ML20134A994
| ML20134A994 | |
| Person / Time | |
|---|---|
| Site: | Zion, 05000204 |
| Issue date: | 11/04/1985 |
| From: | Doyle P, Hemming W, Higgins R, Mcmillen J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20134A983 | List: |
| References | |
| 50-295-OLS-86, 50-295-OLS-86-0, NUDOCS 8511110149 | |
| Download: ML20134A994 (94) | |
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4 U.S. NUCLEAR REGULATORY COMMISSION REGION III Reports No. 50-295/0LS-86-01 Docket Nos. 50-295; 50-304 Licenses No. DPR-39; DRP-48 Licensee: Commonwealth Edison Company Zion Generating Station Zion, Illinois Facility Name: Zion Generating Station Examination Administered At: Zion, Illinois Examination Conducted: September 30, October 1, 2, 3, and 16, 1985 Examiners: . . ///Vdr
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Date
'{fW Approved By: I . cMillen, Chief perating Licensing Section
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Examination Summary The simulator and plant walk-through portions of the examination were administered on September 30, October 1, 2, 3, and 16, 1985. The written portion of the examination was administered on October 16, 1985 (Report No. 50-295/0LS-86-01). Five reactor operators and five senior reactor operators (one of whom was retaking the examination) were administered all portions of the examination.
Results: Five reactor operators and four senior reactor operators passed.
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REPORT DETAILS
- 1. Examiners
- R. L. Higgins, Region III P. V. Doyle, Headquarters W. C. Hemming, INEL
- Chief Examiner
- 2. Examination Review Meeting An examination review meeting is no longer conducted. Specific facility comments, followed by the NRC response, are included in the following paragraphs.
The facility comments concerning the R0 exam, followed by the NRC response,' appear below. .
Question 1.06 Facility Comment:
The graph provided makes it difficult to arrive at the answers as stated in the key. It is requested that more tolerance be allowed when grading this question.
NRC Response: Reasonable answers which give approximate power levels and time frames were awarded full credit.
Question 1.08.b Facility Comment:
Answer should be 5850 pcm.
NRC Response: Agree. The answer key was changed.
Question 1.11 Facility Comment:
It is requested that a larger margin of error be allowed due to the difficulty in reading the Mollier Diagram.
NRC Response: Agree. Answers within 10 BTU per pound mass of the correct answer were awarded full credit.
Question 2.01 Facility Comment:
At the time of examination Zion Unit 1 RCFC's had been modified significantly. Unit 2 RCFC's, presently in the original state, are scheduled for similar modification. The candidates responses could differ from the answers (2.01.a. and 2.01.c.) since these answers do not include modification information. The stated reference (Zion SD 11-4) is currently undergoing reprint to reflect Mod M22-2-84-40, which involves changing the RCFC's to a one flowpath system. .It has been determined that the moisture separators and HEPA filters are not necessary during accident conditions. Therefore, there is no longer any need for two separate flowpaths within the RCFC's. Switching the RCFC's to a one flowpath 2-
system makes their operation inherently more. reliable as there are no I i
longer any RCFC dampers that must shift during accident conditions. The result of this modification is that the only condition required for an RCFC to be in the accident mode is to have the fan in low speed.
NRC Response : Agree. The answer key was changed to include this current modification as a correct response. Since both units have not been modified, the original answer will also receive full credit.
Question 2.07 Facility Comment:
In addition to the answers listed, Zion also utilizes jacket water heaters.
The purpose of these heaters is to keep the jacket warm thereby keeping the cylinders warm to provide lower friction for starting.
NRC Response: Agree. The answer key was changed to accept " jacket water heaters" as a correct response.
Question 2.08 Facility Comment:
The letdown orifice isolation valves will also close on a Containment Phase "A" Isolation. (Zion SD Chapt Sa, page 59, attached).
NRC Response: Agree. The answer key was changed to require " Containment Phase "A" Isolation" as a required response. Credit was awarded for "SI" in lieu of " Phase A."
Question 3.03.c Facility Comment:
The answer should state that only outward rod motion will be prevented.
NRC Response: Agree. The answer key was changed to read " preventing any auto or manual outward rod motion."
Question 3.10.d Facility Comment:
The correct answer is "d." (Zion 50 Chapter 3c page 23 , attached).
NRC Response: Agree. The answer key was changed to choice "d,"
auctioneered high Tavg.
Question 4.12 Facility Comment:
The answer key should be changed to reflect the actual sequence of automatic actions listed in AOP-21, and the statement "after 30 seconds" should be changed to "within 30 seconds" per A0P-21.
NRC. Response: Agree. The answer key was changed.
The facility comments concerning the SRO exam, followed by the NRC response,
. appear below:
Question 6.01.b Facility Comment:
The correct answer should be " overpower differential temperature" per Technical Specification bases, pages 21 and 22.
NRC Response: Agree. The answer key was changed to " overpower l differential temperature."
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Question 6.02.a Facility Comment:
The word " activate" could lead candidate to provide trip setpoints and coincidence vice logic to enable these trips. Please consider this when grading.
NRC Response: Agree. The wording of the question does not necessarily elicit the answer from the answer key. The answer key was modified to
. grant full credit to the following responses:
" Single loop loss of flow: 2/3 flow detectors less than 90% in one loop" "Two loop loss of flow: 2/3 flow detectors less than 90% in two loops"
. Question 6.03a Facility Comment:
Technical Specification bases, page 248, also discuss iodine activity which should be included as part of the answer.
, NRC Response: Agree. The answer key was modified to grant full credit to the response " remove iodine activity."
Question 6.04 Facility Comment: i Answers a.4 and b.1 do not apply to Zion.
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- a. 4 should be " Reactor Coolant Pumps Thermal Barrier Cooling Water Flow High."
- b. 1 should be " closure upon high flow of 190 gpm."
NRC Response: Agree. The answer key was changed.
. Question 6.07.c Facility Comment:
The answer key should be changed to:
(1) Steamline differential pressure S.I.
(2) High Steamflow with Lo Tave or lo Steam Pressure S.I.
. .(3) Lo-Lo S/G Level Reactor Trip--
(4) Hi-Hi S/G Level Reactor. Trip (5) S/G Low Level with SF/FF mismatch Reactor Trip -
NRC Response: Partially agree. There is no "Hi-Hi S/G Level Reactor Trip." - There is a "Hi-Hi S/G Level feedwater pump trip, turbine trip and feedwater isolation." The answer ~ key.was modified accordingly.
Question 6.08.a.2 Facility Comment:
Motor Driven AFW pumps auto start on Low-Low Level in one S/G.
NRC Response: Agree. The answer key was changed.
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Question 6.08.b Facility Comment:
Zion does not have a circuit to isolate S/G Blowdown upon receipt of an AFW auto-start signal. This is incorrectly stated in_the.
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reference as shown by the attached electrical drawing 22-1-4840 page 80-17. Reference will be corrected to prevent any future error in this regard.
NRC Response: Agree. The answer key was changed. The facility should ensure that the reference material sent to the NRC is free from errors to avoid having to modify the answer key after the exam is administered.
f Question 7.04.a Facility Comment:
Question asks for conditions .to verify adequate subcooling while answer states conditions to verify natural circulation. Please consider this when grading.
NRC Response: Agree. The question was somewhat ambiguous. Reasonable answers will be awarded credit.
Question 7.07.b Facility Comment:
Due to information provided in part a., candidate may consider the core to be preconditioned to 50% power which will affect the final time.
NRC Response: Agree. Full credit will be awarded if the examinee assumes that the core was preconditioned to 50% power, in which case the correct answer will be 19.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
Question 8.04 Facility Comment:
Zion's training program for administrative controls informs students to only regard those reporting requirements which are most restrictive. In the case of exceeding a Safety Limit the one hour reporting requirement as set forth in 10 CFR 50.72 is highly stressed. Although the question asks for the time per Technical Specifications the candidates may answer in accordance with the most restrictive limitation due to the fact it
- will supersede the Technical Specifications requirement. Please consider this when' grading.
NRC Response: Agree. The answer was changed to "b," I hour.
. Question 8.06 Facility Comment:
The correct answer is flawed by the fact that, IAW Zion Technical Specifications, in Mode 2 reactivity is zero or greater and therefore Keff is 1.0 or greater. If the question is in regard to a transient this should be stated for purposes of clarification.
NRC Response: Disagree. When rods are being withdrawn during a startup the reactor is in Mode 2.
- 3. Exit Meeting On October 3,1985, representatives of the NRC met with facility representatives to discuss preliminary results of the simulator and plant walk-through examinations, as well as any relevant observations made by the examiners. The following NRC personnel were in attendance:
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M. M. Holzmer, Zion Senior Resident Inspector R. L. Higgins, Region III Operator Licensing Examiner The following facility personnel were in attendance:
George Plim1, Zion Station Manager Ed Fuerst, Zion Superintendent of Operations Terry Rieck, Zion Superintendent of Services Mark Carnahan, Zion . Training Supervisor Ray Landrum, Zion Principal Instructor
- a. The facility representatives were informed that of the ten oral / simulator examinations administered, eight examinees definitely passed and two examinees were marginal.
- b. While conducting the simulator examinations, the examiners noted that some examinees blindly followed emergency procedures during situations which differed materially from the plant conditions for which the procedures were written. It was felt that the procedures
' would be better utilized if they were used in a more flexible manner. Though this technique would require more thought and i analysis on the operator's part, it would still allow the procedures to be used as a guide and an aid. The examiners believe this is preferable to performing procedural steps which are inappropriate or erroneous for the actual plant condition.
- c. The facility was complimented for being extremely clean.
Cleanliness was particularly noteworthy because one of the units was in an outage condition. -
} d. Facility and Westinghouse Training Center personnel were complimented for being cooperative during the administration of the examinations.
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L 84 U. S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION FACILITY: ZION 1&2 REACTOR TYPE: PWR-WEC4 DATE ADMINISTERED: 85/09/30 EXAMINER: HEMMING, W.
APPLICANT
- _________________________
INSTRUCTIONS TO APPLICANT:
Uso ceparate paper for the answers. Write answers on one side only.
Stcple question sheet on top of the answer sheets. Points for each question are indicated in parentheses after the question. The passing grade requires at least 70% in each category and a final grade of at losst 80%. Examination papers will be picked up six (6) hours after the examination starts.
% OF BATEGORY % OF APPLICANT'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY w_______ ______ ___________ ________ ___________________________________
25.00 25.00 s_______ ______ ___________ ________ 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW 25.00 25.00
,_______ ______ ___________ ________ 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS 25.00 25.00 3_______ ______ ___________ ________ 3. INSTRUMENTS AND CONTROLS 25.00 25*00 PROCEDURES - NORMAL, ABNORMAL, 3_______ ___ __ ___________ ________ 4.
EMERGENCY AND RADIOLOGICAL CONTROL 300.00 100.00 TOTALS 5 ______ ______ ___________ ________
FINAL GRADE _________________%
11 work done on this examination is my own. I have neither s iv0n nor received aid.
PPL5CIUTI 5~556UIiURE~~~~~~~~~~~~~~
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- 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 2
~~~~T 5ER566Y IUEC5,"UEST'TRd 5EER'5 D'FL ED'EL U QUESTION 1.01 (1.00)
During a reactor startup from an initial Keff of .90, the first rocctivity addition caused count rate to increase from 10 eps to 16 cps. The second reactivity addition caused count rate to increase froa 16 cps to 32 eps. Which of the following statements BEST describes tha relationship between the first and second reactivity additions?
- o. The first reactivity addition was the larger of the two.
- b. The second reactivity addition was the larger of the two.
- c. The first and second reactivity additions were equal.
- d. There is not enough data given to determine the relationship.
QUESTION 1.02 (1.00)
TRUE or FALSE?
- c. During 100% power operation, Departure from Nucleate Boiling Ratio (DNBR) is greater than the DNBR for 20% reactor power.
- b. As the temperature difference between the fuel rod surface and the eatoration temp?rature of the coolant (Twall-Tsat) increases at a constant linear rate,(0-10E4), the heat flux across the fuel surface (BTU /hr sq. ft.) .ncreases at a constant linear rate.
. QUESTION 1.03 (1.50)
TRUE or FALSE?
- o. The faster a centrifugal pump rotates, the greater the NPSH required to prevent cavitation.
- b. One of the pump laws for centrifugal pumps states that the volumetric flow rate is inversely proportional to the speed of the pump.
- c. Pump runout is the term used to describe the condition of a centrifugal pump runnin3 with no volumetric flow rate.
(xxxxx CATEGORY 01 CONTINUED ON NEXT PAGE xxxxx)
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- 1. . PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 3
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~~~~5H5R566 U5U5C5I~E55T"TR5U5EER 5U6~ FLU 56~fL6U QUESTION 1.04 (2.00)
- e. If the reactor is operating in the power range, how long will it take to raise power from 20% to 40% with a +0.5 DPM Start-up rate?
- b. Will it take the same amount of time to raise power from 40%
to 60% if the same startup is maintained? EXPLAIN.
QUESTION 1.05 (1.00)
Which of the following best describes the effect on MTC if the RCS tsoperature is LOWERED?
- a. It becomes less negativei Baron and water molecules are zwept into the core as a result of the outsurge from the pressurizer, therefore, neutrons spend more time in the resonance region.
- b. It becomes less negative; The rate of change in the density of water per degree F is less at' lower temperatures causing a reduction in the rate of change in resonance escape probability.
- c. It becomes more negativei Thermal utilization increases and resonance escape probability decreases.
- d. It becomes more negative; As temperature is lowered the coderator becomes oore dense. This increases the amount of water molecules in the core, therefore neutrons have a greater probability of colliding with a water molecule which increases the negative reactivity effect.
(***** CATEGORY 01 CONTINUED ON NEXT PAGE *****)
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- 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 4
--- iREER55isARIEi- sEAi iEAssFEE As5 FEUi5 FE5E GUESTION 1.06 (4.00)
Using the attached Xenon worth curve, Fig. 1.1, answer the following.
- c. Power at TO was at 70%. What was the power level between T1 and T2?
- b. What was the lenth of time between T2 and T3?
- c. What happened at T2?
- d. At time T4... (choose one)
- 1. all Xenon production has stopped.
- 3. All Xenon production remains constant, but burnout increases.
4 4.-Xenon production directly from fission has stopped, but Xenon production fron Iodine decay continues.
QUESTION 1.07 (1.00) i Delayed neutrons play a major role in the operation of the core bscause they ...
- a. are born at (thermal) slow energy levels (less than 1 ev) and therefore are more apt to cause a fission as compared to being absorbed by a poison.
- b. cre considered as epithermal neutrons and therefore they will not travel far enou3h to leak out of the core.
- c. are born so much later than the prompt neutrons and provide controlability during steady state operations and power transients.
d, provide 70% of the fission neutron inventory and_have. higher importance factors associated with them as compared to prompt neutrons.
(xxxxx CATEGORY 01 CONTINUED ON NEXT PAGE xxxxx)
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- 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 5
~~~~TEER066 d55C57~55dT"TRIU5EEE~506'ELU56'EL6U QUESTION 1.08 (2.00)
- a. 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 brins Me*f equal to 0.957 Assume BOL' conditions.
- b. How much reactivity was added? (Include units.)
OUESTION 1.09 (1.50)
Conpare the calculated Estimated Critical Position (ECP) for a etartup 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br />.after a trip to the actual Critical Rod Position (ACP) if the following events / conditions occurred. Consider each indapendently. . Limit your answer to
- 1. One Reactor Coolant Pump is stopped one minute prior to criticality.
- 2. The steam dump pressure setpoint is increased to a value just below the code safties setpoints.
- 3. The startup is 'elayed d 2 more hours.
. QUESTION 1.10 (1.00)
TRUE'or FALSE?
- a. Durins a RCS heatup, as temperature sets higher, it will take a smaller letdown flow rate to maintain a constant pressurizer level.
- b. Increasins condensate depression (subcoolins) will cause BOTH a decrease in plint efficiency AND en increase in condensate (hotwell) pump available NPSH.
(xxxxx CATEGORY 01 CONTINUED ON NEXT PAGE xxxxx)
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- 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 6
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~~~~TUER566YU555C5,~5EST TR5U5EER d 6~ELU56~ELUU QUESTION 1.11 (1.00)
Stosm exit'ing the HP turbine is at 785 psis, 90% quality. Steam ontoring the LP turbine is superheated to 100 F. What is the onthalpy change of the steam?
DUESTION 1.12 (1.00)
In order to maintain a 200 F subcooling margin in the RCS when roducing RCS pressure to 1600 psis, the steam generator pressure j cost be reduced to ____ psig.
QUESTION 1.13 (1.00)
During a Xenon-free reactor startup, critical data was inadvertently taken two decades below the required Intermediate Range (IR) level (1xE-10 amps).
The critical data was taken again at the proper IR level (1xE-8 amps).
Assuming RCS temperatures and boron concentrations were the same for each set of data, which of the following statements is correct?
- a. The critical rod position taken at the proper IR level is LESS THAN the critical rod position taken two decades below the proper IR level.
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- b. 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.
- c. The critical rod position taken at the proper IR level is GREATER THAN the critical rod position taken two decades below the proper IR level.
- d. There is not enough information given to determine the relationship between the critical rod position taken at the proper IR level and the critical rod position taken two decades below the proper IR level.
QUESTION 1.14 (2.00)
If eteam Soes through a throttling process, indicate whether the followinS perometers will INCREASE, DECREASE, or REMAIN THE SAME.
- a. Enthalpy
- b. Pressure
- c. Entropy
- d. Temperature (mmmmm CATEGORY 01 CONTINUED ON NEXT PAGE *****)
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- 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 7
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~~~~iEER566YUd55C5I"5Edi TRIU5F5R~ UD iEUi6~fEUU QUESTION 1.15 (2.00)
Indicate how the following will affect Unit efficiency (increase,
~d crease, no change) at a steady state power level. (Consider each caso separately.)
- c. Absolute condenser pressure changes from 1 psi to 1.25 psi.
- b. Total S/G blowdown is changed from 35 spa to 40 spm.
- c. Condenser hotwell temperature changes from 125 F to 130 F. -
(Assume no change in condenser pressure.)
! d. Steam quality changes from 99.8% to 99.7%.
QUESTION 1.16 (2.00) j o. Which parameter below will have the MOST effect on the shape i of a Differential Rod Worth Curve?
- 1) Core radial flux profile j 2) Core axial flux profile
- 3) Core axial temperature profile
- 4) Time of core cycle
- b. TRUE or FALSE?
The effect of the bank overlap program on the Differential Rod Worth curve is to make the shape of the curve more linear.
(***** END OF CATEGORY 01 wuumu) 7 1
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- 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 8 QUESTION 2.01 (2.50)
- o. Describe the normal flewpath of air circulated by a Reactor Containment Fan Cooler (RCFC). Include the major components that air is directed to. (1.0)
- b. How many RCFC's are needed during normal operation? During accident operations? (0.5)
- c. How is the RCFC system affected by a Safety Injection signal. (1.0)
QUESTION 2.02 (2.50)
D. With the Component Coolin3 Water Pump Control Switch in '
the ' AUTO' position, what will automatically start the Standby pump? (Setpoints not required.) (.75)
- b. Under what conditions will component cooling water automatically be isolated to the RCP's? (0.5)
- c. What signal will isolate the CCW return water from the Excess LDHX by closing valve 1A0V-CC94377 (Setpoints not required.) (0.5)
- d. What is the aporoximate setpoint of the CCW relief valve downstream of the thermal barrier heat exchanger?
Why is it set at this value? (.75)
QUESTION 2.03 (2.00)
- o. Diesel Generator 0 is loaded and paralleled to 4 KV Bus 147 uhen a complete loss of offsite power occurs (LOSP). In conjunction with the LOSP, unit two undergoes a safety injection.
Explain the affect on D/G 0 and it's output breaker. Be specific. (1.0)
How does LBB action differ when breakers 1718 and 1819 (unit one cain generator output breakers) are affected? (1.0)
(rxxxx CATEGORY 02 CONTINUED ON NEXT PAGE ummun) e- _
- 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 9 QUESTION 2.04 (2.75)
- o. What THREE different parameters are used for input to the Main Feedwater Pump Net Positive Suction Head (FWPNPSH) Control System? (Be specific.) (.75)
- b. If the available FWPNPSH decreases to 275 psis, an alarm sounds.
What other FOUR actions automatically occur when a low FWP cuction pressure condition exists? (2.0)
QUESTION 2.05 (2.50)
- o. State the rated flow of each type of auxiliary feedwater Pump below:
motor driven.
turbine driven. (1.0)
- b. State FOUR signals that will automatically start the TURBINE driven auxiliary feedwater pump. (Include coincidences) (1.0)
- c. Which S/G's can supply steam to the turbine driven auxiliary feedwater pump? (0.5)
GUESTION 2.06 (2.50)
- o. The flowrate through the RCP #1 seal is not constant for all plant conditions. EXPLAIN when AND why the flowrate will be at it's highest and lowest value. (1.0)
- b. What is/are the flowpath(s) for the RCP #1 seal leakoff during a cafety injection? (1.0)
- c. What determines the differential pressure across the RCP 41 seal? (0.5)
QUESTION 2.07 (2.25)
List THREE support systems used to ensure that the emergency diocel engine will rapid start within the required time limit.
INCLUDE what each system does for the engine to ensure that it will rapid start. (Do not include maintenance or surveillance itcos.) (2.25)
(xxxxx CATEGORY 02 CONTINUED ON NEXT PAGE muunu) l
- 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 10 QUESTION 2.08 (2.50)
- c. What will cause the letdown orifice isolation valves (8149 A,B,C) to automatically close with no operator action? (control switch for the valves in the auto /open position).
- b. What is the function AND purpose of valve PCV 131 (letdown pressure control valve) during each of the below. Be specific.
- 1. normal operations.
- 2. solid plant operations. (1.5)
GUESTION 2.09 (2.50)
- a. List TWO reasons for maintaining a minimum pressurizer spray line flow during normal *at power' operations (1.0)
- b. What gives indication to the operator that minimum spray flow is not bein3 maintained? (0.5)
- c. What' creates the motive force for pressurizer spray flow? (1.0)
QUESTION 2.10 (3.00)
- a. Describe the difference in flowpaths used for ALTERNATE DILUTE and DILUTE modes of operation in the Reactor Makeup Control System. Why are two dilution paths necessary? (1.5)
- b. What is the major concern with fluids containing boric acid?
What is done to alleviate this concern? Include all methods used. (1.5)
(xx*** END OF CATEGORY 02 muxum)
- 3. INSTRUMENTS AND CONTROLS PAGE 11 QUESTION 3.01 (2.50)
Indicate which of the Excore Nuclear Instrumentation Ranges (SOURCE, INTERMEDIATE, POWER, OR NONE) will correctly match the following statements. More than one may apply to each.
- e. Provides a direct input to the Rod Control System.
- b. Has a reactor trip function that is blocked at some time between startup and full power operation.
- c. It's detector operation is unaffected by gamma radiation.
- d. Utilizes a Boron-10 coating in it's detectors.
- o. Operates in the ' Ion Chamber
- region of the ' Gas Filled Detector Characteristic Curve'. (2.5)
DUESTION 3.02 (2.00)
- o. Pressurizer pressure channels 455 and 456 are selected for control. Explain the response of the pressurizer pressure i control system if PT-456 failed high. (1.0)
! b. With pressurizer pressure channels 455 and 456 selected for I control, will one Pressurizer PORV open before the other if pressurizer pressure rises at a rapid rate? EXPLAIN. (1.0)
, QUESTION 3.03 (2.00)
BRIEFLY EXPLAIN the response of the Rod Control System for each of tha following instrument failures. Include in your answer direction of cotion, why the motion occurs as it does, and any controls or poroissives encountered (and their effects). Assume the plant at 75%
pow 2r with all systems in automatic and no operator action or protective trips occur.
- b. Turbine Impulse Pressure (PT-505) fails LOW.
- c. Power Range lower detector (NI-44) fails HIGH.
(xxxxx CATEGORY 03 CONTINUED ON NEXT PAGE mmmmm)
- 3. INSTRUMENTS AND CONTROLS PAGE 12 QUESTION 3.04 (3.00)
List FOUR signals that will initiate a safety injection. Include with occh any permissive that will block or allow blockin3 of the signal.
Satpoints not required.
QUESTION 3.05 (3.00)
The reactor is operating at.100% power with all systems in cutomatic control. For the following failures, state the protective eignal which will cause the reactor to trip. Provide an explanation of why the trip occurs. Assume no operator action and consider each failure independently.
- c. The contro11in3 Pressuri=er level channel fails HIGH.
- b. The controlling cold les temperature detector fails HIGH.
QUESTION 3.06 (2.50)
- a. Explain the purpose of the steam pressure input used in the developement of a steam flow signal for the S/G water level control system. (1.0)
- b. How would INDICATED steam flow compare to ACTUAL steam flow if, during a power increase from 0-100%, the steam pressure signal
' stuck at its 50% power value. Briefly explain why. (1.5)
GUESTION 3.07 (3.00)
- c. Define " Coincidence' as it applies to the Reactor Protection System (RPS). (1.0)
- b. What is the minimum degree of redundancy that is allowed for protection instrumentation? (1.0)
- c. Protective signals that initiate Reactor Protection and Engineering Safety Features use a 'de-ener3 i ce to operate" bistable principle.
State the one protective feature that does not use this principle and explain why. (1.0)
(xxxxx CATEGORY 03 CONTINUED ON NEXT PAGE asumm)
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- 3. INSTRUMENTS AND CONTROLS PAGE 13 QUESTION 3.08 (3.00)
Match the proper Steam Dump Control (s) or Controller (s) in Column B to each statement in Column A. More than one in Column B may apply to each in column A. Place answers on your answer page.
COLUMN A COLUMN B
____a. Operates Steam Dumps based on a 1. Turbine trip controller.
temperature deviation (Tavg-Tref).
- 2. Steam pressure controller.
____b. Used to reset the C-7 arming signal.
- 3. Load rejection controller.
____c. Contains no trip open features.
- 4. Steam Dump Control Mode
____d. Uses auctioneered high Tavs. Selector.
____e. Compares the actual parameter to 5. Steam Dump Interlock that of a pre-set value for operation Selector.
____f. Used to allow cooldown valves to open below P-12.
_-- S. Used to turn the system off.
____h. Uses quick open bistables for rapid transients.
QUESTION 3.09 (1.00)
Tha THREE input signals to the Steam Generator Water Level Control Dret
- a. Tavs, compensated feed flow, uncompensated steam flow.
- b. Feed flow, compensated steam flow, water level error.
- c. Compensated feed flow, water level, compensated steam flow.
- d. Uncompensated feed flow, compensated steam flow, water level.
(xxxxx CATEGORY 03 CONTINUED ON NEXT PAGE xxxxx) 1 4
- 3. INSTRUMENTS AND CONTROLS PAGE 14 GUESTION 3.10 (1.00)
. Programmed Pressurizer level is based ont
- a. Auctioneered High Power.
- b. Loop Tavs.
- c. Tret from Pimp.
- d. Auctioneered High Tavg.
QUESTION 3.11 (1.00)
Which of the following core parameters does the OT delta T protective circuit prevent exceedins?
- o. Power density.
- b. Departure from Nucleate Boiling.
- c. Total core power.
- d. Redistribution.
QUESTION 3.12 (1.00)
Th2 OP delta T setpoint is a calculated value determined by 109%
full power delta T,' minus correction proportional to the rate of
- a. increase of Tavs, minus correction proportional to variation of delta T above full load value.
- b. increase of Thot, minus correction proportional to varation of Thot above full load Thot
- c. increase of Tavs, minus correction proportional to varation of Tavs above full load Tavg.
- d. increase of delta T, minus correction proportional to variation of delta T above full load.
(*zzam END OF CATEGORY 03 mmxxx)
1 l
I
- 4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 15
~~~~ ~ ----------~~------------
RA656E6G56AL 66sTR6L GUESTION 4.01 (2.50)
Briefly describe the automatic actions that occur when the following Radiation Monitoring System channels reach their alstm setpoints.
- c. Steam Generator Blowdown Liquid Monitor (R-19)
- b. Component Cooling Water System Monitor (R-17)
- c. Fire Sump Monitor (ORT-PR17)
- d. Air Ejector Monitor (R-15)
(2.5)
GUESTION 4.02 (2.50)
Ccaplete the followins statements utilizing information found in
'Plent Heatup' (GOP-1).
- o. For normal heatup of the Pressurizer, a rate of ________ F/ hour will not be exceeded.
- b. Spray Flow into the Pressurizer will not be initiated if the temperature difference between the Per and Spray fluid exceeds
________ F.
- c. If Component Coolins flow to the RCP oil coolers is lost for any reason during RCP operation, the RCP(s) must be stopped before bearing temperature reaches ________ F.
- d. Heat-up must be terminated or spray initiated if RC Loop Boron Concentration decrease approaches ________ ppm or if PZR Boron opproaches ________ ppm less than RC Loop Concentration.
QUESTION 4.03 (2.50)
- o. What action must be taken if, while performing a startup per procedure GOP-2 (Plant Startup), criticality is achieved below the Control Bank Low-Low insertion limit? (1.0)
- b. What are the THREE reasons for maintaining Control Banks above the Low-Low insertion limits? (1.5)
(**z*n CATEGORY 04 CONTINUED ON NEXT PAGE musum)
- a. '
.. _ _ . .~ .
4, PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 16 RADIOLOGICAL CONTROL GUESTION 4.04 (1.50)
Define the following Technical Specification terms.
.a. INADVERTENT TRIP i
- b. DEGREE OF REDUNDANCY GUESTION 4.05 (1.00)
Which of the following defines a RESTRICTED AREA per 10 CFR 20?
- o. The area surrounding the reactor in which the licensee has the authority to determine all activities including the removal of personnel or property from the area.
- b. An area where an individual located at any point on it's boundary for two hours following a postulated accident will not receive in
, excess of 25 rems whole body or 300 rems to the thyroid
- c. An area in which access is controlled by the licensee for purposes of protection of individuals from exposure to radiatior. and radioactive materials.
- d. An area where an individual located at any point on it's boundary followins a postulated accident will not receive in excess of 25 rems whole body or 300 rems to the thyroid.
QUESTION 4.06 (1.00) i According to 10 CFR 20, what is the maximum dose any individual may receive with Form NRC-4 on file?
- a. 1 1/4 rems / quarter not to e: ceed 5(n-18) .
- b. 3 rems / quarter not to exceed 5(n-18).
- c. 5 rems / quarter not to exceed 5(n-18).
- d. 5(n-18).
(mmmmm CATEGORY 04 CONTINUED ON NEXT PAGE mamma) l l
l l i
- 4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 17
~~~~ ~ ~~~~~~~~~~~~~~~~~~~~~~~~
RA656LU6565L 66UTR6L 1
QUESTION 4.07 (2.50)
is a caution directing the operator to manually reinitiate safety injection if any of three conditions are exhibited. List the three conditions,'be specific. (1.5)
- b. The caution in part "a* above and a note preceeding the caution indicates that automatic safaty injection is not available.
Explain why only manual initiation is available at this time. (1.0)
L QUESTION 4.08 (1.50)
List the three symptoms that indicate inadequate core cooling eccording to E0P-11, Inadequate Core Coolins, if the computer in not available. Be specific.
QUESTION 4.09 (2.00) l E0P-5, Emergency Boration, lists four ways to emergency borate. List tho four ways and indicate which of the four is/are not preferred.
(Individual procedural steps not required.)
QUESTION 4.10 (2.50)
- a. If leakase into a S/G is dia3 nosed and AOP-19, S/G. Tube Leak, is an use, what plant conditions require exiting AOP-19 and where are you directed to proceed? (1.0) i b. AOP-19 directs the centrifugal chargins Pump (CCP) miniflow isolation valves to be closed if additional charging flow is needed. When may the velves be closed? When are they required to be reopened and why must they be reopened at this time? (1.5) i i (mmmmm CATEGORY 04 CONTINUED ON NEXT PAGE mamma)
s
- 4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 18
~~~~ ~~~~~~~~~~~~~~~~~~~~~~~~
R D56L655ddE"66NTRUL ;
GUESTION 4.11 (3.00)
- o. Technical Specifications Section 3.3.1 (RCS Operational Components) makes provisions for all reactor coolant pumps and decay heat removal pumps to be stopped when in mode 4. How long can they be stopped and what requirements must be met while they are stopped? (1.25)
- b. According to AOP-20, Loss of RHR Shutdown Cooling, what are the immediate operator actions if RHR is lost because of the fo11owin3 favits:
- 1. MOV-RH 8701 or 8702 closes.
- 2. HCV-RH 606 or 607 closes. (1.75)
QUESTION 4 12' (2.50)
AOP-21, De3raded 4 KV ESF Bus Voltage, states that certain delayed cutomatic actions will occur if a de3raded condition of 3850 volts rocoins for 8 seconds. State the lenSth of this delay and the ,
! cutomatic actions that occur. (Include any loads that are shed or cuto-start.) -
4 2
i r
- (numan END OF CATEGORY 04 maman)
! (mmmmmmmmmmmam END OF EXAMINATION maammmmmmmmmmmm) 4 I
i 5
i 1 I k l
s .
FOUATIONS s REACTOR THEORY RADIATION Fl.UIDS/THERH0/ HEAT TRANSFEk
.. 't . r. . W g. , .
I " I o*t/t l0 SUR 4 y . y . At - .
o . 33,3y, ,g,,,y,
, {. , 3 p ,g p A = AN q . A1V1 = AaVa P A8 AD - ~
g . g WK = 0I 10 "# M E in
~
out
+A k-1 stored 0*
km - k i 0 k kaka
- At ATis = 0.693 E = KE + PE + U + pV + Q + W C211 1-k i R/hr e d feet = 6
. y [sg Z k*1 Point source E cyst , 1 - ka Inda8 = lada g
~
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Inda - line source b"5 U R/hr x time - R reduced for turbine. SG pump, nozzle.
CPe
- 1, - ,
Rad x QF = Rem orifice. c ud user, pipe. Rx LJ cys, -
flow a /dp Tis = Bio x % Rad net " A " doppler + " mod + 8 void Tis , g, + T!s Rad head loss = f or head loss a V e head loss a AP
- e+8Se X + # Fu + P=h + p a diut =k v
pSoron + prod + pfuel + F = pA 2E c gpaphase AP1 phase x K O
Folsons) k = f(quality & Pressure)
Pump laus speed a flow ka = kg + Sk (speed)ac pressure 6k=k-1 HAT 11 (speed)3a power Q = kAAT = hAa7 = UAAT SUN =
- 1 y =b Q = m cp4T ,
log b-a 9 * "Ah I4V y Q = ccT ''''
\, ,,3.1 x 101fg '
c log x = c log x All = m e. aT ,
x P I = No I Ey"losx-logy atr = ,a c. AT '
4 . g, los xy = log x + log y H=U+pV Defect = Coeff x a Parameter AS * '
PV = nRT '
PVI T
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- 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 19
--- isEER557aARiEE- REKi iEAssFEE AR5 FEGi6 FE6E ANSWERS -- ZION 1&2 -85/09/30-HEMMING, W.
ANSWER 1.01 (1.00)
D REFERENCE HBR, Reactor Theory, Sessions 41 and 42 Cook, WNTC Theory text, pp. I-4.26 -27.
Zion, NUS book 3, sections 12.1, 12.4.
ANSWER '1.02 (1.00)
- a. False
- b. False CO.5 ea.3 REFERENCE Cock, Westinghouse Thermal Science, Chapter 13, Pp. 17-23. KA002/000,K5.01 Zion, Same as Cook.
ANSWER 1.03 (1.50)
- n. True
- b. False
- c. False CO.5 each3 REFERENCE Cook, Westinghouse Thermal Science, Chapter 10, Pp. 41-49 Zion, Same as Cook.
ANSWER 1.04 (2.00)
- c. 36 seconds. (+/- 2) .
- b. No.C.253 Power esca11ation is a los function and therefore increases et an increasein3 rate. E.753 (2.0)
REFERENCE Cook Theory, Pp. I3.15-16. KA001/010,K5.37,3.2.
Zion, NUS book-3, section 6.4 l
l t
- 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 20
~~~~TEER566YUd5EC5IUEdi~TR5 5 FEE ~dU6 FLUE 6~FL6E ANSWERS -- ZION 1&2 -85/09/30-HEMMING, W.
ANSWER 1.05 (1.00) b.
REFERENCE SONP, 6 Factor Formula lesson, pp. 3-5 KA001/000,K5.26,3.3.
Cook Theory, Pp I-5 2-15.
Zion, NUS book 3, section 8.3 ANSWER 1.06 (4.00)
- o. 90%
(fcW- V b . O ', e_. 5"; [ - 5'/O W M '
- c. reactor power was reduced to 10%.( - /O-8 '
- d. 4 E1.0 ea3 (4.0)
REFERENCE SONP, Review of core poisons lesson, p. 6 KA004/000,K5.20,3.6.
Cook Theory, Pp. I-5.57-77.
Zion, NUS book 3, sections 10.2,10.3,10.4.
ANSWER 1.07 (1.00) c.
REFERENCE SONP, Review of Neutron Kinetics, p. 5 KA001/000,K5.49,2.9.
Cock Theory, Pp. I-3.3-10.
Zicn, NUS book 3, section 5.5.
ANSWER 1.08 (2.00)
- a. 100 cps.-(+/- 10)
- b. 585$ pen. (+/- 15) E1.0 ea3 (2.0) 56f '
S~ me -r%M)
r
- 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 21
--- isEss55isAsiEE- sEAi iEAssFEE As5 FEUi5 FE5s CNSWERS -- ZION 1&2 -85/09/30-HEMMING, W.
REFERENCE SONP, Suberitical Multiplication lesson, p. Si Review of Kinetics, p. 3 Ceck Theory, Pp. I-4.13-15. KA001/000,K5.49,2.9.
Zion, NUS book 3, section 12.1.
ANSWER 1.09 (1.50)
- 1. e (same)
- 2. o (ACP higher)
- 3. b (ACP lower) [0.5 ea.]
REFERENCE SONP, Review of Core Poisons, pp. 4-7 KA001/000,K5.18,4.2.
Cock Theory, Pp. I-36-45.
Zion, NUS book 3, section 12.5.
ANSWER 1.10 (1.00)
- c. FALSE
- b. TRUE CO.5 ea.]
REFERENCE SONP, General Physics, HTRFF, pp. 155 and 320 end KA056/000,K5.02,1.5 Subcooled Liquid Density Tables K5.0$,1.7 C :k, Westinghouse Thermal Science, Chapter 10, Pp 9-24 KA004/020,K5.06,2.4 Chapter 09, Pp 21-23.
Zicne Same as Cook.
ANSWER 1.11 (1.00) 156 BTU /LBM M -- N (t/_/0)
REFERENCE SQNP, HTFF text, pp. 23 - 24 Ccck, Westinshouse Thermal Science, Chsapter 7, Pp 32-46.
Zion, Same as Cook.
l
- 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 22
--- iREER557RARICi- sEAi iEARsFEE AR5 FC0i6 FC6s ANSWERS -- ZION 1&2 -85/09/30-HEMMING, W.
ANSWER 1.12 (1 00) 245 psis. ./ p M _f REFERENCE Shaaron Harris-Thermo-LP-1.1 and steam tables KA002/000,K5.01,3.1 Cock-Westinghouse Thermal Science, Chapter 2,Pp 63-70,79. /020,K5.06,3.4 Zion, Same as Cook.
ANSWER 1 13 (1.00) b REFERENCE NUS, Nuclear Energy Training, Module 3, Unit 6 Wastinghouse Reactor Physics, Sect. 3, Neutron Kinetics and Sect. 5, Core Physics HBR, Reactor Theory, Sessions 20 and 24 - 31 Zion, NUS book 3, sections 6.5, 6.6, 6.7, 12.4, 12.5.
ANSWER 1.14 (2.00)
- o. REMAIN THE SAME
- b. DECREASE
- c. INCREASE
- d. DECREASE E.5 each] (2.0)
REFERENCE Stoam Tables ANSWER 1.15 (2.00)
- a. Decrease
- b. Decrease
- c. Increase
- d. Decrease [0 5 ea.3
- 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 23
~~- isEEs557sisiEi- sEAi iEsssFEE As5 FEUi5 FE5s ANSWERS -- ZION 1&2 -85/09/30-HEMMING, W.
REFERENCE SGNPi HTFF, page'15 Cock, Westinghouse Therm. and Hyd. Prin., Chap. 7 pp. 64 - 67 Zicn, Same as Cook.
ANSWER 1.16 (2.00)
- o. 2
- b. TRUE [1.0 each3 REFERENCE IP-3, ECI Rx Theoryi Chapter 7, Pages 21, 22, and 27 DCC, Rx Theory Review Text, pp. I-5.42 - .50 Zicn, NUS book 3, sections 7.3, 7.4,-7.5, 13.2, 13.7.
- 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 24 ANSWERS -- ZION 1&2 -85/09/30-HEMMING, W.
ANSWER 2.01 (2.50)
- c. Suction from risers 50 feet above operating floor, into the RCFC's fan and cooling coils.E.53 Discharges to the inside periphery of the secondary shield to the RCP's, S/G's and then up to the cperating floor.t.53 (1.0) b.' Normal ops- four RCFC's.
Accident ops- three RCFC's. gg ,[ (0.5)
- c. Each unit is shifted to slow air flow intoamoistureseparator(andspeedandkdampersshiftdirecting (1.0)
NM EPAfilter.}
REFERENCE Zion SDi 11-4 ANSWER 2.02 (2.50)
- c. Low pump discharge pressure (80 psis)
Blackout Sequence SI Sequence (.75)
- b. Phase 'B' isolation. (0.5)
- c. Phase 'A isolation. (SI) (0.5)
- d. 2484 psis.'t.253 The piping it protects may be subjected to full RCS pressure
- if a thermal barrier HX leak developes. [.53 (.75)
REFERENCE Zicn SD 15, Pp 10-11,12,30-31.
- 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 25 ANSWERS -- ZION 182 -85/09/30-HEMMING, W.
ANSWER 2.03 (2.00)
- c. The D/G breaker to bus 147 will open automatically from the SI.E.53 Once the breaker interlocks are satisfied the D/G breaker for Bus 247 will close and reload the diesel via the SI sequencer.E.53(1.0)
- b. LBB trips all sources of fault current adjacent to the affected breaker should it fail to open after 8 cycles. E.53 Local Breaker Backup relays trip the generator if OCB's 1718 and 1819 fail to open on fault. E.53 (1.0)
REFERENCE Zicn SD 1, Pp 47,58,61 and 70.
ANSWER 2.04 (2.75)
- a. - FWP flowrate (separate for each pump).
- Feed suction header temperature.
- Feed suction header pressure. [0.25 each3 (.75)
- b. - Gland seal condenser bypass valves trip open
- Standby Cond./Cond. Booster Pump starts
- Cond. Booster Pump recire valves trip shut
- Heater Drain Level Control overrides (to allow full HDTP flow to So to the FWP). CO.5 each] (2.0)
REFERENCE Zion SDi 25a-44 ANSWER 2.05 (2.50)
- o. Motor Driven- 495 GPM (at 3099 ft of head). /@ ~
Turbine Driven- 990 GPM (at 3099 ft of head). (fd ,'I8 cas9 E S[~ (1.0)
- b. 2/3 low-low levels in 2/4 S/G's.
2/4 reactor coolant pump bus voltages low.
Any safty injection si3nal.
Any blackout signal. (1.0)
- c. A and D. (0.5) s
- 2. PLANT DESIGN INCLUDING S.)FETY AND EMERGENCY SYSTEMS PAGE 26 ANSWERS -- ZION 1&2 -85/09/30-HEMMING, W.
REFERENCE Zion S.D.12c, Pp 2,6,and 9.
ANSWER 2.06 (2.50)
- a. As the plant pressure changes so will the delta-P across the el seal thus changing the seal flowrate. [.53 Flow is high at high pressures and low at low pressures. C.53 (1.0)
- b. (Through42sealtotheRCDT)andthe #1 seal return line relief valve to the PRT (1.0)
REFERENCE Millstone System Descriptions, topic 1, lesson 2, Pp 15 and figure RP 14 Zion S.D. 3b, Pp 9-11 and drawing M-54.
. ANSWER 2.07 (2.25)
Lube oil systemi prewarming and prelubing ensures the engine will run and assume load immediately.
Air start systemi precharged reservoir insures starting air is available immediately.
Fual system; auxilary air driven pump to insure immediate. priming to the engine during starting and Day tank insures immediate reservoir of fuel.
E.25 ea syst me .5 ea reason] . (2.25)
REFERENCE f ,$
' Wh&
Millstone System Descriptions, diesel generator and support systems, Pp 5-7, 25-26, 32-33.
4 Zion S.D. 31. Pp. 3-6.
- 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 27 ANSWERS -- ZION 182 -85/09/30-HEMMING, W.
ANSWER 2 (2 5 ) ~
o S leve c.4P:r.L n.08 = % or ess. (Law P r. level.)
- 3) Loss of all charging pumps. (1.0)
(Loss of air is a faiore, not an automatic feature.)
- b. 1. Controls pressure downstream of the letdown orifices to eliminate flashing and two phase flow.
REFERENCE
! Millstone System Descriptions, topic 2, lesson 1, Pp 9, 11-12 Zion S.D.5a, Pp.39,60, and 72.
ANSWER 2.09 (2.50)
- c. (1) Reduces thermal stress to the spray line and spray no::le.
(2) Maintains pressurizer chemistry uniform with RCS (1.0)
- b. Spray line low temp alarms (0.5)
- c. Differential pressure across the reactor vessel and is aided bytheuseofscoopsintheRCS) (1.0)
REFERENCE Millstone System Descriptions, topic 1, lesson 4, Pp 6-8 and figure PR-2 Zicn S.D.3c, p.5.
4 0
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- 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 28 ANSWERS -- ZION 182 -85/09/30-HEMMING, W.
CNSWER 2.10 (3.00)
- o. Dilute mode travels only to the top of the VCT (spray noz=le).
Alternate Dilute travels to the top of the VCT and also to the suction of the charging pumps. E.753 A routine path using the spray no::le of the VCT dilutes without affecting the chemistry of the RCS.(Dilute mode). An alternate path offers a faster method when needed but partially bypasses the chemistry control of the VCT (Alternate Dilute). E.753 (1.5)
- b. Borie acid leaving solution (precipitation). C.253 .
The temperature of any system containing boric acid is kept elevated to a temperature which keeps the acid in solution.C.53 This is accomplished by heat tracing or in-tank heaters.
Systems which are not heat traced, but pass borated water, are flushed after use. C.753 (1.5)
REFERENCE Millstone System Descriptions, topic 2, lesson 2, PP 14, 19, 29-31.
Zion S.D. Sa. p.12, and 5b, p.13.
6
- 3. INSTRUMENTS AND CONTROLS PAGE 29 ANSWERS -- ZION 182 -85/09/30-HEMMING, W.
ANSWER 3.01 (2.50)
- o. INTERMEDIATE and POWER
- b. SOURCE, INTERMEDIATE and POWER
- c. NONE
- d. INTERMEDIATE and POWER
- o. INTERMEDIATE and POWER [0.5 each] (2.5)
REFERENCE Zicn SD, 6a,6beand 6c.
ANSWER 3.02 (2.00)
- o. -one channel input for the high pressure reactor trip will be active.
-the high pressure annunciator will activate. (1 0) !
- b. No.E.253 Even though one PORV receives an input from the PID controller, the valve logic requires two inputs at 2335 to activate. The second input is not rate sensitive for either valve.t.753 (1.0)
REFERENCE Zion SDI 3c-22 and 24 ANSWER 3 03 (2.00)
- o. NO MOTIONI Failure results in loop B Tavs decreasing. Rod Control C.253 uses Auctioneered Hi 3h Tav3 [.253 (0.5)
- b. ROOS INI Failed Pimp will generate a maximum rate change due to an <
t.53 instantaneous power mismatch C.53. C-5 will activate which will prevent any outward auto rod motion C.253. (1.25)
- c. RODS INI Failed NI channel will generate a maximum rate change due
[.53 to an instaneous power mismatch E.53. C-2 rod stop will activate preventin3 any auto or manual rod motion C.253 (1.25) 4 REFERENCE Zion SDI 88-11 through 13 4
i
- . , , , _ _ - . _ _ _ _ _ _ . _ . - _ _ . . . _ __ _ . _ . _ . , . . _ . , . _ _ . . . _ . . _ _ , _ _ _ ..-, _.....~ ___ ._ _ _
E
- 3. INSTRUMENTS AND CONTROLS PACE 30 ANSWERS -- ZION 182 -85/09/30-HEMNING, W.
ANSWER 3.04 (3.00')
- Low Pressuri er Pressure E.253, P-11 E.253.
- High Steam Flow with Low Steam Pressure or Lo-Lo Tavs C.253, P-12 E.253.
- High Steamline Differential Pressure C.253, R.C. Loop Isolation Valve Formissive C.253.
- High Containment Pressure C.253, No Permissive [.253. (2.0)
- _0 s ep_ - " T- L e
Zion SDt 12b-31 and 32 ANSWER 3.05 (3.00)
- o. HIGH P2R LEVELI Failure causes chargin3 flow to So to minimum which E.53 allows p:r. level to decrease. Low p:r. level will isolate letdown causins p:r. level to rise until a hi 3h level trip occurs [1.03. (1.5)
- b. LOW PZR FRESSUREI High Loop /Auctioneered Tavs causes rods to C.53 insert. Decreasing Tave will cause p:r pressure
. and level to decrease and trip the reactor on
{ low pressure. C1.03 (1.5)
) REFERENCE Zion SDI Chapter 9 l ANSWER 3.06 (2.50)
- o. Cteam pressure is used to compensate the steam flow signal for i; density variations in the steam caused by pressure changes as power is altered. (1 0)
- b. Indicated steam flow will be higher than actual steam flow C.53
- due to the over-compensating signal from the steam pressure channel.
50% steam pressure is higher than 100% steam pressure and will
, create a compensatin3 Si3nal that is 3reater than needed C1.03. (1.5)
)
i REFERENCE Millstone System Descriptions, topic 6, lesson 9, p 18.
i Zinn S.D. 25be p.14.
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- 3. INSTRUMENTS AND. CONTROLS PAGE 31 3
I ANSWERS -- ZION 182 -85/09/30-HEMMING, W.
i 1
i i ANSWER 3.07 (3.00)
- o. Coincidence is the number of input channels required to l initiate a protective action as compared to the total number of input channels. (1.0) l
- b. Minimum is one more channel than is required to initiate the Protective action. (1.0)
] c. High-high containment pressure,C.53 to prevent inadvertant initiation of containment spray if power is lost. C.53 (1.0)
REFERENCE
! Millstone Systems Descriptions, topic 7, lesson le2, and 3, pp 8-11, 73
! cnd topic 8, lesson 4, p 6.
Zion S.D. 9, p.13, S.D. 12b, p.3.
ANSWER 3.08 (3.00) i c. 1,3
- b. 4
- c, 2 i d. 1,3
- o. 1,2 i f. 5 l 3 5 1 h. 1,3 C.25 each response 3 (3.0)
, REFERENCE l VCS Plant System Descriptions, IC-1, pp 19-23
- Zion S.D. 21c.
l ANSWER 3.09 (1.00)
I b.
I REFERENCE
- VCS Plant System Descriptions, IC-2, p. 10
- Zicn S.D.25b, Pp. 2-3.
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- 3. INSTRUMENTS AND CONTROLS PAGE 32
' ANSWERS -- ZION 182 -85/09/30-HEMNING, W.
ANSWER 3 10 (1.00)
REFERENCE VCS Plant System Descriptions, IC-3, p. 9 Zion S.D.3e, p.23.- ,
ANSWER 3.11 (1.00) b.
REFERENCE VCS Plant System Descriptions, IC-9, p. 47 Zicn S.D.9, P.22.
ANSWER 3.12 (1.00) ce REFERENCE VCS Plant System Descriptions, IC-6, p. 25 Zion S.D.9, p.23 and T.S. Section 1 1, p.9-10.
m .
- 4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 33
~~~Rd656E66f65E~66 T66E~~~~~~~~~~~~~~~~~~~~~~~~
ANSWERS -- ZION 182 -85/09/30-HEMMING, W.
ANSWER 4.01 (2.50)
- o. - Common blowdown valve shuts.
- Individual sample valves shut. (1.0)
- b. SurSe tank vent valve shuts. ("No action' is acceptable if it is assumed that the valve is blocked open.) (0.5)
- c. Fire sump pumps discharge shuts. (0.5)
- d. No action. (0.5)
REFERENCE Zicn SDi 13a-7, 13a-37 and 38 ANSWER 4.02 (2.50)
- n. 100 (0.5)
- b. 320 (0.5)
- c. 200 (185 accepted for partial credit) (0.5) d.1) 50 E0.53
- 2) 200 [0.53 (1.0)
REFERENCE Zicn GOP-li pp 7 through 10 ANSWER 4.03 (2.50)
- o. - Emergency borate (100 ppm)
- Reinsert all control banks
- Recalculate ECC (and adjust boron if necessary) [0.33 each3 (1.0)
- b. - Insure adequate SDM
- Insure ejected rod reactivity limits maintained
- Insure acceptable core power distribution limits E0.5 each] (1.5)
REFERENCE Zicn GOP-21 pp 7 and 13
- 4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 34
~~~~
R 656E6EfEdE~d6NTE6E~~~~~~~~~~~~~~~~~~~~~~~~
ANSWERS -- ZION 1&2 -85/09/30-HEMMING, W.
ANSWER 4.04 (1.50)
- a. INADVERTENT TRIP: A reactor trip that results from personnel Grror or from minor equipment malfunction and that can be demonstrated to be unrelated with a reactor plant transient or any valid protective system actuation. (.75)
- b. DEGREE OF REDUNDANCY: The degree of redundancy is the difference >
between the number of operable channels and the minimum number of these channels which, when tripped, will cause an automatic trip.
(.75)
REFERENCE Zion T.S.; p_2 and 5 ANSWER 4.05 (1.00) c.
REFERENCE 10 CFR 20.3 ANSWER 4.06 (1.00) b.
REFERENCE 10 CFR 20.101.
ANSWER 4.07 (2.50)
- e. -P=r. pressure drops below 1815 psis.
-P=r. level drops below 10%.
-RCS subcooling drops below 35 F. E.5 es.3 (1.5)
- b. The P-4 (reactor tripped) input into the SI reset logic blocks the automatic initiation signals from activating the SI logic until the P-4 signal is removed if even momentarily. (1.0) l
- 4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 35
- ~~~~~~~~~~~~~~~~~~~~~~~~
~~~~R5656L66565L 66HTR6L ANSWERS -- ZION 1R2 -85/09/30-HEMMING, W.
REFERENCE Zion.EOP-0, Pp. 10-11 and figure 12b-II-C5.
ANSWER 4.08 (1.50)
Hnt les RTO's pegged high, or 5 or more core exit thermocouples cbeve 1200 F. AND No ECCS flow is being delivered to the RCS. AND No cuxiliary feedwater being delivered to the intact S/G's. [.5 ea3 (1.5)
REFERENCE Zion E0P-11, p.2.
ANSWER 4.09 (2.00)
- 1. Through MOV-VC 8104.
- 2. Through FCV-VC 110A and 110B.
- 3. Through VC 8439.
- 4. Through the BIT. NOT PREFERRED. E.5 ea3 (2.0)
REFERENCE Zicn E0P-5, p.4.
ANSWER 4.10 (2.50)
- o. If pressurizer level cannot be maintained.C.53 You are directed to proceed according to E0P-0. E.53 (1.0)
- b. May be closed when RCS pressure is BELOW 2000 psig. [.53 Must be reopened when RCS pressure increases to 2000 psis. E.53 Reopined to insure adequate flow through the CCP's. The higher the_RCS pressure the lower the flow through the pumps into the system. E.53 (1.5)
r -
- 4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 36
~~~~ RdD56EUhEEAE~CbkTRUE~~~~~~~~~~~~~~~~~~~~~~~~
ANSWERS -- ZION 1&2 -85/09/30-HEMMING, W.
REFERENCE Zion AOP-19, p.3 and S.D. Sa, p.6.
ANSWER 4.11 (3.00)
O. One hour. E.53 No operationsare allowed that would cause dilution and core outlet temperature must be maintained at least 10 F below saturation temperature. E.753 (1.25)
- 6. 1. Trip running RHR pump (s).
Determine reason for closure.
Reopen valve.
Start a RHR pump.
- 2. Verify adequate RHR flow.
Throttle HCV which is still operable as required to maintain RHR cooling.
[.25 ea.3 (1.75)
REFERENCE 2 ion T.S. 3.3.1.A.3, p.73a and AOP-20, p.2.
ANSWER 4 12 (2.50) 5 oinute delay. (0.5)
Tho affected: 6D/G starts.
vjD/G output breaker closes.
Smain feed breaker to 4 KV ESF bus opens.
gg $ reserve feed breaker to 4 KV ESF bus opens. [.25 ea3 (1.0)
N seconds: OCCW auto-starts.
a) Service Water auto-starts.
4)RCFC's auto-start.
3 Auxiliary Feedwater auto-starts. (148/149 only)
C.25 ea3 (1.0)
REFERENCE Zion AOP-21, p.3.
U. S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION FACILITY: ZION 1&2 REACTOR TYPE! PWR-WEC4 DATE ADMINISTERED 85/09/30 EXAMINER: HIGGINS, R.
APPLICANT! ________________________. "*%3 INSTRUCTIONS TO APPLICANT!
Uao ceparate paper for the answers. Write answers on one side only.
Stcple question sheet on top of the answer sheets. Points for each quantion are indicated in parentheses after the question. The passing secd3 requires at least 70% in each category and a final grade of at 1 cost 80%. Examination papers will be Picked up six (6) hours after tho oxamination starts.
% OF CATEGORY % OF APPLICANT'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY '
25.00 25.00
____ .._ ___ .. .._______ _ ________ 5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND THERMODYNAMICS 25 0 25.00
___I__0__ ______ _____ .____ ... ___. 6. PLANT SYSTEMS DESIGNe CONTROL, AND INSTRUMENTATION 25 0 25.00
...I__0 __ ______ ___________ ________ 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL
. Ib __ _ Ib .... _____. ..._____ 8. ADMINISTRATIVE PROCEDURES, CONDITIONSe AND LIMITATIONS 100.00 100.00 TOTALS FINAL GRADE _________________%
D11 eork done on this examination is my own. I have neither 31vCn nor received aid.
APPL 5CAUiI5~555UAYUR5~~~~~~~~~~~~~~
,s
- 5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 2
--- g gggggggggggg----------------- --------------------
QUESTION 5 01 (2.50) ,
Cetpare the CALCULATED Estimated Critical Position (ECP) for a otartup to be performed 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after a trip from 100% power, to the ACTUAL. control rod position if the followins events / conditions cccurred. Consider each indeper.dently. Limit your answer to HIGHER thon, LOWER than, or SAME as the ECP.
- c. One reactor coolant pump is stopped two minutes prior to
, criticality. (0.5) -
- b. The startup is delayed until 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after the trip. (0.5)
- c. The steam dump pressure setpoint is increased to a value just below the Steam Generator PORV setpoint. (0.5)
- d. Condenser vacuum is reduced by 4 inches of Mercury. (0.5)
- o. All Steam Generator levels are being raised'by 5% as the ECP is reached. (0.5)
GUESTION 5 02 (2.00) i A. Does Beta bar effective Increase, Decrease, or Remain the Same, from BOL to EOL? (Briefly explain your choice.) (1 0)
B. For equivalent positive reactivity additions to a critical reactor, will the SUR be the Same, Largere or Smaller at EOL compared to BOL? (no explanation necessary) (1.0) i
- OUESTION 5.03 (1 50)
Teo identical reactors are taken critical usin3 continous rod withdrawal.
Roactor A has a rod speed of 48 steps per minute and reactor B has a rod spood of 24 steps per minuts.
j o. Which reactor will obtain criticality first? (0.5) ,
- b. Which reactor will have the highert source range counts at criticality? (0.5)
- c. How will 10-0 critical rod heights compare in the two reactors? (0.5)
(** sus CATEGORY 05 CONTINUED ON NEXT PAGE sassa) l
- 5. THEORY OF NUCLEAR POWER PLANT OPERATIONe FLUIDS, AND PAGE 3
- ----------. ---------------~~-----~~--
QUESTION 5.04 ( .50)
TRUE or FALSE?
At EOL, the Doppler Temperature Coefficient is more negative due to en increase in the quantity of Pu-240 in the fuel.
QUESTION 5.05 ( .50)
TRUE or FALSE 7 With all rods out, and a constant boron concentration (ppm), the MTC becomes more negative as RCS temperature (Tavg) increases.
QUESTION 5.06 (2.00)
- c. Provide TWO reasons for Xenon contributing more negative reactivity at full power than Samarium. (1.0)
- b. Explain why you agree or disagree with the following statement!
- Equilibrius Samarium concentration at 50% power is approximately half its concentration at 100% power.' (1.0)
QUESTION 5.07 (1.00)
At BOL, the components of the power defect in an INCREASING order of significance (reactivity value) aret
- a. Void, Ooppler, MTC
- b. Void, MTC, Doppler
- c. MTC, Void, Doppler
- d. MTC, Doppler, Void (smss: CATECORY 05 CONTINUED ON NEXT PACE susse) i
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- 5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDSe AND PAGE 4 gg7 g...___....__....--.... __.............
I I
GUESTION 5.08 (1.00) !
Which of the following statements concernin3 the power defect is correct?
- o. The power defect is the difference between the measured power I coefficient and the predicted power coefficient.
i b. The power defect increases the rod worth requirements necessary 4
! to raintain the desired shutdown margin following a reactor trip.
i c. Because of the higher boron concentratione the power defect is ;
, more negative at beginnin3 of core life.
j de The power defect necessitates the use of a ramped Tavs program
) to maintain an adequate Reactor Coolant System subcooling margin. t l '
QUESTION 5.09 (1.00) i During fuel 1cadin3, which of the following will have NO effect on the I shape of a 1/M plot? t
,! c. Location of the neutron source in the core.
- b. Strenath of the neutron source in the core.
- c. Location of the neutron detectors around the core. i
- d. Order of placement of fuel assemblies in the core.
QUESTION 5.10 (1.00) !
4 Tho reactor is critical at 10,000 ops when a S/G PORV fatis open. t
, ossuming BOL conditionse no rod motione and no reactor tripe choose ,
1 tho answer below that best describes the values of Tave and nuclear l poeor for the resulting new steady state. (PDAH = Point of adding i i hoat)
- o. Final Tav3 3reater than initial Tavs, Final power above POAH. '
- b. Final Tavs greater than initial Tavge Final power at POAH.
t
- c. Final Tava less than initial Tavge Final power at POAH,
! d. Final Tavs less than initial Tavs, Final power above PDAH.
4 (maans CATECORY 05 CONTINUED ON NEXT PACE assum)
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- 5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 5 1
i 5 QUESTION 5 11 (1 00)
Tho Moderator Temperature Coefficient (MTC) varies with certain plant '
ccnditions. Concerning these variations, which of the followins it' correct?
l l o. The MTC becomes more negative as boron concentration is increased.
, b. The MTC causes axial flux distribution to be tilted towards the -
i top of the core at BOL.
}
j c. The MTC varies as temperature changes because of the non-linear
- density changes of water as temperature changes.
l d. The MTC is not permitted by Technical Specifications to be positive 1 in any plant operating modes.
i QUESTION 5.12 (1.50) l o. At what axial location in a PWR core is the critical heat flux j at the MAXIMUM 7 (Limit your answer to top, middle, or bottom.) (0.5)
- b. How does the MINIMUM critical heat flux change (increase, decrease
- not chan3e) as the following parameters are INCREASED? Consider cach separately. (1.0)
]
- 1. Tave
- 2. RCS pressure
- 3. RCS flow I
OUESTION 5.13 (2.50)
I
- a. If steam Goes throu3h a throttling process, specifically as in a leak
] from the high pressure main steam header, indicate whether the follow-ing parameters will INCREASE, DECREASE, or REMAIN THE SAME. (2.0) i 1. Enthalpy
- 2. Pressure
- 3. Entropy
- 4. Temperature
- b. Will the steam become subcooled, saturated or superheated as it lects out? (0.5)
, (zussa CATEGORY 05 CONTINUED ON NEXT PAGE sussa) f e
F
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=
G. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 6
--- g ggggggg--------------------------------------
-QUESTION 5.14 (1.00) s Wh3n the flow rate through a centrifugal pump is increased by openin3 the diccharge valve, the required NPSH _______, and the available NPSH ______.
(0) increasest increases (b) increasest decreases (c) decreasest increases 1
(d) decreasest decreases GUESTION 5.15 (1 50)
TRUE or FALSE?
- o. The faster a centrifugal pump rotates, the greater the NpSH required to prevent cavitation. (0.5)
- b. One of the pump laws for centrifugal pumps states that the volumetric flow rate is inversely proportional to the speed of the pump. (0.5)
- c. Pump runout is the term used to describe the condition of a centrifugal pump runnin3 with no volumetric flow rate. (0.5)
OUESTION 5 16 (1.00) 7 In crder to maintain a 200 F subcooling margin in the RCS when reducing
, RCS pressure to 1600 psig, steam generator pressure must be reduced
- to opproximatelyt
- o. 245 psis
- b. 445 psi 3
- c. 645 psi 3
- d. 845 psis i
(masas CATEGORY 05 CONTINUED ON NEXT PAGE sassa)
- 5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 7 QUESTION 5.17 (1.00)
Th2 reactor is operating at 30% power when one RCP trips. Assuming NO rocetor trip or turbine load change occur, which of the followin3 percmeters will DECREASE?
- c. Flow in operating reactor coolant loops
- b. Core delta T
- c. Reactor vessel delta P
- d. Steam generator pressure in affected loop QUESTION 5.18 (1.00)
Th2 main condenser must remove more heat energy to condense ...
- e. One pound of steam at 0 psia.
- b. One pound of steam at 300 psia <
- c. Two pounds of steam at 600 psia.
- d. Two pounds of stesa at 1200 psia.
QUESTION 5.19 (1.50)
- n. With the plant operating at 85% power and all systems in a normal / automatic configuration, the operator borates 100 PCM.
Shutdown Margin will: (1.0)
- 1. Increase
- 2. Increases until rods move
- 3. Decrease
- 4. Decreases until rods move
- 5. Remain unchanged, whether or not rods move
- b. The Shutdown Margin required by Technical Specifications for Cold Shutdown condition is ________% DeltaK/K. (0.5)
(**xxx END OF CATEGORY 05 xxxur) i l
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- 6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 8 GUESTION 6.01 (1.50)
Indicate which, OT delta-T, OP delta-T, or BOTH (OT delta-T and OP delta-T) protection instruments, apply to each of the following statements.
- a. Backup for the high neutron flux trip. (0.5)
- b. Circuitry dynamically compensates for piping delays to the loop temperature detectors. (0.5)
- c. Requires RCS pressure within the high and low reactor trip setpoints in order to be valid. (0.5)
OUESTION 6.02 (2.00)
- a. Describe the instrument LOGIC and SETPOINTS necessary to :: tract-the Reactor Coolant 1 and 2 loop low flow trips in the protection system. (1.5)
- b. What core protection is provided by the undervoltage and underfrequency low flow ~ reactor trips. (0.5) 2 QUESTION 6.03 (3.00)
Answer the following concerning the Spent Fuel Pool (SFP):
- c. Why is SFP level maintained between +/- 3' of normal? (1.0)
- b. List 4 normal and alternate sources of makeup water for the SFP. (1.0)
- c. How is baron concentration normally maintained in the SFP? (1.0)
QUESTION 6.04 (3.00)
The following Ovestions concern the Component Cooling Water System.
- a. Name THREE CCW system alarms that could indicate a RCS to CCW 1eak. (1.5) b.- Describe, in detail, how the CCW system is protected against an overpressure condition if a RCS to CCW rupture occurred in the RCP Thermal Barrier. (1.5)
(***xx CATEGORY 06 CONTINUED ON NEXT PAGE musum) e
- 6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 9 GUESTION 6.05 (2.50)
The-following concern the CVCS at Zion,
- s. What are the TWO functions (purposes) -r the tesss+ eTh38.re Flow Control Valve (PCV-131)? (1.0)
- b. If left in automatic control, what p- L)>' wh6, .d PCV-131 be found in two minutes after a safts ?? juttl..., initiation? (0.5)
- c. Why is letdown flow limited to 120 spm? (0.5)
- d. With only the PD pump operating at power, which valve (s) is/are utilized to vary RCP seal injection flow? (Either noun name or numbers acceptable.) (0.5)
GUESTION 6.06 (2.00)
- a. State the INITIAL direction of rod motion for the following events. Briefly explain.
- 1. First stage pressure fails high at 50% power.
- 2. Feed reSulating valve fails open at 90% power. (1.0)
- b. Briefly explain the reason for including the following inputs into the Rod Control System.
- 1. Tavs
- 2. Neutron Flux. (1.0)
(mmmxx CATEGORY 06 CONTINUED ON NEXT PAGE **xxx)
_____.__________.m_
2
'6.- PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 10 QUESTION 6.07 (3.00)
- e. If while operating at 100% power, the pressure compensation signal to the SGWLC system fails hight
- 1. Explain the immediate response of feedwater flow. (1.0)
- 2. What would be the long term effect on steam generator level?
Assume no operator action or trip actuation. (0.5)
- b. What. input signal (s) is/are used as the reference signal for the feedwater pump speed control system programmed Delta P? (0.5)
- c. List the FOUR Protective features derived from monitored Steam Generator parameters (Setpoints and coincidence not required). (1.0)
GUESTION 6.08 (4.00)
O. List the automatic start signals for:
- 1. STEAM DRIVEN auxiliary feed pumps.
- 2. MOTOR DRIVEN auxiliary feed pumps. (3.5)
- b. What valves are automatically shut with any of the auto start signals in 'a' above? (0.5)
QUESTION 6.09 (2.00)
If the available Feedwater Pump NPSH decreases to 275 psis, an alarm counds. What other FOUR actions automatically occur when a low FWD
'cuction pressure condition exists? (2.0)
(mxxxx CATEGORY 06 CONTINUED ON NEXT PAGE muumu)
- 6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 11 GUESTION 6.10 (2.00)
Indicate which of the Excr.re Nuclear Instrumentation Ranges (SOURCE, INTERMEDIATE, or POWER), will correctly match with th9 following statements. More than one may apply to each.
- o. Provides a direct input to the Rod Control System.
- b. Has a reactor trip function that is blocked at some time between startup and full power operation.
- c. Utilizes a Baron-10 coating in it's detectors.
- d. Operates in the ' Ion. Chamber" region of the ' Gas Filled Detector Characteristic Curve'. (2.0)
(xxxxx END OF CATEGORY 06 xxxxx) s L
}
4
- 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 12
~~~~R5656[6G565E 66 TR6E~~~~~~~~~~~~~~~~~~~~~~~~
QUESTION 7.01 (2.50) 1
, Document 10 CFR 20 provides regulations for radiation exposure at th9 Zion facility. Answer the following questions in accordance with 10 CFR 20.
- a. The whole body exposure limit provided is 1.25 Rem / Quarter.
Under what THREE non-emergency conditions / criteria may this ;
limit be exceeded? (1.5)
- b. Personnel monitoring.(film badge, dosimeter, etc.) is required in three situations. Provide TWO of these situations. (1.0)
GUESTION 7.02 (4.00)
- c. What THREE indications ' identify
- a specific ruptured steam Senerator (S/G) according to E0P-10, " Steam Generator Tube Rupture *(SGTR) procedure? (1.5)
- b. After the ruptured S/G has been identified, the MSIV is required to be shut. What THREE other actions / verifications are required by E0P-10 to isolate the ruptured S/G? (1.5)
- c. What specific actions are required to initiate RCS cooldown if the ruptured E/G MSIV will not shut? (1.0)
QUESTION 7.03 (3.00)
During refueling operations, RT-AR03 alarms indicating high radiation in the Fuel Building Pool Area.
- a. What automatic actions take place? (1.0)
- b. What are the Fuel Handling Supervisors immediate responsi-bilities as stated in FOP-6 (Fuel Handling Emergency)? (1.0)
- c. If Health Physics reports there is a high level of tritium in the area, what protective measures must be taken prior to entry into this area? (1.0) 1 4
-(mmmmm CATEGORY 07 CONTINUED ON NEXT PAGE musam)
.. ,, _w - - - , . . _
- 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 13
~~~~~~~~~~~~~~~~~~~~~~~~
~~~~R565 L55iEAC E5NTRUL QUESTION 7.04 (2.00)
- c. List FOUR parameters used to verify adequate z'rt .ul... ?/*+44F natural c i r cul a t i o n. c crM i ' i;r. ; . (1.0)
- b. During natural circulation cooldown, a steam bubble may form in the reactor vessel head area.
- 1. What is the primary indication of this bubble formation? (0.5)
- 2. Why is the bubble expected to occur in this area first? (0.5)
QUESTION 7.05 (3.50)
FILL IN THE BLANKS for GOP-1 precautions.
- a. The RCS oxySen concentration must be less than _____ ppm prior to raising RCS temperature above ______ degrees F.
, temperature exceeds ______ degrees F.
- c. A minimum of one Source Range channel shall be in operation with
_________ and _________ indication anytime the reactor is shutdown.
- d. If any RCP's seal leakoff flow does not increase by at least ____
spm after ther RCS is pressurized to approximately _______ psis asid the seal leakoff valve is open, do not start the RCP. (3.5)
(xxxxx CATEGORY 07 CONTINUED ON NEXT PAGE xxxxx)
- 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 14
~~~~R d656[66I6d[~66 TR6[~~~~~~~~~~~~~~~~~~~~~~~~
GUESTION 7.06 (2.00)
Answer the following according to GOP-2.
- a. The shutdown banks do not need to be withdrawn prior to dilution if what condition is met? (0.5)
- b. Which SI must be unblocked prior to diluting below the required cold shutdown boron concentration? (0.5)
- c. Why must the startup of Main Feedwater Pump B or C be done only when ready to go off Auxiliary Feedwater? (0.5)
- d. Why is it required that the Main Turbine bearing lift pump control switch be placed in the AUTO (after-start) position at the end of the turbine oil pump interlock checks? (0.5)
(nuxxx CATEGORY 07 CONTINUED ON NEXT PAGE xxxxx).
- 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 15
~ ~~~~~~~~~~~~~~~~~~~~~~~~
~~~~R5656L6GECEL 66NTR6L GUESTION 7.07 (3.00)
POWER HISTORY 8/1 -- 0800 hrs. the reactor is at 1% power after a refueling shut-down with all physics testing complete. Power was raised to 22% max.
at 1800 hrs on 8/1.
8/7 -- 1300 hrs. Power ramp commenced to 50% when at 1430 hrs a trip occured at 32% power from a feed pump failure.
8/11 -- 0030 hrs. the reactor is at PDAH. At 0830 50% power is achieved.
8/15 -- 0800 hrs commenced raising power to 90% power, which is obtained at 1200 hrs. on 8/16.
8/16 - power is held at 90% until 1735 hrs. on 8/18 when the reactor is tripped due to an instrument tech. error.
- a. Describe any fuel conditioning limit violations. (2.0)
- b. ASSUME: Control rods for bank D were at 220 steps prior to the trip from 90% power.
The NORMAL power rate of change is 20% per hout unless special limits apply.
ALL POWER CHANGE IS TO BE CONSIDERED WITH RODS ONLY, NEGLECT BORON CHANGE REQUIREMENTS.
What would be the minimum time required to achieve 100% power with rods at 220 steps, from the time of reaching 1% power on the recovery from 90%?
QUESTION 7.08 (2.50)
, s. According to E0P-0 what are the RCP termination criteria. (1.5)
- b. What additional action must be done as a result of the RCP termination and WHY? (1.0)
(*sxxx CATEGORY 07 CONTINUED ON NEXT PAGE musam) l L
-7. PROCEDURES - NORMAL,-ABNORMAL, EMERGENCY AND PAGE 16
~~~~~~~~~~~~~~~~~~~~~~~~
~~~~R I656L6656d['66HTR6L
-QUESTION 7.09 (2.50)
- o. Describe the immediate action steps to determine which instrument
' bus is lost according to ADP-15, ' Loss of Instrument Bus'. (1.5)
- b. How is power restored to the bus? (1.0)
F i
4 1
(m**** END OF CATEGORY 07 mmmmm) i l
- 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 17 QUESTION 8.01 (1.50)
Lict THREE reasons / bases why control rods must be riaintained above the Toch. Spec. minimum insertion limit during power operation.
QUESTION 8.02 (3.00)
Th2 concentration of the boric acid solution in the Boron Injection Tank (BIT) shall be verified once a week in accordance with Technical
. Specification 4.1.8 E. The chemist sampled the BIT on the following cch dule. (All samples taken at 1200 hours0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br />).
Aug 1 --- Aug 8 ---Aug 16 --- Aug 24 --- AUG 31
- c. EXPLAIN why surveillance time interval requirements were or were not exceeded on AUG 16. (1.5)
- b. EXPLAIN why surveillance time interval requirements were or were not exceeded on Aug 24. (1.5)
GUESTION 8.03 (2.00)
What are the THREE provisions that must be met before a temporary change con be made to an approved operating procedure, according to Technical Specifications?
QUESTION 8.04 (1.00)
According to Technical Specifications, if a safety limit is exceeded the NRC Operations Center shall be notified within _____.
- a. 15 minutes
- b. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />
- c. 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />
- d. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (xxxxx CATEGORY 08 CONTINUED ON NEXT PAGE xxxxx)
- 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 18 GUESTION 8.05 (1.00)
Which of the following statements concerning the AFD requirements is correct?
- a. Above 90%, within 30 minutes of going outside the target band, either restore indicated AFD to within the target band or reduce power to less than 90%.
- b. If the axial flux difference alarms are out of service, the AFD shall shall be lo39ed every hour for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and half-hourly thereafter until the alarms are returned to operable.
- c. Below 50% power, penalty points are accumulated at one point for every minute outside the target band.
- d. Power level shall not be increased above 50% unless the AFD is within the target band.
, GUESTION 8.06 (1.00)
Which of the following statements concerning Shutdown Margin (SDM) c onsider at: ions is correct?
- a. With Tavs less than 200 degrees, the SDM requirements are increased because of the possibility of a positive MTC.
- b. The most restrictive condition for SDH requirements occur at EOL, with Tavs at no load temperature, and is associated with a rod ejection accident.
- c. When in Mode 2 with keff less than 1.0, adequate SDM is ensured by verifying the predicted critical rod position is above the rod insertion limits.
- d. If one rod is known to be partially inserted and untrippable an increased allowance for the entire rod worth shall be made to the SDM requirements.
(xxxxx CATEGORY 08 CONTINUED ON NEXT PAGE mamma) l I
4 l
- 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 19 QUESTION 8.07 (3.00) ,
The following concern the Plant Emergency Procedures.
- a. State the title of the person who is responsible for the initiation of the INITIAL emergency action. Who is responsible i f this person is unavailable or incapacitated? (1.0)
- b. A Site Evacuation of non-essential personnel has been determined necessary.
- 1. Where is the main assembly area? (0.5)
- 2. Provide THREE conditions that would preclude evacuation of personnel, assume personnel accountability complete. (1.5)
GUESTION 8.08 (1.00)
Which of the following is a function / responsibility of the Shift Engineer according to ZAP-0-1, Admittin3 and Control of Westinghouse Trainees?
- a. Authorizing more than five trainees per Westinghouse Instructor,
- b. Verify instructors are on the approved list.
- c. Advise the instructor as to the status of the plant.
- d. Inform Control Room personnel the areas in which observations / training will be performed.
i (rrunw CATEGORY 08 CONTINUED ON NEXT PAGE ummum)
, . - .- - - r-y , s a _ - _ , - . , , , , - . . . _ - - , __
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- 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 20 GUESTION 8.09 (3.00)
Indicate whether the following is a primary function of the Shift Engineer OR Shift Foreman (licensed), according to ZAP 1-151-1, Station Organization.
- c. Authorize Surveillance.
- b. Act as Fire Chief.
- c. Submit work requests and coordinate operations /maintanence activities.
- d. Placing equipment in or out of service.
- e. Review Unit logs.
! f. Ensure unqualified operating personnel perform evolutions in the presence of qualified personnel.
QUESTION 8.10 (1.50)
What is the bases / reason for the Technical Specification requirement to reduce Tavs to less *~ . 600 de3rees when specific activity limits are exceeded?
GUESTION 8.11 (2.00)
Provide TWO of the four Shift Engineer responsibilities concerning "High Radiation Area Access Control', ZAP 5-51-15.
QUESTION 8.12 (2.40)
What are FOUR of the five means of protection taken to prevent a low temp-oroture over~ pressurization accident when RCS temperature is below 250-F cnd the vessel head is installed, in accordance with Technical Specificat-inns?
(mmmmm CATEGORY 08 CONTINUED ON NE'T X PAGE **mmm)
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(
B. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 21 QUESTION 8.13 (2.60)
Pricary to secondary leakage through the steam generator tubes has two :
Technical Specification leakage rate criteria. j
! 1. What are the allowable leakage rates? (1.0)
- 2. What is the bases for each of the leakage rates? (1.6) i 1
i (zxxxx END OF CATEGORY 08 musum)
- (musuruxxxxxxx END OF EXAMINATION mammanummmmmmax)
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- 5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 22 ANSWERS -- ZION 1&2 -85/09/30-HIGGINS, R.
ANSWER 5.01 (2.50)
- c. SAME
- b. HIGHER
- c. HIGHER
- d. SAME
- o. LOWER E0.5 each3 (2.5)
REFERENCE SHNPP RT-LP-3.13, p 10-15 and RT-TP-262.
NUS Nuclear Energy Training (NET), 12.5-1.
ANSWER 5.02 (2.00)
- o. Decreases E0 253 Pu 239 concentration increases (while U 235 concentration decreases) [0.753. (1.0)
- b. Larger SUR. (1.0)
REFERENCE SHNPP RT-LP-1.6, p 23,24.
i NUS-NET, 5.3-1 to-3.
ANSWER 5.03 (1.50)
. o. A
- b. B -
- c. Same rod height CO.5 each]
REFERENCE SHNPF RT-LP-1.6, p39-46.
NUS-NET, 12.4-2.
l
g.
- 5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 23 ANSWERS -- ZION 1&2 -85/09/30-HIGGINS, R.
ANSWER 5.04 ( .50)
Trua.
REFERENCE SHNPP RT-LP-1.9, p 19.
NUS-NET, 13.4-3 and A.9-1.
ANSWER 5.05 ( .50)
Truo. E1.03 REFERENCE SHNPP RT-LP-1.10, p 11-16,20-22.
NUS-NET, 9.2-1 to-4.
ANSWER 5.06 (2.00)
- o. 1. Higher fission yield.
- 2. Larser (thermal) absorbtion cross section (1.0)
- b. Disagree Co.43 Equilibrium Sa concentration is not power dependent.[0.63 (1.0)
REFERENCE SHNPP RT-LP-1.11, p 9-21.
NUS-NET, 10.5-1,-2.
ANSWER 5.07 (1.00) b REFERENCE Wactinghouse Reactor Physics, pp. I-5.12, 25, and 27 SHNPP RT-LP-1.10, p 14,15.
NUS-NET, 8.2,4,5,6,-1 and 9.6-1.
L
- 5. THEORY OF NULLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 24 ANSWERS -- ZION 182 -85/09/30-HIGGINS, R.
ANSWER 5.08 (1.00) b REFERENCE Wactinghouse Reactor Physics, pp. I-5.26 & 27 SHNPP RT-LP-1.10, p 13-15.
NUS-NET, 8.6-1.
ANSWER 5.09 (1.00) b REFERENCE Wactinghouse Reactor Physics, pp. I-4.19 - 24.
SHNPP RT-LP-1.7.
NUS-NET, 12.3-1 to-5.
ANSWER 5.10 (1.00) d REFERENCE Wactinghouse Reactor Physics, Section I-5, MTC and Power Defect SHNPP RT-LP-1.6, p 36-41.
NUS-NET, 13.5-2.
ANSWER 5.11 (1.00) c REFERENCE W20tinghouse Reactor Physics, pp. I-5.2 - 16 SHNPP RT-LP-1.10, p 9-12.
NUS-NET, 8.3-1; 9.2-1 to-4.
L
e
- 5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 25 ANSWERS -- ZION 182 -85/09/30-HIGGINS, R.
ANSWER 5.12 (1.50)
- o. Bottom of the core. (0.5)
- b. 1. Decrease
- 2. Increase
- 3. Increase CO.33 each3 (1.0)
REFERENCE GPNT Vol III, Ch. 2, Sect E, p. 2-164 thru 167.
SHNPP HT-LP-1.2, p 10-14.
Wastinghouse Thermal-Hydraulic Principles and Applications to the PWR.(WTH) 13-19,-24,-34.
ANSWER 5.13 (2.50)
- c. 1. REMAIN THE SAME
- 2. DECREASE
- 3. INCREASE
- 4. DECREASE
- b. Superheated. [0.5 each3 REFERENCE Stoon Tables SHNPP FF-LP-1.1, p 32-34.
HTH, 10-67 to-73.
ANSWER 5 14 (1.00) b REFERENCE FF-LP-1.1, p 27-30.
WTH, 10-53 to-56.
i I
l L
- 5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 26
.J ANSWERS -- ZION la2 -85/09/30-HIGGINS, R.
ANSWER 5.15 (1.50)
- o. True
- b. False
- c. False C0.5 each3 REFERENCE W2stinghouse Thermal Science, Chapter 10, Pp. 41-49 SHNPP FF-LP-1.1, p 21-23, 27-30.
WTH, 10-35 to-49.
j ANSWER 5.16 (1.00) as REFERENCE SHNPP Thermo-LP-1.1 and steam tables KA002/000,K5.01,3.1 Cook-Westinghouse Thermal Science, Chapter 2,Pp 63-70,79. /020,K5.06,3 4 l
Steem Tables.
ANSWER 5.17 (1.00) c REFERENCE
. Gen 3ral Physics, HTFF - Fluid Flow Applications for Systems and Components.
1 SHNPP TRAA-LP-1.19.
WTH, 12-15 to-18.
ANSWER 5.18 (1.00) c REFERENCE
, Stocm Tables i
1 1
_ _ _ . _ _ . _ _ _ _ _ _ _ _ _ _ _ _.______.___.m_______.__ _ . _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ _ . _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ _
ok .
3
- 5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 27 gggggggggggggg--------------------------------------
ANSWERS -- ZION 182 -85/09/30-HIGGINS, R.
ANSWER 5.19 (1.50)
- o. 1 (Increase) C1.03 <
- b. 1 E0.53 1 REFERENCE l SHNPP. Technical Specifications 3.1.1.1; RT-LP-3.13, p 7-9.
ZION TS, p 39,65,66.
i l
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f t
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f v
i 5
- 6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 28 ANSWERS -- ZION 182 -85/09/30-HIGGINS, R.
ANSWER 6.01 (1.50)
- 1. OP Delta-T
- 2. :: ^ 7 " Ofd]-
- 3. OT Delta-T E0.5 each]
4 REFERENCE Millstone 3, Vol. 3, Topic 6, Lesson 8, Pages 7-14.
ZION System Descriptions, Chapter 9, pp 22-23 and Functional Dia. 617F767 ANSWER 6.02 (2.00) g3 gh , 9hk> /*h +
- c. Single loop loss of flow when 2/4 pow'er ranges > 6d%. (0.5)
Two loop loss of flow: when 2/4 power ranges > 10% OR 1/2 impulse pressures > 10% [0.5 each] (1.0)
- b. DNB protection.
.1/3 WM921JEm' .
M'"^-4Wh
'=>-
Qf (0.5) 3 REFERENCE ZION System Description Chapter 9, pp 19, 23-24 and Table 9-II-C1 ANSWER 6.03 (3.00)
- o. Maintain. radiation levels below 2.5 MREM /HR at the Spent Fuel .
Pool (SFP) surface, during fuel movement. OR M d h (1.0)
- b. Refueling Water Storage Tank (RWST) or Baron Recycle System or Deminyt li ed Flushin3 Water System or Service Water System.
/M, 4A$DC[hg [0.25 each] (1.0)
- c. Makeup is via the Boric Acid Blender by a temporary line or RWST normal makeup. [0.5 each] (1.0)
REFERENCE
- o. HO-SF-24
- b. HO-SF-25
, c. HO-SF-25
- IION System Descriptions, Chapter 16, p. 2 l
l ~
~
- 6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 29 ANSWERS -- ZION 1&2 -85/09/30-HIGGINS, R.
ANSWER 6.04 '(3.00)
- o. 1. CCW surge tank high level.
- 2. CCW RMS &lsam.
- 3. RCP Thermal Barrier outlet low flow al rm
- 4. RCP Thermal Barrier Return Mi. Y ,.9 Ycr r... 1 Flow
- y. g. r...
_ w,www . h.
v v.S W ...______
-.--. ___ _ _ _ _ _A. . . . . ?__,ga,S
- 2. Check valve isolates on reverse flow.
- 3. ;<elief valve (~2500 psis) protects from overpressure. (1.5)
REFERENCE WB FSARi 9.2.2-11 WB PID; 47W611-70-3 WB Instrument Tabulation, XA-55-27B & XA-55-27B-A.
ZION System Descriptions Chapter 15, pp 8-9, P&ID M-66 and M-67 ANSWER 6.05 (2.50)
- a. - Maintain backpressure on orifices to prevent flashing.
- Maintain RCS pressure when solid. [0.5 each3 (1.0)
- b. SHUT (0.5)
- c. Prevent (resin channeling due to) excess flow through demin resin. (0.5)
- d. HCV-i12 (Charging flow control valve). (0.5)
REFERENCE WBLP; CVCS, pages 11 and 16 ZION System Descriptions Chapter 5, pp 5-6, 39 and Fig. Sa-I-C1
- 6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 30 ANSWERS -- ZION 1&2 -85/09/30-HIGGINS, R.
ANSWER 6.06 (2.00)
- a. 1. Rods drive out-- because of the sudden reactor / turbine mismatch.
- 2. Out--Tavs decreases. (1.0)
- b. 1. Provides 1/2 of the temperature error signial required for the Tavs-Tref sigan1.
- 2. Acts as an anticipatory signal and modifies rod speed accordingly. (1.0)
REFERENCE Connecticut Yankee Plant Information Book (PIB)--Rod Control pp. 13,22 ZION System Descriptions, Chapter 8, pp 1-30 ANSWER 6.07 (3.00)
- a. 1. Increase CO.53 steam flow signal would increase CO.253 causing an immediate SF-FF mismatch [0.253. (1.0)
- 2. The steam senerator. level would level out at a higher than normal level. (0.5)
- b. Total steam flow. (0.5)
- c. 1.
2.
Low u
r +iva =+
steam line pressure (SI) n do TM4 r p r ::; r W. Ah ate 'ates;1ine i;;1_ti;r.). A A 4P Jr
- 3. Low-Low S/G level (Reactor trip and AFW actuation).
- 4. Hi-Hi S/G 1evel (P-14) (turbine trip and feedwater 1 o g i
y yp g. E0.25 each] (1.0)
REFERENCE Plont System Book 3, SNPT-223, Chapter 6, pp 6-7 to 6-21 GLJ 19 ZION System Descriptions, Chapter 21a, pp 30-35' ZION Logic Diagrams, 5653D30, 617F767
- 6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 31 ANSWERS - ZION 1&2 -85/09/30-HIGGINS, R.
ANSWER 6.08 (4.00) 0 1. Low-low level in TWO S/G 2/4 reactor coolant pump bus voltage low SI signal Blackout signal E0.5 each] (2.0)
- 2. Low-low level in S/G9 Blackout signal SI signal E0.5 each3 (1.5)
- b. h S/G sampling valves [ eachJ (0.5)
REFERENCE CPSES System Information Manuali VIII-8.7 and 8.8 ZION System Descriptions, Chapter 12c, pp 1-2 and 19 ANSWER 6.09 (2.00)
- Gland seal condenser bypass valves trip open
- Standby Cond./Cond. Booster Pump starts
- Cond. Booster Pump recire valves trip shut
- H2ater Drain Level Control overrides (to allow full HDTP flow to go to the FWP). [0.5 each3 (2.0)
REFERENCE Zion Sy, stem Descriptions, Chapter 25a, p. 44 ANSWER 6.10 (2.00)
- o. INTERMEDIATE and POWER
- b. SOURCE, INTERMEDIATE and POWER
- c. INTERMEDIATE and POWER
- d. INTERMEDIATE and POWER E0.5 each3 (2.0)
REFERENCE Zion SD, 6a,6beand 6c.
SHNP NIS-LP-1.0, pp 8-19
4 7.- PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 32
~
~~~~RdD56L6556dL 66NTR6L'~~~~~~~~~~~~~~~~~~~~~~~
ANSWERS -- ZION 182 -85/09/30-HIGGINS, R.
ANSWER 7.01 (2.50)
- c. -3 Rem / Quarter is NOT exceeded. [0.53
-Total accumulated dose does not exceed 5(N-18). [0.53
-Accumulated exposure on record (NRC-4). [0.53 (1.5)
- b. -When'the individual entering a resticted area receives or is likely to receive 25% of his quarterly exposure limit.
-When an individual 18 years or younger receives or is likely to receive 5% of the adult quarterly exposure limit.
-Anyone enterin3 a high radiation area. E0.5 each, two required] (1.0)
REFERENCE ZNPT-211, Radiation Protection and Safety, A-13, pp 8,11,12 of 33 BLS 42 ANSWER 7.02 (4.00)
- a. 1. Unexpected rise in S/G level.
- 2. High radiation from S/G blowdown sample.
- 3. High radiation from S/G steamline. [0.5 each3 (1.5)
- b. 1. Secure all feedwater flow to the faulted S/G (F-S/G).
- 2. Verify F-S/G Blowdown valves closed.
- 3. Close steam supply to TDAFW pump (if A or D S/G). [0.5 each3 (1.5)
- c. 1. Close non-ruptured (N/R) S/G MSIV's and bypass valves.
- 2. Use N/R S/G PORV's for steam dumps.
- 3. Terminate steam dump to the condenser. [0.33 each] (1.0)
REFERENCE ZION E0P-10, pp 3-6.
L
- 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 33
~~~~~~~~~~~~~~~~~~~~~~~~
~~~~RhD56LU5fE5L'EUUTR6L ANSWERS -- ZION 1&2 -85/09/30-HIGGINS, R.
ANSWER 7.03 (3.00)
- 6. 1. Fuel building ventilation diverts through the charcoal filters.
- 2. Charcoal booster fans auto start.- (1.0)
- b. 1. All personnel accesses to the affected area are closed.
- 2. All personnel have evacuated the affected area (1.0)
- c. 1. Shield against injestion.
- 2. Air feed respirators.
- 3. Use of a plastic or rubber suit. [0.33 each3 (1.0)
REFERENCE E0P-8 p.4,5 & Rad Con Considerations ANSWER 7.04 (2.00)
- 3. Tc from S/G pressure.
Th from averase Incore T/Cs Core delta T < 60 F S/G pressure following RCS Hot Les temperature.- [0.25 each3 (1.0)
- b. 1) Erratic pressurizer level indication. (0.5)
- 2) Low RCS flow results in significant cooling reduction in the head area. (0.5)
REFERENCE ZION EOP-7, Appendix Av.p. 31 ANSWER 7.05 (3.50)
- a. 0.1, 250
- b. 200
- c. visual, audible
- d. - 0.2, 400 E0.5 each3 (3.5)
REFERENCE ZION GOP-1, precautions, pp 7-9
- 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 34
~~~~~~~~~~~~~~~~~~~~~~~~
~~~~R 65UL5GIEEE E5UTRUL ANSWERS -- ZION 1&2 -85/09/30-HIGGINS, R.
ANSWER 7.06 (2.00)
- a. Minimum S/D margin is not violated.
- b. HI STEAM FLOW.
- c. Prolonged idling may dama3e the turbine due to high moisture content in the steam at low powers.
- d. Auto stop of the pump at " 600 RPM.
[0.5 each3 (2.0)
REFERENCE ZION GDP-2, pp 9, 10, 22, 26 ANSWER 7.07 (3.00)
- o. YES E0.53, power increase to 32% power exceeded the 3%/hr rate on 8/7 [0.753. And on 8/11 the rate to 50% exceeded 3%/hr and the one hour soak at 25% power [0.753. (2.0)
- b. 27.25 /- 0.5 hrs. f 4 N M y# b (1.0)
REFERE CE ZION GOP-3, p. 6 ANSWER 7.08 (2.50)
- b. Transfer Steam dumps to steam pressure mode. (0.5)
REASON' When pumps are secured the dump looses a valid Tavs input from the bypass instrument loop. (0.5)
REFERENCE ZION EDP-0, p. 7 5 Rc Sp < I.200m GF.20m 55 Q % C CW4% Rct%-
- 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 35
~~~~Ed6E6[6556d[~66 TR6[~~~~~~~~~~~~~~~~~~~~~~~~
, ANSWERS -- ZION 182 -85/09/30-HIGGINS, R.
ANSWER 7.09 (2.50)
- o. 1. Check AC amps and/or output voltage on inverter.
- 2. Check
- power supply' lights on the RPS or Safeguards status lights.
- 3. Check any common 4 channel indication. [0.5 each3 (1.5)
- b. 1. Open the inverter feed breaker.
- 2. Close dirty power feed breaker. [0.5 each3 (1.0)
REFERENCE ZION ADP-15 1
i i
4
(
- 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 36 ANSWERS -- ZION 182 -85/09/30-HIGGINS, R.
ANSWER 8.01 (1.50)
- 1. Maintain acceptable power distribution limits.(nuclear peaking factors)
- 2. Maintain adequate SDM.
- 3. Limit _affects of rod ejection accident. [0.5 each3 REFERENCE SHNPP TS, B 3/4 1-3.
ZION TS, p 65.
ANSWER 8.02 (3.00)
- a. Interval requirement not exceeded CO.53. Eight days does not exceed 1.25 times the specified interval [1.03. (1.5)
- b. Interval requirement exceeded [0.53. The last 3 consecutive intervals exceed 3.25 times the specified interval [1.03. (1.5)
REFERENCE SHNPP TS, p. 3/4 0-2, 5-10.
ZION TS, p 27a.
ANSWER 8.03 (2.00)
- 1. The intent of the procedure is not altered E0.53.
- 2. The change is approved by two members of the plant management staff, at least one holds a SRO license C1.03.
- 3. The chan3e is documented, reviewed, and approved within 14 days of implementation by the Station Superintendent CO.53. (2.0)
~ REFERENCE SHNPP TS, p 6-17.
ZION TS, p308.
ANSWER 8.04 (1.00) k REFERENCE SHNPP TS p 6-16.
ZION TS, p320.
- 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 37 CNSWERS -- ZION 112 -85/09/30-HIGGINS, R.
ANSWER 8.05 (1.00) b REFERENCE SHNPP, TS 3/4 2.1
' ZION TS, p 46a-47.
4 ANSWER 8.06 (1.00) c REFERENCE.
SHNPP, TS, pp. 3/4 1-1 and B 3/4 1-1.
ZION TS, pp. 39-42 and 64,65.
ANSWER 8.07 (3.00)
- o. Shift Engineer E0.53 Shift Foreman E0.53 (1.0)
- b. 1. Service building machine shop area. (0.5)
- 2. -Severe weather
-Radiological hazard
-Security threat
-Similiar condition that would adversly affect personnel in the Station Director's opinion. [3 required, 0.5 each] (1.5)
REFERENCE SHNPP PEP 101 p 4-6; 103 p 61 2.3-2.5 p 1.
ZION EPIP 110-1, p 28 360-1, p 2.
4 ONSWER 8.08 (1.00) c REFERENCE ZION ZAP-0-1, p 2,3.
l k
g- -
- 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 38 ANSWERS -- ZION 112 -85/09/30-HIGGINS, R.
ANSWER 8.09 (3.00)
- o. Shift Engineer b.' Shift Foreman
- c. Shift Foreman
- d. Shift Engineer
- 9. Shift Foreman
- f. Shift Engineer [0.5 each3 (3.0)
REFERENCE ZION ZAP 1-151-1, p 4-6.
ANSWER 8.10 (1.50)
Provents a release of activity in event of a SGTR (saturation pressure loco than atmospheric steam relief valve setpoint).
REFERENCE ZION TS, p 125.
ANSWER 8.11 (2.00)
- 1. Controls *R' keys (issued thru his office)
- 2. Maintain logbook / clipboard for each 'R' key issued (and non issued keys)
- 3. Accounts for each 'R' key at the end of shift.
- 4. Forward filled out los sheets to the office supervisor.
Q g Q [Two required, 1.0 each] (2.0)
REFERENCE ZION ZAP 5-51-15, p 3.
ANSWER 8.12 (2.40)
- 2. Only ONE charging pump operable.
- 3. No SI pumps.
- 4. No accumulators operable.
- 5. The first RCP not started with associsted S/G temp >50-F above RCS temp. [Four required, 0.6 each3 (2.4)
y 1
- 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 39 ANSWERS -- ZION 182 -85/09/30-HIGGINS, R.
REFERENCE ZION TS, p 82,83.
ANSWER 8.13 (2.60)
- 1. 1. spa total leakage for all S/G's.
500'spd per S/G. [0.5 each3 (1.0)
- 2. 1'spm--ensures the dosage contribution from the tube leakage will be limited to a small fraction of the Part 100 limits in event of a SGTR or SLB.- (0.8) 500 spd--ensures that S/G tube integrity is maintained in the event of a steam line rupture as under LOCA conditions. (0.8)
REFERENCE ZION TS, p 98a.
.