTECTION SYSTEM para 3.
045/000-4.12[3.3/3.6]
[ ANSWER 6.07 (1.00)
C. [1.0]
REFERENCE HBR SD-011 REACTOR PROTECTION SYSTEM para 3.
045/000-4.12[3.3/3.6]
ANSWER 6.08 (2.50)
-Setpoint Coincidence Basis
-a. <25%[24%] 2/4 protection for power excursions beginning from low power during.a start up
- b. variable 2/3 protection again'st DNB
- c. variable 2/3 protection against exceeding Linear Power Rating [KW/ft]
- d. >16% 2/3 Ilt $/Ik-
'{#'}Protectsagainstlossof.feedwaterflow
' accident [or loss of heat sink]
' lp c/'"
- e. <G2%[91%] 2/3 Protects pressurizer safety valves against water relief
[0.1 for setpoint, 0.1 for coincidence, 0.3 for basis]
REFERENCE HBR TECHNICAL SPECIFICATIONS 2.3 HBR.SD-011 REACTOR PROTECTION SYSTEM para 3.
012/000-K4.02[3.9/4.3]
a
' ' ' ' ' ' ' ' - . ___._-._____m_ _ _ _ _ - . _ _ _ . _ _ _ _ _ _ _ _ _ - _ _ _ _ _
r . ,
- 6. PLANT SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION PAGE 29 ANSWERS -- ROBINSON -86/09/30-KEITH PARKINSON ANSWER 6.09 (2.50)
- a. 1. Refueling water storage tank [0.5]
- 2. Accumulators [0.5]
- 3. Containment vessel sump [0.5]
[or other reasonable sources]
- b. 1. Remove free iodine from the containment vessel atmosphere [0.5]
- 2. Prevent chloride stress corrosion of stainless steel piping and components in the containment vessel following SI initiation [0.5]
[ partial credit will be given for other appropriately phrased-answers such as control ph in containment]
REFERENCE HBR SD-002 SAFETY INJECTION para 1. & 2.
006/030-K4.02[3.4/3.8]
026/020-K4.01[2.8/3.2]
ANSWER 6.10 (1.00) .
The amor.nt of water needed for at least 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> operation at hot standby
[1.0]
REFERENCE HBR TECHNICAL SPECIFICATIONS page 3.4-3 061/000-K4.01[3.9/4.2]
9 e
- 6. PLANT' SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION PAGE 30
. ANSWERS -- ROBINSON -86/09/30-KEITH PARKINSON ANSWER 6.11 (2.00)
,a. 1. steam flow limiting devices in the-S/G outlet nozzle chokes steam
. flow should a steam line' break [0.5]
- 2. each steam line contains a venturi'for flow instrumentation which will provide a resistance to steam flow should a rupture occur-downstream [0.5]
- b. closing solenoid valve energizes [0.25]
air pressure admitted to the upper volume of the double acting' air cylinder [0.25]
open air.is vented from'the lower volume [0.25]
valve closes.with a spring assist [0.25]
REFERENCE.
HBR SD-025 pages 1, 2a, 9 039/000-K1.01[3.1/3.2]
ANSWER 6.12 (1.50) charging pumps slowdown -
[0.25]
pressurizer level dpcreases -
letdown isolates il p ,g . l. [0.2 pressurizer heaters deenergize (( ll [0.25]-
level would oscillate-[ increase and decrease] around the setpoint [0.25]
reactor trips on low-RCS pressure [or over temperature delta T] [0.25]
REFERENCE HBR SD-001 page 34 HBR SD-021 pages 27 & 28 000/028-EA2.02[3.4/3.8]
016/000-K1.02[3.4/3.3]
-K4.03[2.8/2.9]
-A2.01[3.0/3.1]
l
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- 6. PLANT SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION PAGE 31 ANSWERS -- ROBINSON -86/09/30-KEITH PARKINSON ANSWER' 6.13 (2.50)
- a. 1. The surge tank relief is sized to relieve maximum ' flow from a ruptured RCP Thermal-BARRIER Cooling Coil. [0.5]
- 2. The relief valve downstream-from the excess letdown heat exchanger is sized to relieve the volumetric expansion occurring if the heat exchanger shell side is isolated when cool ^and high-temperature coolant flows through the tube side [0. 5]'
- b. 1. CCW Surge Tank High Level Alarm [CCW surge tank level-increase]
- 2. CCW pump suction header radiation monitor annunciator
- 3. CCW' valve 626 [CCW return] goes shut [any 2, 0.75 each]
REFERENCE HBR SD-013' COMPONENT COOLING para 1.
000/026-EA2.01[2.9/3.5] '
ANSWER ~6.14 (2.25)
- a. Ensures that secondary system pressure will be limited to within its design pressure during the most severe transient [ loss of load]
[0.5]
[If. give answer of " maintain Tave in proper limits" then give partial-credit of 0.25]'
- b. Minimize positive reactivity effects of'RCS cooldown associated with'the rupture [0.5]
[If- give answer of " prevent more than 1 steam generator blowing down" then give partial credit of 0.25]
- c. 1. High steam flow coincident with low steam-line pressure [0.375]
- 2. High steam flow coincident with low Tave [0.375]
- 3. High-High containment pressure [0.25]
- 4. Manual actuation [0.25]
-REFERENCE HBR TECHNICAL SPECIFICATIONS 3.4 & 4.7 039/000-K6.01[2.1/2.4]
-K4.05[3.7/3.7) 000/040-SG5[3.2/4.1]
d .
05
- 7. - PROCEDURER - NORMAL. ABNORMAL. EMERGENCY AND PAGE 32; RADIOLOGICAL CONTROL ANSWERS - ROBINSON -86/09/30-KEITH PARKINSON
' ANSWER 7.01 (1.00)
L1'. unusual event [0.25]
2 . alert- ; [0. 25] '
3.' site emergency .[0.25]
- 4. general emer'gency '[0.25]
REFERENCE HBR PEP-101 para 2.1.1 PWG-36[2.9/4.7]
~
ANSWER 7.iO2 (3.00)
- a. 1. PATH-1 .[0.5]
- 2. . Critical Safety Function Status Tree [0.5]
.i
- 2. Pressurizer pressure , [0.25]
greater than 2335 psig [0.25]'
- c. 1. Subcooling Monitor T/Cs [0.5]'
- 2. At least two RCS hot leg temperatures < 350F -[0.5] '
[< 350F not required for full credit]
REFERENCE HBR FRP-H.1 page 3 HBR'FRP-C.1.page 9 000/038-EA2.07[4.4/4.8]
I i
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.. _- . . . , _ _ _ . _ . . . - - - . . _ . . . _ . ~ . _ _ . _ _ . . . _ . _ _ . _ _ . _ _ . . _ _ . . _ . _ _ . _
f '
~7. PROCEDURES - NORMAL.' ABNORMAL. EMERG2NCY AND PAGE -33 RADIOLOGICAL CONTROL ANSWERS -- ROBINSON -86/09/30-KEITH PARKINSON o
ANSWER 7.03 (1.00)
Source CHECK the alarming monitor [0.5]
AND VERIFY alarm-is-valid [0.5]
REFERENCE HBR TECHNICAL SPECIFICATIONS para 1.2.2 and 1.2.6 HBR AOP-005 para 1.3.1.1 SWG-5[2.9/3.9]
ANSWER 7.04 (1.00)
- 1. d [0.2]'
- 2. b [0.2]
- 3. c [0.2]
- 4. e [0.2]
- 5. a [0.2]
' REFERENCE HBR OMM-022 page 12 SWG-10[4.1/4.5]
ANSWER 7.05 ( .00)
- 1. PZR PORVs - closed
- 2. Letdown isolation valves - closed [LCV-460A/460B]
- 3. -Excess letdown isolation valve - closed [CVC-387]
4 '. Reactor vessel head vent valves - closed
'[ question deleted - see examination report]
REFERENCE HBR EPP-1 page 4 SG-10[4.3/4.5]
_ _ _ - _ - - - _ - - - _ - - - - . - - - - . - J
(-
- 27. PROCEDURES - NORMAL. ABNORMAL, EMERGENCY AND PAGE 34
. RADIOLOGICAL-CONTROL ANSWERS -- ROBINSON -86/09/30-KEITH PARKINSON A"SWER 7.06 (2.00)
- 1. Insufficient. letdown [0.5]
- 2. Letdown - charging mismatch [0 ~. 5 ]
- 3. Load rejection
[0.5]
- 4. Increasing Tave [0.5]
[OTHER REASONABLE ANSWERS WILL BE ACCEPTED]'
REFERENCE HBR APP-003 page 29 000/028-EA2.01[3.4/3.6]
-EA2.02[3.4/3.8]
ANSWER 7.07 (1.00)
- a. TRUE
[0.5]
- b. TRUE
[0.5]
-REFERENCE HBR OP-006 page 5 SWG-3[2.8/3.8]
5 010/000-K4.03[3~8/4.1] .
i i
i 1
J I
l
n- -7. PROCEDURES - NORMAL'. ABNORMAL'. EMERGENCY AND 'PAGE 35-T~ -M DIOLOGICAL CONTROL
~
' ANSWERS'- ROBINSON -86/09/30-KEITH PARKINSON ANSWER- 7.08 (2.00)
- 1. Manually. insert control rods
[0.25]
-2. . Verify all turbine valves have closed [0.25]
.and'that turbine. speed is decreasing' [0.25]
- 3. . Verify: turbine casing drain valves DV-1-through DV-7 are,open [0.25]l
and bearing lift pump are; running [0.25].
- 5. Verify plant auxiliaries shift to start-up transformer [0'.25]
and generator ~ lockout occurs approximately 1 minute after generator trip [0.25]
REFERENCE HBR AOP-007-page 4 045/050-A1.01[3.8/4.1]
-A1.02[3.3/3.7]
-SG12[2.4/2.4]
ANSWER 7.09 (2.50) 1 - b. [0.5]
2.- c. [0.5]
3.- c. .[0 5]
( 4.- f. [0.5]
L 3
5.- d. [0.5]
i
, REFERENCE HBR PLS-2 pages 1&2
- SWG-7[3.5/4.0]
i-i t
PI( .; -
3
- 7. PROCEDURES'- NORMAL. ABNORMAL. EMERGENCY AND- :PAGE 36 RADIOLOGICAL CONTROL
> ANSWERS -- ROBINSON -86/09/30-KEITH PARKINSON f
LANSWER 7.-10 (2.00)
- 1. Place the RCS Makeup Mode Selector Switch in th'e BORATE-postion- [0.5]
- 2. Set the Boric Acid Flow Controller, FCV-113A, dial setpoint to the desired quantity of boric acid [0.5]
- 3. Set thefBoric Acid' Totalizer,.YIC-113, to the desired quantity of boric acid [0. 5] '
- 4. Place the RCS Makeup System Start /Stop switch in the START position-
[0.5]
[ paraphrased. steps will be accepted]-
REFERENCE HBR OP-301 Para 6.0-004/010-A4.03[3.9/3.7]
' ANSWER 7.11 (1.00)
- a. 1 DPM [0.5]
- b. 500 pcm .
[0.5]
REFERENCE HBR GP-OO3 para 5.0 001/050-SG12[3.7/3.7]
ANSWER 7.12 (2.00)
- 1. Turbine Stop Valves [0.5]
- 2. Govenor Valves [0.5]
- 3. Reheat Stop Valves [0.5]-
-4. Reheat Intercept Valves [0.5]
REFERENCE HBR GP-005 para 5.0 045/050-SG12[2.4/2.5]
C .:,- . .,.
- . 7 '.
- PROCEDURRR - NORMAL. ABNORMAL; EMERGENCY AND -PAGE 37 RADIOLOGICAL CONTROL
~
" ANSWERS.-- ROBINSON -86/09/30-KEITH PARKINSON
' ANSWER 7.13 (1.00)
Cooldown1and depressurize the RCS [0.5]
or heatup'the RCS above 350 F [0.5]
REFERENCE-HBR OP-006.page 5 .
HBR TECHNICAL SPECIFICATIONS page'3.1-4
'010/000-SG8[3.6/4.3]
ANSWER: 7.14 (1.50)'
.to safely bring the-Reactor Plant to a hot-shutdown condition after a severe fire [0.75]
when the use of EOPs is precluded [0.75]
REFERENCE HBR OMM-012 page 12 000/068-EK3.18[4.2/4.5]
1 ANSWER 7.15 (2.00)
- a. a fourth start can not'be' attempted until the motor has cooled by standing idle for at least one hour. [0.5]
- b. 2 minutes [0.5]
- c. 50 SECONDS [0.5]
- d. Defeat the degraded grid. voltage protection [0.5]
REFERENCE .
HBR OP-101 pages 9-11 003/000-A4.06[2.9/2.9]
'K6.14[2.6/2.9]
F i . .
- 8. ADMINISTRATIVE PROCEDURES. CONDITIONS. AND LIMITATIONS PAGE 38 ANSWERS -- ROBINSON -86/09/30-KEITH PARKINSON ANSWER 8.01 (2.00)
- a. When the reactor is suberitical [0.5]
and Tave is equal to or < 200 F [0.5]
- b. Any operation involving movement of core components when there is fuel in the containment vessel [0.5]
and the pressure vessel head is unbolted or removed [0.5]
REFERENCE HBR TECHNICAL SPECIFICATIONS para 1.2.2 and 1.2.6 HBR AOP-005 para 1.3.1.1 SWG-5[2.9/3.9]
ANSWER 8.02 (1.50)
- 1. Rod can't be moved by its drive mechanism [0.5]
- 2. Rod misaligned by > 15 inches with its bank [0.5]
- 3. Rod drop time not met [0.5]
REFERENCE HBR TECHNICAL SPECIFICATION 3.10.6.1 000/001-EK3.02[3.2/4.3 ANSWER 8.03 (1.00)
Reduce the consequences of a fuel handling accident [0.5]
by providing for the decay of short-lived fission products [0.25]
and the reduction of fission gas inventory in any potentially failed fuel. [0.25]
REFERENCE HBR TECHNICAL SPECIFICATIONS page 3.8-5 SG-8[2.9/4.0]
i
-. o ._ .
s8. ADMINISTRATIVE PROCEDURES.-CONDITIONS. AND LIMITATIONS PAGE 41
. ANSWERS -- ROBINSON. -86/09/30-KEITH PARKINSON
' ANSWER 8.08' 1(2.00)'
- a. : post a continuous. fire watch until the CO2 system ij~ restored to operable condition [reasonablywording accepted] . > {- k O T b.
cc //h Yb post a continuous fire. watch with backup fire suppression capability .
[ reasonable wording accepted] w;Pl,w 3
-mQ ,f. ,j)ft-0] ,
REFERENCE HBR TECHNICAL SPECIFICATIONS para 3.14.5 000/067-EA2.15[2.9/3.9 SWG-8[3.5/4.5]
PWG-19[3.4/4.2]
ANSWER 8.09 (2.50) .
l'. 110KV-4160V startup transformer is in service [0.5]
- 2. 480V buses E1,& E2 energized [0. 5] .
- 3. 4160V buses 2 & 3 energized [0.5]
- 4. 2 diesel generators operable [0.5]
5.- both batteries-&-the DC distribution system operable [0.5]
REFERENCE .
HBR TECHNICAL SPECIFICATIONS para 3.7.1 062/000-SG8[3.4/4.3]
063/000-SG8[3.2/4.1]
064/050-SG8[3.4/4.4]
4
(.
(iL . , . . ..
8'
~
ADMINISTRATIVE PROCEDURES. CONDITIONS. AND LIMITATIONS -PAGE- 39
' ANSWERS - -ROBINSON
-86/09/30-KEITH PARKINSON ANSWER 8.04 (2.00)
- a. Interval requirement not exceeded- [0.5]
.Eight' days does not exceed 1.25 times the specified interval' -[0.5]
- b. : Interval 1 requirement exceeded. [0.5] l
.The.last 3 consecutive intervals exceed 3.25 times the.specified interval [0.5]
REFERENCE HBR TECHNICAL SPECIFICATION ~4.0.1 SWG-1[3.5/3.9]
-8[3.5/4.5]
ANSWER 8.05 (3.00)
- a. de-energizing, isolating and clearing a piece of equipment [0. 5].
[ appropriate answers will be accepted]
- b. used to request post maintenance testing for purpose of documenting equipment operability [0.5]
- c. Bulk Load Dispatcher [0.5]
d.
Shift Foreman or designated alternate [0.5]
-e. no [0.5]
1 l f. the worker's supervisor [0.5]
REFERENCE
- HBR OMM-005 para 4.1 & 5.1 PWG-14[3.6/4.0]
. 4
.D. ADMINISTRATIVE PROCEDURES. CONDITIONS. AND LIMITATIONS PAGE 40 I ANSWERS -- ROBINSON -86/09/30-KEITH PARKINSON.
ANSWER 8.06 (1.50)
- a. one shift foreman holding a SRO license [0.3]
one control operator holding a RO license [0.3]
one additional shift member [0.3]
- b. 14 [0.3]
- c. Plant General Manager [0.3]
REFERENCE HBR TECHNICAL SPECIFICATIONS para 6.2.3 PWG-23[2.8/3.5]
ANSWER 8.07 (2.50)
- a. When it is capable of performing its function. [1.0]
- b. OPERABLE because [0.5]
- 1. the normal source is operable and [0.5]
- 2. all it's redundant systems, subsystems, trains, components and devices are operable [0.5]
[ reasonably worded answers accepted]
REFERENCE HBR TECHNICAL SPECIFICATIONS para 1.3 SWG-5[2.9/3.9]
a n .. ,; .,
- 8. ADMINISTRATIVE PROCEDURES. CONDITIONS.'AND LIMITATIONS -PAGE '42
~
' ANSWERS -- ROBINSON --86/09/30-KEITH PARKINSON 4
, - ANSWER. 8.10 (1.50)
- 1. If time exists the shift foreman shal1' consult with another.
member of plant management prior to approval [0.5]
- 2. If time does not exist'to consult management, the shift foreman approves the deviation prior to performing the protective action.-[0.5]
3.-the N $U7t be notified, via the red phone, if protection action
- would violate TECHNICAL SPECIFICATIONS. [0.5]
i.
i I [ reasonably worded answers accepted]
REFERENCE.
HBR AP-006 para'5.2 PWG-21[3.8/4.1]
4 i ANSWER 8.11 (1.50)
- 1. The valve is part of a safety related system [0.75]
- 2. The valve serves an important function in maintaining plant / system l
reliability ,. .[0.75]
REFERENCE HBR OMM-001 para 5.19.3 PWG-13[3.7/4.0]
ANSWER 8.12 (1.50)
- a. 1&3 [both required, 0.25'each].
b 1&2 [both required, 0 25 each]
4
- c. 1. [0.5]
1 REFERENCE HBR DP-004 para 10.5 PWG-15[3.4/3.9]
1
- o. -
- 8. A>MINISTRATIVE PROCEDURES. CONDITIONS. AND LIMITATIONS PAGE 43 ANSWERS -- ROBINSON -86/09/30-KEITH PARKINSON 1
ANSWER 8.13 (2.50)
- 1. spent resin storage tank [0.5]
- 2. containment sump [0.5]
when thimbles are withdrawn [0.5]
- 3. the areas below the transfer canal [0.5]
during fuel movement [0.5]
REFERENCE HBR HPP-001 para 4.1.15 PWG-16[3.4/3.7]
-17[2.9/3.5]
, . __ . _ _ _ _ _ - _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ - _ _ -