IR 05000029/1988018
| ML20206G941 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 11/07/1988 |
| From: | Bissett P, Eselgroth P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20206G932 | List: |
| References | |
| 50-029-88-18OL, 50-29-88-18OL, NUDOCS 8811230040 | |
| Download: ML20206G941 (117) | |
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0.S. NUCl. EAR REGULATORY COMMISSION REGION I OPERATOR LICENSING EXAMINATION REPORT
EXAMINATION REPORT NO. 50-029/88-18 (OL) FACILITY 00CKET NO. 50-029 FACILITY LICENSE NO. DPR-3 LICENSEE: Yankee Atomic Electric Company 1671 Worcester Road Framingham, Massachusetts 01701 FACILITY: Yankee Nuclear Power Station EXAMINATION DATES: September 12-15, 1988 d ~ ['/
-3 CHIEF EXAMINER: . Paul H.<Bissett,' Senior Operations Engineer ///*[#f_
Dite' APPROVED BY: / / Peterlselg th, Chief, PWR Sectica
////86 Date
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Operatio / ranch, Division of Reactor Safety SUMMARY: Written examinations and operating tests were administered to one (1) instant senior reactor operator (SRO) and four (4) reactor operator (RO) candidates. The SR0 and all four RO's passed their written and ope ating
- examinations.
8811230040 081114 PDR ADOCK 05000029 V PNU k
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. OETAILS TYPE OF EXAMINATIONS: Replacement EXAMINATION RESULTS: E R0 E $RO E E Pass / Fall E Pass / Fail B E E I E E I E E Written 5 4/0 5 I/0 E E E E __ E I E E I I Operating I 4/0 5 1/0 I E E E E E E E E E Overall I 4/0 E 1/0 E I E I E 1. CHIEF EXAMINER AT SITE: P.H.Bissett, Senior Operations Engineer 2. OTHER 2XAMINERS: F.S. Jagger, EG&G N.C. Jensen, EG&G 3. PERSONNEL PRESENT AT THE EXIT INTE2 VIEW Facilit, Personnel: C.R. Clark, Training Manager T.K. Henderson, Assistant Plant Manager K.E. Jucentkuff, Plant Operations Manager L.J. Laf fond, Senior Instructor D.H. White, Operations Training Supervisor 4. SUMMARY OF NRC AND LICENSEE COMMENTS MADE AT THE EXIT INTERVIEW a. The NRC expressed appreciation to the Training, Operations and Security departments for providing assistance in expediting the examination process.
b. NRC Open Item S0-029/86-03-02 was reviewed and subsequently closed (refer to paragraph 6 for details).
c. The NRC reviewed the number and type of examinations conducted during the week. Also reviewed were associated generic deficiencies observed during the conduct of the operating examinations (refer to paragraph 5 for details).
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5. NRC CONCERNS /0BSERVATIONS a. The following is a summary of generic deficiencies noted on operating tests. This information is being provided to aid the licensee in upgrading license and requalification training programs. No licensee response is required.
1. Two RO candidates did not understand how to meet shutdown margin requirements per OP 4708, in the case of one unremovable control rod.
2. Candidates generally seemed unfamiliar with security access requirements, i.e., which doors are alarmed and when, especially with respect to after-normal working hours.
3. Different answers were received from all five candidates when asked about local administrative radi. tion limits, b. The following is a generic deficiency noted from the grading of written examinations. This information is being provided to aid the licensee in upgrading license and requalification training programs. No licensee response is required.
1. All four R0 candidates demonstrated a weakness in their knowledge of normal, abnormal, emergency and radiological , control ,,rocedures.
6. Licensee Action in Response to Examination Repo t No. 50-029/86-03 (OL)
(Closed) Open Item (86-03-02): Licanse.e nas not developed or provided integrated systems training.
Following a review of several selected lesson plans and discussions with training department personnel, it was determined that the licensee has adequately resolved this concern. As detailed in ; each respective lesson plan, it was noted that each plant system now l includes a discussion of system interrelationship with other associated systems. Also, the licensee informed the examinei of the development of a system performance analysis program. Through the use of a computer, a student would be able to observe the plant response as a result of , various system malfunctions, as inputted by the student. The licensee is ! in the process of updating and verifying various system responses and associated parameters before formalizing and incorporating into their training program. Based upon this review, this item is closed.
Attachments: 1. Written Examination and Answer Key (RO) > 2. Written Examination and Answer Key (SRO) ' 3. Facility Comments on Written Examinations after Facility Review 4. NRC Response to Facility Comments
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U. S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION FACILITY: YANKEE-ROWE _ REACTOR TYPE: PWR-WEC4 * DATE ADMINSTERED: 88/09/13 EXAMINER: dAQQAR. F.
CANDIDATE b m rw i,lT- _f ( _ F 'AQ INSTRUCTIONS TO CARDIDATE: Use separate paper for the answers. Write answers on one side only.
Staple question sheet on top of the answer sheets. Points for each question are indicated in parentheses t.fter the question. The passing grade requires at least 704 in each category and a final grado of at least 80%. Examination papers will be picked up six (6) hours after the examination starts.
% OF CATEGORY % OF CANDIDATE'S CATEGORY VALUE__ TOTAL SCO.BE__._ VALUE CATEGORY 25.00 24.
25.m0 f.T 1. PRINCIPLES OF NUCLEAR POWER
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26.vC PLANT OPERATION, THERMODYNAMICS, zg 2.o HEAT TRANSFER AND FLUID FLOW 22.40 2%29 _25.^0 =25.99 2. PLANT DESIGN INCLUDING SAFETY 27. Go AND EMERGFNCY SYSTEMS 22.oo -23.-72 _25,^^ _ 25,^? 3. INSTRUMENTS AND CONTROLS 23.75* -34.-% _t+-44 _E6.r4G 4. PROCEDURES - NORMAL, ABNORMAL, a5. 40 EMERGENCY AND RADIOLOGICAL 73.3 5 CONTROL 42.4Y
- i ^ ^ ^- % Totals Final Grade ;
All work done on this examination is my own. I have neither given nor received aid.
' Candidate's Signature i i I A, . - - - -_.,-.-n . - - _ _ - - . - - _ - - - - - - . - , _ . - _ _ - - - . , _ . . , U
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. . , NRC RULES AN. GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules apply:
1. Cheating on the examination means an automatic denial of your application and could result in more severe penalties.
2. Restroom trips are to be limited and only one candidate at a time may leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.
3. Use black ink or dark pencil only to facilitate legible reproductions.
4. Print your name in the blank provided on the cover sheet of the examination.
< . 5. Fill in the date on the cover sheet of the examination (if necessary).
6. Use only the paper provided for answers.
7. Print your name in the upper right-hand corner of the first page of each section of the answer sheet.
8. Consecutively number each answer sheet, write "End of Category __" as appropriate, start each category on a new page, write only on one side of the paper, and write "Last Page" on the last answer sheet.
9. Number each answer as to category and number, for example, 1.4, 6.3.
10. Skip at least three lines between each answer.
11. Separate answer sheets from pad and place finished answer sheets face down on your desh or table.
12. Use abbreviations only if they are commonly used in facility literature.
13. The point value for each question is indicated in parentheses after tho question and can be used as a guide for the depth of answer required.
14. Show all calculations, methods, or assumptions useo to obtain an answer to mathematical problems whether indicated in the question or not.
15. Partial credit may ba given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLANK.
16. If parts of the examination are not clear as to intent, ask questions of the examiner only.
17. You must sign the statement on the cover sheet that indicates that the work is your own and you have not received or been given assistance in completing the examination. This must be done after the examination has been completed. - i
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o 18. When you complete your examination, you shall: a. Assemble your examination as follows:
(1) Exam questions on top.
(2) Exam aids - figures, tables, etc.
(3) Answer pages including figures which are part of the answer.
b. Turn in your copy of the examination and all pages used to answer the examination questions, c. Turn in all scrap paper and the balance of the paper that you did not use for ancwering the questions, d. Leave the examination area, as defined by the examiner. If after leaving, you are found in this area while the examination is still in progress, your license may be denied or revoked.
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1. PRIHg.lELEE_QF NUCLEAR POWEB_ PLANT OEEBA11QHz Pcgo 2
. IHERMODYN&MICS. HEAT TRAESFER AND FLUID FIQW 4 QUESTION 1.01 (1.00)
Increasing the boron concentration at a low temperature has little effect on the Moderator Temperature Coefficient as compared to higher operating temperatures because: (choose the one answer, from below, that correctly completes the sentence) a. Water density does not change as much at low temperature.
i b. water density is greater at lower temperatures so neutron leakage is less.
c, water density is greater at lower temperatures so parasitic neutron absorption is greater.
d. boric acid is less soluble at lower temperatures.
QUESTION 1.02 tl.00) Which one of the following statements concerning Xenon-135 production and removal is correct? a. At full power, equilibrium conditinns, about half of the Xenon is produced by Iodine decay and the other half is produced as a direct fission product, b. Following a reactor trip from equilibrium conditions, Xenon peaks because delayed neutron precursors continue to decay to Xenon while neutron absorption (burnout) has ceased.
c. Xenon production and removal increases linearly as power level increases; i.e., the value of 100% equilibrium Xenon is twice that of 50% equilibrium Xenon, d. At low power levels, Xenon decay is the major removal methoc At high power levels, burnout is the major removal method.
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1. PRINCIPLES OF NUCLEAR POWER PLANT __OPEBATIONi_ Pcgs 3
. IHEBMODYNAMLGEuBEAT TRAt!EEEB_ AND FLUID FLOW QUESTION 1.03 (1.00)
At the core ages, the ratio of PU239 atoms to U235 atoms increases.
This changing ratio causes the: (Choose the one answer, from , below.that correctly comp,\etes the sentence) a. reactor startup rate ( L'UR ) to increase, for the same reactivity additi.on, b. Void Coefficient to becoae less negative.
c. Moderator Temperature Coefficient to become less negative.
d. delayed neutron fraction to increase.
QUESTION 1.04 (1.00) Which one of the following statements concerning Shutdown hargin (SDM) is correct? a. The maximum SDM requirement occurs at EOL and is based on a rod ejection accident, b. The maximum SDM requirement occurs at EOL and is based on a steam line break accident. ; c. The maximum SDM requirement occurs at BOL c-d 4.s based on having a positive moderator temperature coefficient.
d. The maximum SDN requirement occurs at BOL and is based on a rod withdrawal accident while in the source range.
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1. PBINCIPLES OF_NUCLEAB_ POWER PLANT OEEBA11QHz Pego 4 :
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~ QUEuTION 1.05 (1.50) I ' The reactor is taken critical with Xenon concentration at zero.
is raised to 50% at 5%/hr.
Power . Using one of the fo21owing choices: Incroasing Decreasing At equilibrium, describe how Xenon concentration will be trending for each of the
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following situations (a,b, and c).
a. One hour after a trip occurs as power reaches 50%. ' i b. Four hours after the trip occurs the reactor is taken critical and i power raised back to 50%. t c. If reactor operation continues and power level is maintained at 50% ' for one hour.
, QUESTION 1.06 (2.00)
a. How is Shutdown Margin (SDM) affected (Increase, screase, or No , change) by a 50 ppm boron addition while operating at 50% power?
(0,5)
{ b. List FIVE factors, other than RCS boron concentration and rod
- position, which will affect SDM and are used in the SDM 1 calculation. (1.5)
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1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION. Pego 5
. IHEBMODYN6dICS. HEAT TRANEEER AND FLUID FLOW QUESTION 1.07 (1.00) -
' Which'one of the following conditions would cau.:e a 1/M plot to be NON-conservative during fuel loading? a. Fuel being loaded closer to the neutron source than to the source range detector.- b. Loading fuel in the order of high reactivity worth to low reactivity worth.
c. Loading poison rods between the source range detectors and spaces to , be filled by fuel assemblies.
- d. Increasing the boron concentration in the Loderator.
i i QUESTION 1.08 (1.50) ! Match the parameter change in Column A to the direction it will change the Moderator Temperature Coefficient (MTC) in Column B. Consider each case separately.
! COLUMN A COLUMN B j 1. Moderator temperature increases a. More Negative j 2. Boron concentration increases b. Less Negative ! 3. All rods in vs. all rods out c. No Effect I
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' QUESTION 1.09 (2.00) If the Sourco Range (SR) instruments indicate 50 cps with Keff equal to 0.9, what would the SR instrument indicate if rods were withdrawn to bring Keff equal to 0.957 Assume BOL conditions,
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, a. 1. 50 cps 2. 75 cps 3. 100 cps ' J 4. 200 cps (1.0) i b. How much reactivity was added? 1. 0.0347 2. 0.0500 3. 0.0526 4. 0.0585 (1,0) i
) QUESTION 1.10 (1.00) ) Which one of the following correctly describes the observed reactor response for the same small addition of reactivity, one positive and , one negative? , a. The response will be faster for the negative addition at all ) times in core life.
j b. The response will be faster for the negative addition at BOL
- but faster for the positive addition at EOL,
' , c. The response will be faster for the positive addition at all q times in core life.
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d. The response will be faster for the positive addition at BOL , but faster for the negative addition at EOL.
e. The response will be the same for both the positive and negative addition.
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4* L EBlHQIELES OF NUCLEAR POWER PLANT OEEBATION, Pcgo 7
- IEEBtiQRYEAMICL__ BEAT TRAtMEEB_6ER_ELVID_.ELQE QUESTION 1.11 (1.00)
Which one of the following statements concerning power defect is correct? a. The power defect is the difference between the measured power coefficient and the predicted power coefficient.
b. The power defect increases the rod worth requirements necessary , to maintain the desired shutdown margi'n following a reactor trip.
c. Because of the higher boron concentraticn, the power defect is more negative at boginning of core life, d. The power defect necessitates the use of a cont. tant Tava program ! to maintain an adequate Reactor Coolant System subcooling margin.
QUESTION 1.12 (1.00) State TWO reasons for establishing Power Dependent Insertion limits.
QUESTION 1.13 (1.00) A centrifugal pump is operating at rated flow when the discharge , valve is throttled in the shut direction. For each of the t following indicate whether the parameter will increase, decrease I or remain the same, after the valve is throttled in the shut direction. f l
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a. NPSH
- b. motor amperage I
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L,,._EE.lE91ELES OF NUCLEAR-_ POWER PLANT OEEBATION . Pcgo 8
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IBEBMQDlHAtilGL._HEALIB6HEEER AND FLQ1D FLOW QUESTION 1.14 (1.00) ' TRUE or FALSE a. During a RCS heatup, as temperature gets higher, it will take a smaller letdown flow rate to maintain a constant pressurizer level, b. Increasing condensate depression (subcooling) will cause BOTH a decrease in plant efficiency AND an increase in condensate (hotwell) pump available NPSH.
QUESTION 1.15 (2.50) - a. What is the subcooling margin (SCH) of the RCS if the following conditions exist? Th =580 F Pressuriser pressure =2185 psig Tc =520 F Steam Generator Pressure =850 psig (1.0) b. If power is raised from 50 to 100%, HOW and WHY will SCH change ,
(increase, decrease, stay the same)? (0.75)
c. Which one of the following would result in the smallest SCH7 Briefly explain your choice. Assume identical RCS pressures. (0.75) 1. SCH during a controlled natural circulation cooldown fo)2owing a reactor trip from loss of flow.
2. SCH during continued operation at 5% power.
' 3. SCM produced when all RCP's are operated at normal no-load temperature after extended shutdown.
, QUESTION 1.16 (1.00) At each of the following leak locations, indicate the state of the exiting fluid (subcooled, saturated, or superhuated). Assume normal 100% power initial operating plant conditions, i a. PZR steam space to CTHT atmosphere.
b. Main steam header to turbine building atmosphere.
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1. PRINCIELES OF NUGLEAR POWEB_ELANT OPEBATION. Pcgo 9
. IBEBMODYNAMICS. HEAT TEAMfjB_A@ FLUID FLOW QUESTION 1.17 (1.00)
Primary system flow rate is many times - teater than secondary system flow rate while the heat transferred by the two systems is essentially the same. Explain how this is possi' ole.
QUESTION 1.18 (1.50) List all of the conditions / requirements that must be present in order for natural circulation to exist.
I QUESTION 1.19 (2.00) The plant is operating at 33% power when #1 Non-Return valve fails shut, t Using the giv:nn initial conditions, determine the new steady state i values / conditions for the below parameters. Assume no operator action, ! no reactor scram, and that all control systems are in automatic with the exception of rod control. Justify your answers with calculations and/or r discussion, j Initial Conditions: Tavg = 515 F Patm = 645 psig Core Delta T = 18 F a. Turbine power b. Tavg - Loop 1 ! c. Tava - Loop 4 l
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e. Patm - Loop 4 l
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2 PL&HI_QE110_N_lEQLUDING SAFETY AND EMEEG_EEQ1 Pcgo 10 . EYEIEde ( 2.10) QUESTION 2.01 (2.007 Draw / explain the electrical distribution for supply tc the No. y 2 YO# Vital Bus. Include normal and alternate sources from the +te+ VAC source. Label all major components (breaker numbers not required).
GUESTION 2.02 (1.50)
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What AUTO actions occur as a result of the #1 480V Emergency Bus Protection syetem response to a complete loss of power.
QUESTION 2.03 (1.50)
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Assume that an actuation signal is present for the VCIAS and that the Train A & B TEST / NORMAL /PYPASS switches for valve SW-TV-412 (VC Cooling Water Supply) are positioned as indicated below. State the position of SW-TV-412 prior to receipt of the VCIAS signal and HOW it will respond to the signal. Consider each case separately.
1. Train A in TEST. Train B in BYPASS 2. Both Train A & B in BYPASS QUESTION 2,04 (1.00) Briefly describe the operation of the gravity operated dampers which are located just 4.ownstream of each Vapor Container Heating and Cooling Fan f i Vapor Container Atmosphore Control System. Include i
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normal alignme.it AND operation following a loss of coolant accident into the Vapor Container.
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2. PLANT DESIGN INCLUDING SAFETY _6HD EMERGENQX Pcgo 11 - EXEIEME Delebd r f I QUESTION 2.05 (2.00) desifn State the rated capacity at ehute44 head of the following pumps used to inject water into the MCS during accident conditions. Include the shutoff head pressure below which the pumps will begin to inject water to the MCS.
a. High Pressure Safety In.iection Pump.
J b. Low Pressure Safety Injection Pump.
< QUESTION 2,06 (2.00) a. All three charging pumps auto-started on low level in the pressurizer in response to a small MCS leak (3 spm). If bleed flow is 20 rpm, how will the charging system continue to respond if no operator action is taken? b. State the flow path for supplying STRONG boric acid to the auction of si and #2 charging pumps. Assume the suction header division valve (CH-V-619 is shut).
QUESTION 2.07 (2.00) Match the Main Coolant System penetration in Column A to the correct location in Column B.
COLUMN A COLUMN B
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a. Pzr Spra/ 1. Loop 1 Cold Leg 2. Loop i Hot Les b. Normal Charging 3. Loop 2 Cold Leg 4. Loop 2 Hot Les c. Shut, town Cooling Suction 5. Loop 3 Cold Les 6. Loop 3 Hot Leg d. Par Surge Line 7. Loop 4 Cold Leg 8. Loop 4 Hot Les
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2 PLANT DESIGN INCLUDIUQ_SAEETY AND EMEBQEHgy Pego 12
. SXSTEMS
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QUESTION 2.08 (2.50) a. State the ACTUAL capacity and the Technical Specification HINIMUM capacity of the following tanks associated with the EDG.
1. Fuel Oil Storage Tank.
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; 2. Diesel Generator Day Tank. (0.6)
b. Describe the operation of the system that shuts off fuel from the Diesel Generator Day Tank in case of fire. (1.6) c. In addition to the Diesel Generators, what other system (s) is/are supplied fuel oil from the Fuel Oil Storage Tank? (0.3)
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QUESTION 2.c9 (2.00) ! a. State the NORMAL and ALTERNATE sources of suction for the Electric and Steam Driven Emergoney Boiler Feed Pumps (EBFP). (1.0) b. TRUE or FALSE l I The Electric Driven AND the Steam Driven EBFP's can be used to
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supply water to the steam generators via either Norma). or ! , Alternate Emergency Feed Water flow paths, (0,5) ! c. How is the steam Driven EBFP discharge pressure maintained when the
pump is running? (0.5) ; i l QUESTION 2.10 (2.00) h i A loss of Control Air has occurred due to a large rupture. [ t a. At what pressure (s) will the backup Control Air compressor (s) l start? (0,5) , l
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b. Describe the sequence of events that will lead to a reactor trip.
(1.0) ,
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c. How will the MCS temperature be controlled following the reactor i trip? (0,5) j
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* 2. Pego 13 PLANT DESIGN INCLQDIN9_ SAFETY AND EMEB9089Y
. SYSIEDS
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QUESTION 2,11 (2,00) a. State the power supply for the Shutdown Cooling (SDC) Pump. (0,5) ' b. How does the location of the SDC pump ensure a positive suction ' head during all modes of SDC pump operation. (0,5) c. State the normal and alternate locations where the SDC relief valves may discharge to. (1,0) > QUESTION 2.12 (2.00) ,
a. How does the flow path of SI water into the MCS change when beginning Safety Injection Recirculations. (1,0) b. Why are all but one High Pressure Safety Injection Pump and one Low Pressure Safety Injection Pump stopped during the performance of Safety Injection Recirculation? (0.5) ,
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c. TRUE or FALSE ' L Hot Leg Injection is normally used only during the recirculation phase of a loss-of-coolant accident. (0.5)
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QUESTION 2.13 (2.00) a. How does the design of the Fire Water System 1.rovide for an adequate / redundant supply of water? b. MULTIPLE CHOICE , Which one of the following will cause the Diesel-Driven Fire Water Pump to trip AUTOMATICALLY? i t
(1.) Overspeed !
(2.) Low 011 Pressure (3.) Low fuel Tank level
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(4.) High Cooling Water temperature ,
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3. LESIggggNTS_AND_GQBIBQLa Pcgo 14
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QUESTION 3.01 (1.50) a. During a reactor shutdown, at what approximate Intermediate Range indication will the effects of over or undercompensation of the Intermediate Range channels be noticable? (0.5) b. Which condition (overcompensation and undercompensation) would provide a MORE conservative indication of power during a reactor startup? Explain your ansver. (1.0) QUESTION 3.02 -
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Ia. State whether or not the High Power Scram Bistable must be reset MANUALLY. AUTOMATICALLY or BOTH for the following excore instrunent channels.
1.) Intermediate Range Power Range, t
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t 2.) Power Range. (1.0) j b. Which of the excore nuclear instrument channels are used to provide a high startup rate reacto." scram? (0.5) . QUESTION 3.03 (1.00) a. What is the function of the Pressurizer Wide Range Pressure input ! to the Pressuricer Narrow Range Level clannel? b. With the reactor at 100% powar and all systems in a normal conf i guration , how will a failure of the power supply to PR-P-700, Pressurizer Wide Range Pressure, effect the speed of the operating charging pumps? , QUESTION 3.04 (2.50) a. State the parameters and their setpoints that will initiate a Safety Injection signal. (1.5) b. List the Vapor Container Isolation System trip valves that are NOT closed by the Diverse Parameter Vapor Container Isolation Actuation System. (1,0)
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QUESTION 3.05 (1.50) ;
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State whether the following SIAS lockout relays can be reset MANUALLY i or ELECTRICALLY. j I WL-1 SIAS-A 4 SIAS A-1 l
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3.06 ' QUESTION (2.00)
a. List the THREE parameters that are inputs to the THRIE-element ; control system used to control fett flow to the Steam Generators. ; g (1.5) j
! b. What parameter is used for density compensation in the feedwater l
control systen.? (0.5) 5 ! v j QUESTION 3.07 (2.50) ; The following concern the Rod Control System.
i l a. hhat will cause an outward rod stcp? Include applicable } l
! setpoints (if any). (0.5) t l I j b. What action is required to allow outward rod motion subsequent to l
the rod stop mentioned in a., above? (0,5) l c. What are THREE ways to produce inward 'od motion? (1.5) l i !
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l , QUESTION 3.08 (2.00) { a. Which reactor trips have permissive circuits associated with them?
(1.6) l l l i b. What plant condition (s) will activate / deactivate the termissive !
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3,..__ INSTRUMERIS_AHQ_CQEIBQLS Pcgo 16
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QUESTION 3.09 (1.50) State the automatic act.on, if any, associated with a HIGH alarm on atch of the process radiation monitor channels listed below, a. Radioactive test tank affluent (liquid radioactive effluent line) ! monitor.
> b. Steam Generator blowdown tank effluent monitor, c. Component Cooling monitor.
/ Delede/ QUESTION 3.10 (2.00) a. State the purpose of the Non-Return Valve (NRV) Scram.
i b. How is the NRV trip reset if Main Coolant pressure in less ths.n 1800 psig with low steam generator pressure?
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__ QUESTION 3.11 (1.50) i a. In addition to preventing water relief through the safety valves, what Main Coolaat System condition does the High Pressuriser Water Level scram provide protection against? (0.5) b. State TWO events for which the High Pressurieer Water Level provides protection for the Reactor Core. (1.0) QUESTION 3.12 (1,50) Assume an SIAS signal is present.
State how t the following components will respond to a loss of normal ) .pply and subsequent re-energitation via the Emergency I 'enerator.
, (Limit your answer to START IMMEDIATELY, START WITH DELAY. or WILL NOT START AS A RESULT OF THIS CONDITION.)
a. High Prosauro Safety Injection pump, b Low Pressure Safety Injection pump.
c. Charging pumps.
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lu__lRE18EMEBIS_AND CONTROLQ
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QUESTION 3.13 (2.00) - a. List the FOUR preameters that are used as inputs to the Main Coolant Saturat,on Monitor. (1.6) b. What is moant by a red dot when ooserved on the digital read-out for the Saturation Monitor. (0.4) QUESTION 3.14 (2.00) The following concern the Shutdown Cooling System.
a. How is primary cooldown rate and/or primary temperature maintained during Shutdown Cooling System operation with Main Coolant temperature: 1. above 140 F7 2. below 14D F? (1.5) ' b. Describe the permissive, with applicabis setpoints, associated rith SD-MOV-553 and -554 (isolation valves to the MCS Hot and Cold legs). (0.5)
l (***** END OF CATEGORY 3 *****)
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4. PROGRURES - NQBtMLdRHQBtML. EMUGENCY Pcgo 18 , AND RADIOLQQLCAL..COEIRQL i
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QUESTION A.01 (2.50) The following concern OP-3107, "Steam Generator Tube Rupture" procedure. f
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a. State THREE methods used t'o identify the faulted Steam Generator (S/G). (0.75) ; i b. What is the criteria for scramming the plant? (0,5)
[ .
c. What is the reason / bases for tripping the RCP associated with ! the faulted S/G7 (0,5)
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t d. After SI has been terminated, what is the SI re-initiation t criteria? THREE criteria required. (0.75) i
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i l QUESTION 4.02 (3.00) l l The following concern OP-3105, "Emergency Boration Is.jection" procedure. > r a. 5 : ate the THREE conditions which may require immediate boric acid I injection. I t b. List FIVE of the seven required immediate operator actions, i
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QUESTION 4.03 (2.25) ' The following concern OP-2100 "Plant Startop from Cold Shutdown or Refueling" procedure, i n. A dedicated operator at the Main Control Board is responsible to monitor the status of what THREE separate indications / systems? i (1.5) { i b. What is the limit on MCS pressure when LTOP is in service, and MCS i temperature is less than or equal to 380 degrees-T? (0.25) i t c. Why must MCS pressure be greater than or equal to 200 pais before operating the control rod drives? (0.5) : I t
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L PRQSEDUBES - HQBMALufRHQBBAL, EMEBQEHQJ Pego 19 !
. ABD_B60IOL9919AL CONIE9L
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QUESTION 4.04 (l. 5'CQ 11.'5,
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The following concern OP-3535 "High T-Aversge" alarm procedure.
a. List FOUR separate possible causes for the alarm. (1.0) i b. What are the TWO immediate operator actions associated with this alarm? (0,5)
c. What additional operator action is required if the "Rod Operations Selector Switch" is selected to the manual position? (0.25)
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, - 1 QUESTION 4.05 (2.00) l I The following concern OP-3054, "Natural Circulation" procedure, i u I ' a. What FOUR parameters are monitored, for verification that Natural
. Circulation is proceeding normally? r
b. What is the basis for the following requirements / limits?
"If it is desired to perform a cooldown on NC, limit the cooldown rate j to 20 F/Hr and ensure that a autJooling margin of at least 40 F is maintained."
! QUESTION 4.06 (2.50) [ The following pertain to OP-3053 Inadequate Core Cooling.
j , l ' a. Under what two conditions is this procedure to be entered? (0,5)
!
b. Under what conditions may PR-SOV-90 be used to depressurize the MCS? TWO of THREE conditions required. (1,0) - c. Under what conditions should MCS depressurization viA the ; steam generators NOT be attempted? TWO of THREE conditions L required. (1,0) l
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3 EBQCEDUBE E EQEMALuAEHQBBALuEMEEGEHgY Pego 20
. AUD_ BAD 10LQQ1 CAL _C9BIEQL QUESTION 4.07 (1.75)
The following pertain to information found in OP-3117. Refue' ting Accidents, n. Communications are temporarily lost between the refueling crew and the control room when improper fuel loading causes an inadvertent ' criti:ality.
List the first two audible indications that would be received in the VC and state why these indicat'ons would be the first ones received. (0.75) b. What immediate operator action is taken to establish reactivity l control during a Criticality Accident in the VC7 (0.5) ; c. Which one of the below symptoms would NOT be expected if a HEW i fuel assembly was dropped while moving it? Assume it was above the water when it fell. , 1. Visible damage te the assembly.
2. Gas bubble emise. ion from the assembly.
3. Plant accident araa radiation monitor high alarm. (0.5) G,Ms) QUESTION 4.08 '2,75)
(2.15) l The following pertain to information found ir. OD-3000. Energency l Shutdown From Power. I a. List tha steps of OP-3000 that are specifically written to I
shutdown the reactor in the event of an ATWS. Assume a Manual
scram and turbine throttle trip wer unsuccessful in causing the ; rods to move in. (1.05) l l
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b. List the actions that occur or are required at 1650 psig and t 1200 psig. Indicate whether they are manual or automatic. (1.2) c. TRUE or FALSE i After a reactor scram all reactor coolant pumps should be ' restarted as soon as possible and left running unless a bona fide , loss of coolant pressure caused automatic initiation of SI. (0.5)
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3, PROCEDUBES - NORMAL,_ ABNORMAL. EMEBGENCY Pego 21
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AUD_BADIDLQ919AL_GQUIBQL QUESTION 4.09 (2.00) a. State the definition of a HIGH RADIATION AREA as found in 10CFR20, b. State THREE of the four conditior s that require a person in the RCA to exit and report to Radiation Protection after checking his/her docimeter.
QUESTION 4.10 (1.00) Describe how the Shutdown Cooling System loop isolation valves (SC-HOV-551. -552 -553, -554) are prevented from opening during normal MCS operation. Do not include interlocks.
( l. 00) QUESTION 4.11 -(2.0^) a. When the ECCS is in the MANUAL operational mode, what specific operator actions are required to initiate the ECCS? p,_ {),p fe,[ b. In what operational modes must the entire ECCS system be in the manual mode of operation? _
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QUESTION 4.12 (1.50) The following pertain to information found in CP-3'06. Loss of Hain Coolant.
a. What ,9CS conditions require a trip of all Main Coolant Pumps?
(0,5)
b. What is the maximum amount of time allotted for placing the VC Hydrogen monitor in service following the initiation of the GIAS?
(0.25)
c. State the THR.TE conditions that would require SI REINITIATION following termination of Safety Injection. (0.75)
. (***** END OF CATEGORY 4 ***=*) (6********* END OF EXAMINATION **********)
* . .. ***
EQUATION SHEET
,.
._
f = as y = s/t
'
v . og ,.yg+ g,g 2 Cycle efficiency = "* * g a = (vI - y* )/t
*
E = aC 2 A = AN-At EE = uv v g = v, + at A = A,e PE = msh w - e/t A = in 2/tq = 0.693/cg , W = vaP- . . . AE = 9314a t h(eff) = (e,;)(q) '
(C,g+t)
.
b 6 = M PAT , I . g -EA
,
o
, , = UAAT g . g -VI , , ,
to -X M
~
Pwr = W' g a" I.g
,
g
-
y=y to M (t). T7L = 1.3/u t UVL a 0.693/v
-
y = y* a /T
-
' SUR = 26.06/T ,
-
T = 1.e.4 DT sCx a s/(1 - x,gg) . e ' sen = 26 f 1[f , CR, = S/(1 - E,ggg) T = '(**/o ) + [(f 'o)/;.,gg ] o
-
-
efdl * eff 2
'
,
-
T = t*/ (, _ p M = 1/(1 - K,gg) = CR /CR0 g l T*I ~ 8)! Asif' H = (1 x,gg)0/II ~ Eeff)1 o = (K,gg-1)/K,gg = AK,gg/K,f, 3D3 , (l , K,gg)jK gg
~
l p= '[1*/TKygg .] + (I/(1 + A,ggt )] 1* = 1 x 10 seconds
,
'
~I F = I(V/(3 x 10 0) A,ggA= 0.1 seconde
- t=W -
t
.
Idgg=Id22 WAT1'R PARAMfTERS Idg =Id2 i
1 gal. = 8.345 lba R/hr = (0.5 CE)/d g,,,,,,) ( 1 sal. = 3.78 liters R/hr = 6 CE/d (feec) -
.
1 ft = 7.48 41. HTSCELLANEOUS CONVERSIONS , 3 10 , Density = 62.4 lba/ft 1 Curie = 3.7 x 10 dps ,
bensity = 1 gn/ca 1 kg = 2.21 1ha Heat of va;orization = 970 ftu/lba 1 hp = 2.54 4 103 BW/hr I 0 Heat of fusien = 144 Stu/lbre 1 Hw = 3.41 x 10 8tu/hr 1 Ata = 14.7 psi = 29.9 in. I's. 1 Stu = 778 ft-lbf
l 1 ft. H 2O = 0.4333 lbf/in g inch = 2.54 cm I *F = 9/$'C + 32
'C 3/9 ('y . 3a) !
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iJ 1. PRINCIP1ES OF NUCLEAR POWER PLANT OEEBA.TlQHz Pega 22
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IHEBtiODYNAMICS. HEAT '"RANSSB_AND FL.UID ' FLOW .
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jk(7 ' _ g v (HJ i 65 L W d L
' ANSWER 1.01 (1.00)
a.
' REFERENCE YAEC 200911 EO 911.2 KAI 3.1/3.1 192004K106 ..(KA's) ANSWER 1.02 (1.00) d. . REFERENCE
'
YAEC 2009.$.2 EO 912.2 KAI 3.1/3.1 192006K105 ..(KA's)
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ANSWER 1.03 (1.00) a.
REFERENCE , YAEC 200908 EO 908.2 i KAI 3.2/3.3 192003K108 ..(KA's)
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ANSWER 1.04 (1.00) b. P (***** CATEGORY t CONTINUED ON NEXT PAGE *****)
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*- "1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION. . Pegs 23<
. : HEBtiODYNAMICS. HEAT TRAHEEER AND FLUID FLOW-l REFERENCE
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YAEC 200913 EO 913.2 200914 914.2 TS Bases 3/4.1.1 KAI 3.8/3.9 192002K114 ..(KA's) ANSWER 1.05 (1.50)
{ a. Increasing b. Decreasing.
c. Increasing. [0.5 each) (1.5) REFERENCE YAEC 200912 EO 912.1 .5 KAI 3.4/3.4 3.4/3.4 192006K106 192006K107 .. (PA's) ANSWER 1.06 (2.00) a. SDM is increased. (0.5] b. (any 6, 0.3 each) <
-RCS avg temp -Samarium
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-Fuel burnup -Power defect-Xenon concentration -Power level REFERENCE YAEC 200913 EO 913.2,.3 KAI 3.8/3.9 192002K114 ..(KA's)
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ANSWER 1.07 (1.00) e (***** CATEGORY 1 CONT'INUED ON NEXT PA0E *****)
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-- , * . * Paga 24-1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION._ .- T1.EBliODYNAtiLCS. HEAT TRANSFER AND FLUID FLOW ,
REFERENCE-YAEC 200909 EO-909.4 KAI 3.8/3.9 2.9/3.1
'152008K106 192002K114 ..(KA's)
ANSWER 1.08 (1.5d) 1. a 2. b 3. a [0.5 each] REFERENCE YAEC 200911 30 911.2 i KAI 3.1/3.1 192004K106 ..(KA's)
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ANSWER 1.09 (2.00) a. 3 . b. 4 (1.0 each] ! REFERENCC
YAEC 200908 EO 908.4,.5 l KAI 3.8/3.8 l 192008K104 ..(KA's) ! , ANSWER 1.10 (1.00) C REFERENCE j (AEC 200908 EO 908.3 KAI 3.3/3.4 192008K110 ..(KA's)
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. IHEBtiODYNAMICS. HEAT TRANSFER AND_ FLUID FLOW ANSWER 1.11' (1.00)-
b - REFERENCE YAEC 200911 EO 911.4 KAI 3.8/3.9 2.9/2.9 192004K113 192002K114 ..(KA's) ANSWER 1.12 (1.00) 1. To insure minimum shutdown margin is maintained. (MSLB) 2. Minimize the reactivity consequences of an ejected rod OR potential effects of rod misalignnent on associated accident analysis are limited 3. Maintain acceptable axial flux distribution.(power distribution limits)
(LOCA). [any 2, 0.5 each]
REFERENCE , YAEC 200910 EO 910.5 KAI 3.4/3.9 192005K115 ..(KA's) ANSWER 1.13 (1.00) a. Increase ' b. Decrease (0.5 each] REFERENCE ! YAEC 200506 EO 506.5 .7 GP HTFF p.328 KAI 2.9/3.0
- 193006K105 ..(KA's)
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,g '. IEEBdODYNAMICS. HEAT TRANSFER AND FLUID FLOW J , ji . :' ' ~ ' ANSWER 1.14 (1.00) a. FALSE o b. TRUE (0.5 each]
!' REFERENCE YAEC 200506 EO 506.7 GP HT&FF, p 155,320 and Subcooled Liquid Density Tables.
KAI 2.5/2.6 2.4/2.5 193004K111 193005K103 ..(KA's) ANSWER 1.15 (2.50) a. From the Stm Tables, Tsat~for 2200-psia: 649.5 F SCH: Tsat-Th= 649.5-580= 69.5 F (+/-1 F) (0.5 ea) (1.0) b.
' decrease (0.25) Th increasesAas unit delta T increases with power (0.5] (0.75) c. 1(0(25]all MCS f angehes inerease) Core delta T during natural circulation cooldown will approach
- full load delta T. (Thot is greater than in the other 2 cases.) (0.5) (0.75)
! REFERENCE
. < LP 200602 "Characteristics of Water and Steam" EO 502.5,6 i GP HTFF p 356; Steam Tables KAI 3.6/3.8 193008K115 ..(KA's)
i i ANSWER 1.16 (1.00) l a. Saturated, b. Superheated.
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l C 1. PRINCIPLES 0F NUCLEAR POWER PLANT OPERATION,_ Pega 27
. IllEBMODYNAliICS. HEAT TRA)!EFER AND FLUID FLOW REFERENCE LP 200502 "Characteristics of Water and Steam" EO 502.7 '
Steam Tables, Hollier diagram GP HTFF p 83,94.
KAI 2.8/2.8 , 193004K115 ..(KA's) ANSWER 1.17 (1.00) - In the secondary system there is a phase change (0.5]. A phase change requires a large delta h. With the larger delta h of the secondary, the same heat can be transferred with a lower flow rate (0.5]. REFERENCE YAEC 200507 EO 507.4(6.c) GP HTFF, Section 3.2 " KAI 2.8/3.0 193008K101 ..(KA's) ANSWER 1.18 (1.50) 1. Density difference (or DELTA T) (0.33] created by heat addition by the heat source (0.33] and heat removal by the heat sink (0.33).
2. The haat sink must be elevated physically above the heat ). source. [0.5]
- REFERENCE YAEC 200510 EO 510.1,.2
[
! KAI 3.9/4.2 ! ! 193008K121 ..(KA's) l i i ,
. !
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1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION. Paga 28
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H EBtiQDYNAMICS. HEAT TBAILQEER AND FLUID FLOW ANSWER' 1.19 (2.00) a. Turbine power remains constant (or decreases slightly) (0.2) due to decreased steam pressure. (0.2] b. Tavg - Loop 1 increases (0.2) Final value will be equal to core outlet temperature (Th)
= 524 F (0.2] ,
c. Tava - Loop.4 decreases (0.2) Final valve => (total reactor power has not changed; however, the power that each of the non-affected loops must transfer to the S/Gs has increased by 1/3 to compensate for #1 NRV going shut.)
Q:mCp(Delta T) Since Q increased by 1/3, Delta T is the only factor which can increase.
Initial Delta T was given as 18 F, and must increase by 1/3
-> new Delta T = 24 F Final Tavs = Th - (Delta T)/2 = 512 F [0.2]
d. Pstm - Loop 1 increases (0.2] Final value is saturation pressure for Loop i Tavg
= 826.psig (0.2) -
e. Pstm - Loop 4 decreases (0.2) Final value - as with part c above, the appropriate Delta T must increase by *./3. Q:UA(Tavg - Tstm) Initial Delta T = 515 F - 496.5 F = 18.5 F (Saturation temp for 645 psig = 496.5 F) Final Tstm = Tavg - Delta T = 512 F - 18.5(4/3) F
= 487.3 F Final Patm = 591.2 psig (Saturation for Tstm) (0.2)
l l REFERENCE i ' l STM, Chpt 2, pgs 1-2 l Westinghouse "Thermal-Hydraulic Principles" Chpt 5, pg 3 RO/SRO LP #37 "Secondary Plant Heat Balance" E.O.200513 . KAI 4.4/4.6 3.8/4.0 3.2/3.4 3.2/3.6 l 035010K601 035010A205 035010K109 035010K301 ..(KA's) l l
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2. PLANT DESIGN INCI.UDING SAFETY AND EMERGENCY Paga 29
. SYSTEMS (2. lo)
ANSWER 2.01 '2.00) Emerg. Gen. #1 -> brk -> Emerg. Bus #1 -> Brk -> Emerg. MCC #3 -> Emerg. MCC #5 -> brk -> transformer -> UPS #1 -> brk -> (No. 1 Vital Bus.) (1.0) Battery -> #1 DC Bus -> brk -> (-> UPS #1) (0.t]IO.Kf7
#$~ Smit" krvice 7% former (Zacrg. c : r. :: > bra e
>mer. Bua ra ~3 tJr'--> brk -> Bus #5-2 ->
[ brk -> MCC #1 Bus #1 -> brk -> brk -> Batte'ry Charger -> brk ->
(-> #1 DC Bus) -[1.1] [0.65]
[0.3 for each source, 0.1 for each component, 0.05 for each breaker 3 REFERENCE STM 37, fs* . 37-7 ST/t 39, fy' . 31-12.f STM 40, rig. 40-7 RO LP "A/C Distribution" EO 106257 3.1/3.5 3.3/3.4 4.1/4.4 062000K102 062000K201 Oe2000K410 ..<KA s)
ANSWER 2.02 (1.50)
#1 EDG automatically starts.
Incoming supply breakers from 480V Bus 6-3 trip.
When #1 EDG comes up to rated voltage, its breaker closes automatically. [0.5ea) REFERENCE STM 39-3, -33 EO 33C 3.5/3.9 062000K301 ..(KA's) . ANSWER 2.03 (1.50) 1. Valve will be shut (0.35); valve will remain shut (0.40).
s 2. Valve will be open (0.35); valve will remain open (0.40).
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2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY Pago 30 . EXEIEME REFERENCE YNPS Systems Traiaing Manual Chapter 25, pages 23-24, Figure 25 34 Handout for lessoa plan 1/103 objective 1103.J 3.1/3.7 103000K406 ..(KA's) ANSWER 2.04 (1.00) Each gravity operated damper is normally held open by (two) fusible links (which are connected in series) [0.50] Following a LOCA, the links melt, causing the dampers to tihut (0.50)
(isolating the VC Heating & Cooling Fans from the ring duct. One fusible link for each damper melts at 160F, the other at 135F)
REFERENCE Systems Treining Manual Chapter 27, page 5 Systems Training Manual Chapter 27, study question #6 No facility objective identified.
3.3/3.5 0220000007 ..(KA's) r 2.05
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r Dele 6d ANSWER ~ (2.00) a. 187 gpm (+/-10 gpm); 4526 psig (+/-50 psig) b. 900 gpm (+/-10 gpm); 690 psig (+/-50 psig) (0.5ea] REFERENCE STM 19-16, -26 EO 16A 3.5/3.9 '-) 006000K506 ..(KA's) g -
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2. PL6NT DESIGN INCLUDING SAFETY AND EMERGENCY Pago 31
. SYSTEMS ANSWER 2.06 (2.00)
a. CFsrging pumps will continue to run until the high level auto-stop is reached. [0.5) Then they will cycle on and off as level drifts above and below the high level setpoint. [0.5) b. STRONG boric acid --- BAMST -> CS-MOV-529 -> CS-V-702 -> Charging Pump suction. [1.0) (Acc, / y,/ve n,,, nan,,, for [u ll cred//, also.)
REFERENCE STM 15-10, - 13, 17-9 EO-14B, 14F 3.6/4.0 3.1/3.3 4.4/4.6 004010K609 004000G004 004000K101 ..(KA's)
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ANSWER 2.07 (2.00) a. 3 (0,5) , b. 8 (0.5) c. 8 (0.5) d. 2 (0.5) REFERENCE STM Fig 13-29 EO 12F , 3.7/4.0 4.1/4.1 4.5/4.6 ' 002000K109 002000K108 002000K106 ..(KA's) ANSWER 2.08 (2.50) a. 1. 30,450 gallons (+/-500 gal) (0.1]; 8000 gallons [0.2) 2. 275 gallons (+/-10 gal) (0.1]; 210 gallons (0.2) ; b. TM cutle+ ==1u- [n A) 4_ - k-M ;:n g 4--+ pring te--ie- by : tri; ?!re. [0.') The trip .; ire ;;ntain: 'unihl: linh [0.'.] : .d-22:::- -ere-- ~ t:; ;: the a :::1 :nga. to.u. f. e r: ..til-relt th: f ucible lin';; i.. the t r ip ,,1 o m a u.e cal;; :111 -ler.
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;0.2k The outla+ valve Eo.n is a Asible valve (&stble yoke) Co.41. A 4;re c. The Auxiliary Boilers. [0.3) will me/d d$e [usib/t 7 ode n/ ffe y,/vt will close (0 6], (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)
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2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY Pega 32 . sysises REFERENCE Yac Prini YM-c-1, Gal o;t Splem.
STM 39-46,-50 EO 35B 3.6/4.0 064000K103 ..(KA's) ANSWER 2.09 (2.00) a. Electric Driven EBFP-- Normal - PWST (Ib 39 Steam Driven EBFP -- Alternate-Normal DWST (TA.12 )
- DWST ( T%.1 )
Alternste- PWSTA [0.25ec) b. $- lo.5) (Tk. 39) c. A recirculation valve is throttled to maintain the discharge pressure. [0.5) REFERENCE , OP-32o9, STM 3-63, ,4H.
-66,A, Fig.8, C, D, f E.
3-77 EO 32A, -32B 3.9/4.2 061000K401 ..(KA's) ANSWER 2.10 (2.00) a. The first compressor will start when the pressure decreases to 90 psig. The second compressor will start when the pressure decreases further to 80 psig. [0.5] b. The condensate recire. valve to the condenser (BF-CV-405) fails open [0.33) on loss of Control Air, this will cause a Boiler Feed Pump to trip on low suction pressure. (0.33) The reactor will scram on low steam generator level. [0.33) c. The steam dump valve must be manually jacked open and MCS temperature will be controlled manually. (0.5]
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2. PLANT DESIGN INCLUDING SAFETY AND EMEBGENCY Pago 33
. SYSTEMS REFERENCE ST) 5-1, -22; OP-3002 EO 30D, 27A 3.4/3.6 3.2/3.5 ,
078000K402 078000K302 ..(KA's) ANSWER 2.11 (2.00) a. 480 VAC Bus 5-2. [0.5) b. The pumps are located (60 feet) below the elevation of the MCS pipe from which the pump takes suction. [0.5) c. Normally lined up to relieve to the LPST.
Alternately lined up to the primary drain collecting tank. [0.5ea] REFERENCE STM 21-5, -6 EO 15A, 15B 3.0/3.2 3.0/3.2 3.6/3.9 005000K109 005000K401 005000K201 ..(KA's) ANSWER 2.12 (2.0C a. The The SIflow
; r p;ib
-"atiido) el,e Rcs
- char.ge: frc: does th: CI. ni to ckange [I.O.7.
the it eumv. [ 0 , 5 ]- The pux; dicch;r;; cf th LP2I pu=;: i; dirccted to th: suction of the ::PCI pua.pe. [0.5) b. To prevent pump cavitation. (0.5) c. TRUE [0.5) REFERENCE STM 19-55, Fig. 19-42 EO 16D 3.8/4.2 3.9/4.1 000011308 000011K313 ..(KA's)
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2. PLABI_ DESIGN INCLUDING SAFETY AND EMEBQENCY Pago 34
. SYSTEMS I
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ANSWER 2.13 (2.00) a. Water can be supplied #-^- rith;r L;km Chora.en [0.0.I=o from-the fire water storage tank. [0. 5 7 [,1, o] . b. (1.) Overspeed [1.0] REFERENCE STM 8-6 No EO available 3.1/3.7 3.3/3.3 086000A401 086000K401 ..(KA's)
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3. INSTRUMENTS At4D CONTROLS Pcgo 35
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ANSWER 3.01 (1.50) a. Approximately 10EE-7 - 10EE-9 amps. [0.5] b. re nservative (0.5] during a reactor Undercompensation startup because 4.1e 5: isyp!9Yr' inge indication will read higher than actual during tha performance of the startup. (0.5] will also accept--Indicatisns will be closer to the trip values.
REFERENCE
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STM 31-25 thru -28 EC 24C 3.1/3.5* 015000A202 ..(KA's)
(0.50)
ANSWER 3.02 -( i . 5 0 )- p,/e fe/
\ a. 1.) Both.
( 2.) Manually. [0.5 eal 1 b. Intsrmediate Range Channels 3 AND 4. (0.5] NOTE: The Source Range dtartup Rate Scram Bistable is not normally used and is cutout of the circuit.
REFERENCE STM 31-33, -38, -44 EO 24C 4.3/4.5 015000K405 ..(KA's) ANSWER 3.03 (1.00) a. The pressure input is used to compensate the level indication for density differences within the pressurizer. (0.5] NOTE: Pressurizer pressure is used to compensato both the water and steam portions of the pressurizer, q b. The charging pum[ps wilf gotominimuh,ep::d'- rip ( s ,/ uj// (0.5]
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REFERENCE STM 1/.~25; 15-28 EO 14C 3.7/4.0 3.3/3.7 3.8/3.9 011000A203 011000K406 011000K103 ..(KA's) ANSWER 3.04 (2.50)
[0. 50]
a. Main Coolant System Pressure. (0.'F} 1650 psig. [0.25] Vapor Container Pressure. (^ '5} [o.5of 5 psig. [0.25) 't b. Main Steam Line NRVs (4) CCS supply valve (CC-TV-205) CCS retu rn trip valve (CC-TV-208)
":;er ee-+:!r r icel:tien er ter tri;[0.33 en.] ;;V OCV 1, ^7 a
v;.v;; ;
(0.25:13-REFERENCE STM 19-71. -73 EO 160, 16D 4.2/4.4 013000K106 ..(KA's)
. ' j ANSWER 3.05 (1.50) WL-1 Manually ! SIAS-A Manually SIAS A-1 Electrically (0.5ea) REFERENCE STM 19-71 thru 19-73 EO 16C, 16D 3.9/4.3 013000K401 ..(KA's) , i I .iNSWER 3,06 (2.00) i a. Steam Generator Narrow Range level.
Steam Flow.
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3. INSTRUMENTS AND CONTROLG .Paga 37
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REFERENCE STH 3-42 RO 27C L.6/3.8 3.2/3.5 035010K402 035010K401 ..(KA's) ANSWER 3.07 (2.50) a. High SUR of greater than 1.5 DPH hn either IR-3 or -4.) (0.5] b. (Once the high SUR signal is cleared), the rod stop is reset by depressing the reset push-button. [0.5) c. 1. Rod Operations Select,7 switch to the all in position.
2. High Tave while in AUTOMATIC.
3. Manual Rod Selector Switch to the IN position with the Rod Operations Selector Switch in MANUAL.
Y, Scram g.5ea] REFERENCE 7%nre,af STM 34-12, -13 EO 110, 11F ' 3.7/3.8 001000K407 ..(KA's) i ! ANSWER 3.C8 (2.00) ! a. Low S/G Level Trip.
High SUR Trip.
- Low HCS Flow Trip.
! Turbine Trip. [0.4ea)
- b. Greatef'/Less than 15 HWe, (0.4)
! u l REFERENCE l STM 33-9, -10
- EO 21A, 21B i 3.3/3.5
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* . 3. INSTRUMENTS AND' CONTROLS Paco 38 .
ANSWER 3.09 (1.50) a. Test tank effluent flow control valve (WD-FCV-301) shuts.
b. Blowdown tank Level Control Valve (VD-LCV-408) shuts.
c. Surge tank vent valve (CC-RCV-210) shuts. (0.5 ea) REFERENCE STM 35-12, -14 -15, -16 EO 1073.3 4.0/4.3 073000K401 ..(KA's) _
, - De le ek
' ANSWER 3.10 (2.00) q 1 a. The purpose of the Non-Return Valve Scram is to limit the cooldcun l of the MCS [0.5] following a main steam line break accident. (J.5] l b. The trip is reset by holding the trip switch in the RESET position j [0.57 and turning the block switch to BLOCK. (0.5] l REFERENCE . STM 33-14 -17 i 3.9/4.3 3.3/3.6
EO 21A, 21B ^ 012000K604 012000K402 ..(KA's)
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l a. Main Coolant System over-pressure. (0.5) i b. Uncontrolled rod withdrawal, j Loss of turbine load. (0.5ea) ! REFERENCE STM 33-19 EO 21A, 21B
- 3.9/4.3 012000K402 ..(KA's)
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ANSWER. 3.12 (1.50) a. Restart with a (10 sec.) time delay.
b. Restart immediately, c. Will not start. [0.5ea] REFERENCC STM 19-28, 15-12 EO 140, 16C 3.5/3.9 000058K301 ..(KA's) J ANSWER 3.13 (2.00) i ' n. Pressurizer Wide Range Pressuce.
Main Coolant System LTOP Pressure.. ! Core exit thermocouples.
,' Reactor Head Thermocouple. (0.4ea) ,
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b. The red dot means that the unit is in test. (0.4] j REFERENCE l STM 14-31,-32
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4.3/4.6 3.9/3.4 l E0 12C l 002000A104 000074A113 ..(KA's) i i l ANSWER 3.14 (2.00) a. 1. Flow is regulated by adjusting the Component Cooling flow to ' the Shutdown Cooler. (0.5] l l 2. CC-TCV-200 control signal is shifted from the LPST temperature i to Shutdown Cooling Pump suction temperature (0.5] and the
- bypass around CC-TCV-200 is throttled (to keep CC-TCV-200 from l
going fully shut). (0.5] - b. They are prevented from opening unless Pressurizer pressure is l
; less than 375 psig. (0.5]
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* 4. PROCEDUBES - NORMAL _1 ABNORMAL... EMERGENCY Pego 41 'ANL_ RADIOLOGICAL CONTROL .
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ANSWER 4.01 (2,50) level a. -UnexpectedArise in one S/G with feedwater flow stopped or reduced.
-A decrease in feedwater flow prior to reactor trip. .
-High radiation'from steamline monitor or hand held survey !
i instrument. (0.25each] [
- b. The leakrate greater than the capacity of one charging pump. (0.5]
c. To minimize heat transfer to the faulted steam generator. (0.5] l, d. -HCS pressure dr-PZR level drops s(below1700)d.
50 inche drops (felow(below 40 degrees-F).
-MCS subcooling (0.25 each)
REFERENCE l YAEC OP-3107 and Attachment A EO 304.1 ! , RO LP "Emergency Procedures" #RO-1999-005-1 I KAI 4.2/4.5/4.6/4.3 ' 000038G011 000038A203 000038K306 000038K308 ..(KA's) !
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2. Failure of two or more control rods to drop after a scram.
3. Unexplained or uncontrolled reactivity insertion (also considered i an ATWS event) (0.5 each) i { l b. 1. Scram the reactor.
l 2. Lineup charging pump discharge to normal charging line.
} 3. Open boric acid mix tank valve,(CS-MOV-529) t i 4. Start all charging pumps at maximum flow. . i 5. Close the following valves to the charging pump suction: ' l -Low press surge tank (CH-HOV 521) [ l -Safety injection tank (CS-MOV 540) [ l -Purification ion exchangers PU-FICV-202) L j -Primary water storage tank (DW-MOV-655) i 6. Establish sufficient bleed flow to prevent PZR level from increasing to the charging pump auto trip setpoint.
7. Initiate OP-3300, "Classification of Emergencies".
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. AE_ BAD 1QLOGICAL CONTROL REFERENCE YAEC OP-3105 EO 1009.4 RO/SRO LP 3004 "Emergency Procedures" E.O. 304.1 KAI 4.4/4.4 000024K302 000024K301 ..(KA's)
ANSWER 4.03 (2.25) a. MCS pressure.
PZR heaters.
SI pumps and valve positions (as prevention or mitigation of a LTOP event) [0.5 each) b. 450 psig (0.25).
c. To prevent control rod housing seal weld deformation. [0.5) REFERENCE YAEC OP-2100, p 4-6 EO 1056.4. 6 LP 3002 "Operating Procedures General Plant Operations" EO 3002.1 KAI 3.9 0020SG0010 ..(KA's)
(l.50)
ANSWER 4.04 fi . '5 )- a. -Improper rod motion-Improper load change-Reactivity addition by dilution-Reactivity addition by Xenon buring out-Instrument malfunction (4 required. 0.25 each) b. Check Tc and Th in all loops (0.25) Check reactor power and load (0.25)
: A driicated :;: rater ch:11 to a t u.m . vd muc.t rui s ec t iv.. v' t h t >"
"'E --{ 0 . 2 G "
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4. PROQEDURES - NORMAL. ABNORMAL, EMERGENCY Pega 43
, AND RADIOLOGICAL CONTROL REFERENCE YAEC OP-3535 EO 304.1 KAI 4.0/3.8 00100GK001 001010A101 ..(KA's)
ANSWER 4.05 (2.00) a. Loop Delta T (less than full power Delta T) Loop Tc (constant or decreasing)
(following Tsat for SG conditions)
Loop Th (stable not increasing) CET's (No abnormal difference between CET's and loop Th)[0.25 each) b. Prsvent void formation (0.5) under the reactor head (0.5).
REFERENCE OP-3054, p 2,3. 20 304.1 RO/SRO LP "Shutdown Cooling" EO 200507 KAI 4.2/4.* 000074K3'41 000074K301 ..(KA's) . ANSWER 4.06 (2.50) a. Incore thermocouples >650 F OR ' Uncontrollably increasing thermocouple temperature indication.
(0.25 ea.)
b. 1. Safety Injection or charging pumps are available.
2. MCS depressurization not available via steam dump.
3. Feedwater not available. (2 0 0.5 na.)
' c. 1. If not sufficient level (>10 feet) in 2 steam generators.
2. Auxiliary or main feedwater not available.
3. Main condenser not available. (2 @ 0.5 ea.)
REFERENCE OP-3053 pp. 1, 2 EO 46B 4.0/4.4 4.5/4.6 . 000074G011 000074K311 ..(KA's)
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.. AND RADIQLOGICAL CONTROL
, ANSWER 4.07 (1.75) a. VC evacuation (0.25) alarm and increased audio count-rate signal. [0.25) ; A large increase in neutron flux would occur prior co any ;
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- OP-3117 p. 1, 2, 5, 6 EO 460, 46D ,
3.4/4.1 3.7/3.8 3.7/4.1 ! 000036K303 000036G010 000036A202 ..(KA's) *
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s l 4.08 ' ANSWER (2.75) i ! a. Emergency borate, (0. 8T.4f (
- manually open the scr,)am breakers, (0 761.45 ;
open circuit No. 12 C,RD power supply on No. 2 battery [ . ! switchboard. [0.K qs45 uc , i t i b. 1650psig--AUTO (b31SafetyInjection(0)5$ f ! ,
-1:00 p:i:-- Man"at c0.:] trip r.cr. :0.:: - . L
! j c. TRUE (0.5] : ! REFERENCE i
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I OP-3000 pp. 1, 2 l ! EO 46B, 460 i l 4.5/4.5 4.0/4.6 ! ! 000007K301 0000290010 ..(KA's) I ! ! i ! I
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ANSWER 4.09 (2.00) a. Any area accessible to personnel (0.25] in which there exist s radiation, at such levels that a major portion of the body '.0.25) could receive in any one hour (0.25) a dose in excess of 100 mrem.
[0.25] b. 1. His/her accumulated dose is nearing the dose limit on the RWP.
2. His/her pocket dosimeter is nearing 3/4 of full scale.
3. His/her pocket dosimeter is off-scale. aai tbec at . 4. His/her pocket dosimeter is lost or damaged. (0.33] REFERENCE OP-8403 p. 3; OP-8100 p. 1 EO 2B, 4A, 4B 2.8/3.4 194001K103 ..(KA's) ANSWER 4.10 (1.00) 1. Motor lead cables removed.
2. Valves locked closed. (0.5 ea) REFERENCE STM 21-2 EO 100507, 100509 3.3/3.4 005000G007 ..(KA's) ANSWER 4.11 ((l.co 0 . 0 ^ ,) a. Place the operable S1 pumps control switches in the AUTO position, (0.5] and the SI initiation channels cutout switches in the AUTO-START position. [0.5) I b.
L Modes 1, 2, 3 (0.33 ea.] [b/'k .
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REFERENCE OP-2652 p.2; Technical Specifications 3.5.2
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4.1/3.9 4.4/4.4 3.6/4.2 0060000011 006030A401 On6000A401 ..(KA's)
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a. MCS subcooling Margin <35 F (0.26) and j VC pressure of >5 psig (0.25) ;
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b. 30 min. (0.25] ' c. 1. MCSpressure(<SIsetpoint(1850psig)).
, 2. Pressu j 3. (<40 subcooling.
F)rizer level (<130 inches). (L 45 ea.) l
; REFERENCE l
! OP-3106 pp. 2, 4; Att. A p. 2
4.1/4.2 4.5/4.5 4.4/4.6 , j 000011K312 000009K328 000011K314 ..(KA's) [
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. . * TEST CROSS REFERENCE Pcgo 1 '
QUESTIOt! _yAINE REFEREt!CE_.
1.01 1.10 ZZZ0000001 1.02 1.00 ZZZ0000002 1.03 1.00 ZZZ0000003 , 1.04 1.00 ZZZ0000004 1.05 1.50 ZZZ0000005 1.06 2.00 ZZZ0000008 1.0. 1.00 ZZZ0000007 1.08 1.50 ZZZ0000008 1.09 2.00 ZZZ0000009 1.10 1.00 ZZZ0000010 1.11 1.00 ZZZ0000011 1.12 1.00 ?7.o000012 1.13 1.00 ZZZ0000013 1.14 1.00 ZZZ0000014 1.15 2.50 ZZZ0000015 i 1.18 1.00 22Z0000016 l 1.17 1.00 ZZZ0000017 1.18 1.50 ZZZ0000028 1.19 2.00 ZZZ0000019 , ,
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25.00 2.01 2.50 22Z0000020 2.02 1.50 ZZZ0000021 2.03 1.50 ZZZ0000022 2.04 1.00 ZZZ0000023 2.05 2.00 ZZu0000024 2.06 2.00 ZZZ0000025 2.07 2.00 ZZZ000002G 2.08 2.50 ZZZ0000027 2.09 2.00 2Z20000028 2.10 2.00 ZZZ0000029 2.11 2.00 ZZZ0000030 2.12 2.00 ZZZ0000031 2.13 2.00 ZZZ0000032
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25.00 3.01 1.50 ZZZ0000033 3.02 1.50 ZZZ0000034 . 3.03 1.00 ZZZ0000035 3.04 2.50 ZZZ0000038 3.05 1.50 ZZZ0000037 3.08 2.00 2220000038 3.07 2.50 ZZZ0000039 3.08 2.00 2220000040 3.09 1.50 ZZZ0000041 3.10 2.00 ZZZ0000042 3.11 1.50 2220000043 3.12 1.50 ZZZO300044 3.13 2.00 ZZZ0000045 3.14 2.00 22Z0000046
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14.01 2.50 ZZZ0000047 ' e. TEST CROSS REFERENCE Page 2 QUESTION _YALUE REFERENCE.
,4.02 3.00 2Z20000048 - 4.03 2.25 ZZZ0000049 4.04 1.75 ZZ20000050 !
' '4.05' 2.00 ZZZ0000051 4.06 2.50 ZZZ0000052 .
L 4.07 1.75 Z220000053 4.08 2.75 ZZZ0000054 , 4.09 2.00 ZZZ0000055
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4.10 1.00 ZZZ0000056 < i 4.11 2.00 ZZZ0000057 4.12 1.50 22Z0000058 ; ______ i 25.00 [ ______ ______ 100.0 [ DOCKET NO 29 ; t
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, .. ATTACHNEliT 2 ..
Jj U. S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION FACILITY: YON $gg-BQWg__, ,_________ REACTOR TYPE: EWB-WEG4 DATE ADMINSTERED: QWLQ241}_________________ EXAMINER: ISQUE N P.______________ CANDIDATE .. . _. _ ___ IUSIB9GI19US_IQ_G602106IEL Une separate paper fo- the answers. Writt answers on one side only.
Staple question sheet on top of the answer sheets. Points for each question are indicated in parentheses citer the question. The passing grade requires at least 70% in each category and a final grade of at least 80%. Examinatier, papers will be picked up six (6) hours after the examination starts.
% OF CATEGORY % OF CANDIDATE'S CATEGORY __YsLUE_ _IQI6L ___EGQBE___ .Y6LUE__ ______________G6IEQQSY_____________ 2544
.;Q,,QQ__ _2;&20 ___________ ________ 5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS,AND THERMODYNAMICS 23.00 23,57
_i@IT9__ _EErk2 ___________ ________ 6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTAT'7N e2t'. 50 .2 S./ 3 25sil__ .52x22 ___________ ______._7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOG1 CAL CONTROL 254f .______ 8. ADMINIb a r:ATIVE PROCEDURES, _32 92__ _I5x2i=
. ___________
CONDITIONS, AND LIMITATIONS fl. 5 Ji9 SIT __ ___________ ________% Totals Final Grade All work dcne on this examination is my own. I have neither given
=
ner received aid.
- p) _ _ _ _ _ _ _ . i = _ _ AL._y_________ 1 I Candidate's Signature
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NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rulou apply: 1. Cheating on the examination means an automatic denial of your application and could result in more severe penalties.
2. Restroom trips are to be limited and only one candidate at a time may leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.
3. Use black ink or dark pencil only to facilitate legible reproductions.
4. Print your name in the blank provided on the cover sheet of the examination.
5. Fill in the date on the cover sheet of the examination (if necessary).
6. Use only the paper provided for answers.
7. Print your name in the upper right-hd.nd corner of the first page of each section of the answer sheet.
8. Consecutively number each answer sheet, write "End of Category __" as appropriate, start each category on a new page, write only on one side of the paper, and write "Last Page" on the last answer sheet.
9. Number Sach answer as to category and number, for example, 1.4, 6.3.
10. kip at least three lines between each answer.
11. Separate answer sheets f ron, pad and place finished answer s'.ieets f ace down on your desk op- table.
10. Use abbreviations only if they are common)v used in facility literature.
13. The point value for each question is indicated in parentheses after the question and can be used am a guide for the depth of answer required.
14. Show all calculations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or not.
15. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLANK.
16. If parts of the examination are nat clear as to intent, ask questions of the examiner only.
17. You must sign the statement on the cover sheet that indicates that the , work is your own and you have not received or been given assistatice in [ completing the examination. Thi s must be done af ter the examination has been completed.
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. . 18. When you complete your examination, you shall a. Assemble your examination as followns (1) Exam questions on top.
(2) Exam aids i figures, tables, etc.
(3) Answer pages including figures which are part of the answer.
b. Turn in your copy of the examination and all pages used to answer the examinat. ion questions.
c. Turn in all scrap paper and the balance of the paper that you did not use for answering the questions.
d. Leave the examination area, as defined by the examiner. I f- *ter leaving, you are found in this area while the examination is still in progress, your license may be denied or revoked.
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Ut__IUEQBY_DE_'UUGLEGB_EQbEE_ELGUI_DEEBOIlQU2
, ELW1932009_IUEBd9kfueb1GB QUESTION 5.01 (1.00)
Increasing the boron concentration at a low temperature has little effect on the Moderator Temperature Coefficient as compared to higher operating temperatures because: (choose the one answer, from below, that correctly completes the sentence) a. water density does not change as much at low temperature.
b. water density is greater at lower temperatures so neutron leakage is less.
c. water density is greater at lower temperatures so parasitic neutron absorption is greater.
d. baric acid is less soluble at lower temperatures.
QUESTION 5.02 (1.00) Which one of the following statements concerning Xenon-135 production and removal is correct? a. At full power, equilibrium conditions, about half of the Xenon r i tu produced by Iodine decay and the other half is produced as a direct fission product.
, b. Following a reactor trip from equilibrium conditions, Xenon peaks > I because delayed neutron procursors continue to decay to Xenon while neutron absorption (burnout) has ceased.
c. Xenon production and removal increases linearly as power level increases; 1.e., the value of 100% equilibrium Xenon is twice that of 50% equilibrium Xenon. : r d. At low power levels, Xenon decay is the major removal method. f At high power level.s, burnout is the major removal method.
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. ' Pcgo 3 Dz__IUEQBi_QE_ NUCLE 68_EQWEB_EL6UI_QEE66I1QU2 . ELUID3200D_IUESdQDXUed1GS QUESTION 5.03 (1.00)
As the core ages, the ratio of PU239 atoms to U235 atoms increases.
This changing ratio causes thet (Choose the one answer, from below,that correctly completes the sentence) a. reactor startup rate (SUR) to increase, for the same reactivity
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addition.
b. Void Coefficient to become less negative.
c. Moderator Temperature Coefficient t) become less negative.
d. delayed neutron f r action to increase.
. QUESTION 5.04 (1.00) Which cro of the following statements concerning Shutdown Margin (SDM) is correct? a. The maximum SDM requirement occurs at EOL and is based on a rod ejection accident.
b. The maximum SDM requirement occurs at EOL and is based on a steam line break accident.
c. The maximum SDM requirement occurs at BOL and is based on having a positive moder ator temperature coefficient.
d. The maximum SDM requirement occurs at BOL and is based on a rod withdrawal accident while in the source range.
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Di__IUE98Y_9E_UUGLEeB_E99EB_EL6UI_9EEB9I1902 '. ELUIDD400D_IUEBd99YUBd1GH QUESTION 5.05 (1.50) The reactor is taken critical with Xenon concentration at zero. Power is raised to 50% at 5%/hr.
Using one of the following choices; Increasing. Decreasing, or At Equilibrium, describe how Xenon concentration will be trending for each of the following situations (a,b, and c), a. One hour after a trip occurs as power reaches 50%. b. Four hours after the trip occurs the reactor is taken critical and power raised back to 50%. c. If reactor operation continues and power level is maintained at 50% for one hour.
QUESTION 5.06 (2.00) a. How is Shutdown Margin (SDM) affected (Increase, Decesase, or No ch.nge) by a 50 ppm boron addition while operating at 50% power?
(0.5) i b. List FIVE factors, other than RCS boron concentration and rod position, which will affect SDM and are used in the SDM calculation. (1.5)
CUESTION 5.07 (1.00) Which one of the following conditions would cause a 1/M plot to be NON-conservative during fuel loading? a. Fuel being leaded closer to the neutron source than to the source range detector, b. Loading fuel in the order of high reactivity worth to low reactivity , worth, c. Loading poison rods between the source range detectors and spaces to be filled by fuel assemblies.
d. Increasing the boron concentration in the moderator.
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. ELW1QSiOUD ISE600DXU651GH QUESTION 5.00 (1.50) Match the parameter change in Column A to the direction it will change the Moderator Temperature Coefficient (MTC) in Column B. Consider each case separately.
COLUMN A COLUMN B 1. Moderator temp"rature increases a. More Negative 2. Baron concentration increases b. Less Negative
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3. All rods in vs. all rods out c. No Effect OUESTION 5.09 (2.00) If the Source Range (SR) instruments indicate 50 cps with Keff equal to 0.9, what would the SR instrument indicate if rods were withdrawn to bring Keff equal to 0.957 Assume BOL conditions.
a. 1. 50 cps 2. 75 cps 3. 100 cps 4. 200 cps (1.0) 6. How much reactivity was added? 1. 0.0347 2. O.0500 3. 0.0526 4. 0.0585 (1.0) ,
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. ELVIDS400D_IUEBOQDXUedlGH QUESTION 5.10 (1.00)
Which one of the following correctly describes the observed ritactor response for the same smali, addition of reactivity, one positive and one negative? a. The response will be faster for the negative a'Jdition at all times in core life.
b. The response will be faster for the negat!ve addition at Bf/L but faster f or the positive addition at ECL . c. The response will be faster for the positive addition at all times in core life.
d. The response will be faster for the positive addition at EOL but faster for the negative addition at EOL.
e. The response will be the same for both the positive and negative addition.
QUESTION 5.11 (1.00) Which one of the following statements concerning power defec': is correct? a. The power defect is the difference between the measured power coefficient and the predicted power coefficient.
b. The power defect increases the rod worth requirements ne:essary to maintain the desired shutdown margin following a reactor trip.
l c. Because of the higher baron concentration, the powe def ect is ' more negative at becinning of core life.
4. The power defect necessitates the use of a constant Tavg program to maintain an adequate Reactor Coolant System subcooling margin.
QUESTION 5.12 (1.00) State TWO reasons for establishing Power Dependent Insertion limite.
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QUESTION 5.13 (1.00) ) A centrifugal pump is operating at rated . low when the discharge valve is throttled towards the shut direction. For each of the following indicate whtither the parameter will increase, decrease or remain the same, after the valve is throttled in the shut , direction.
a. NPSH
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b. motor amperage t GUEST 10N 5.14 (1.00) TRUE or FALSE a. During a RCS heatup, as tempceatura gets higher, it will i
- take a smaller letdown flow rate to maintain a constant '
1 pressurizer level. [ b. Increasing condensate depression (subcooling) Hill cause t
'BOTH a decrease in plant efficiency AND an increase in condensate (hotwell) ptimp available NPSH. ,
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OUESTION 5.15 (2.50) u. What is the subcooling margin (SCM) of the RCS if the following conditions exist? Yh =530 F Fressurizer pressure =2105 psig Tc =520 F Steam Generator Pressure =850 psig (1.0) b. ; 1- power is raised from 50 to 100%, how AND why will SCM change "
(increase, decruase, stay the same)? ,
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c. Which one of the following would result in the smallest SCM7 Briefly explain your choice. Assume identical RCS pressures. (0.75) 1. SCM during a controlled natural circulation cooldown following a reactor trip from loss of flow.
2. SCM during continued operation at 5% power.
, 3. SCM prcduced when all RCP's are operated at normal no-load L temperature after extended shutdown. [ t i QUESTION 5.16 (1.00) ! At each of the following leak locations, indicate the state of the [' exiting fluid (subcooled, saturated, or superheated). Assume normal 100% power initial operating plant conditions.
a. PZR steam space to CTMT atmosphere.
I b. Main steam header to turbine building atmosphere.
OUESTION 5.17 (1.00) , f
Primary system flow rate is many times greater than secondary system flow rate while the heat ter.nsf erred by the two systems is essentially 7 the same. Explain how this is possible. [
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OUESTION 5.18 (1.50) l List all of the conditions / requirements that must be present in order ( for natural circulation to exist. [ t L l (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)
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QUESTION 5.19 (2.00) The plar.t is operating at 33% power when 41 Non-Return valve fails shut.
Using the given initial conditions, determine the new steady state values / conditions for the below parameters. Assume no operator action, no reactor scram, and that all control systems are in automatic with the exception of rod control. Justify your answers with calculations and/or discussion.
Initial Conditions: Tavg = 515 F Patm = 645 psig Core Delta T = 18 F a. Turbine power b. Tavg - Loop 1 c. Tavg - Loop 4 d. Pstm - Loop i e. Pstm - Loop 4 f
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QUESTION 6.01 (1.50) a. What is the function of the Pressuri:er Wide Range Pressure input to the Pressurizer Narrow Range Level channel? (1.0) b. With the reactor at 100*/. power and all systems in a normal configuration, how will a failure of the power supply to PP-P-700, Pressuriger Wide Range Pressure, effect the speed of the operating charging pumps? (0.5) QUESTION 6.02 (1.50) a. State whether the following SIAS relays can be reset MANUALLY or ELECTRICALLY.
WL-1 GIAS-A SIAS A-1 QUESTION 6.03 (2.00) . The following concern the Rod Control System.
a. What will cause an outward rod stop? Include applicable setpoints)
(0.5)
b. What action is required to allow outward rod motion subsequent to the rod stop mentioned in a. above? (0.5) c. What are THREE ways to produce inward rod motion? (1.0) QUESTION 6.04 (1.50) a. List the parameters that are used as inputs to the Main Coolant Satoration Monitor. (four required) (1.0) b. What is meant by a rod det when observed on the digital read-out on the Main Coolant Saturation Monitory (0.5)
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QUEOTION 6.05- (1.50) r Assume an SIAS signal is present.
state how each of the following pieces of equipment will respend to a loss of normal power supply and subseque.1 ee-energi:ation via the ,
; Emergency Diesel Generator. (Limit year answer to START IMMEDIATELY, - '
START WITH A TIME DELAY, or WILL NOT START AS A RESULT OF THIS l CONDITION.) s i a. High Pressure Safety Injection pump.
b. Low Pressure Safety Injection pump. t c. Charging punps.
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OUESTION 6.06 (1.50)
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a. In addition to preventing water relief through the safety valves, ] what Main Coolant System condition does the High Pressurizer Water f
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Level scram provide protection against? (0.5) i l b. State TWO events for which the High Pressurizer Water Level f' provides protection for the Reactor Core. (1.0) i c _ r Deleled' ;
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QUESTION 6.07 (2.00) l l a. State the purpose of tne Non-Return Valve (NRV) Scraca. J $ '
; b. How is the NRV trip reset if Main Coolant pressure is less than l {
1800 psig with low steam generator pressure? i s I
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QUESTION 6.08 (2.00) [ ,
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During power operations at 100X, the instrument air (IA) line to the I/P i l converter for Pressurizer Narrow Range Level (PR-L-6) becomes blocked !
causing the IA supply pressure at the converter to drop to O psig. With ! no operator action, describe the resultant plant transient to the point of [ steady state or ES actuation. State all assumptions. i t I ! i '
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QUESTION 6.09 (3.00) The following concern the Fire Protection systems a. Describe the various responses of the pressure maintenance system to a low pressure condition. (Setpoints not required) b. By what TWO methods is the pressure maintenance system protected from an over-pressure condition? c. If the diesel-driven firewater pump has started with the control switch in the MAN 1 position, what TWO conditions will stop the engine? QUESTION 6.10 (2.50) For each of the process radiation monitoring channels listed belows a. State whether or not any automatic action is associated with its high radiation alarm. If YES, state what that action is. (1.5) b. State whether or not a high radiation alarm will be generated upon loss of power to the channel. (1.0)
(1) Steam Generator #1 Blowdown (2) Steam Gennrator Blowdown Tank Effluent (3) Component Cooling (4) Main Coolant System Bleedline (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
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State the position of SW-TV-412 prior to receipt of the VCIAS signal AND how it will respond to the signal. Consider each case separately.
(1) Train A in Test, Train B in Bypass (2) Both Train A & B in Bypass (1.5) l
- OUESTION 6.12 (3.00) . ,
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' The following concern the operation of the Low Temperature
! Overpressurization System (LTOP), include setpoints as appropriate:
1; a. Assume the LTOP system is in operation and MCS pressure is 350 psig. : i What signals will PR-SOV-90 and PR-MOV-512 receive and how will each valve respond if pressure increases to 550 psig and then decreases ,
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back to 350 psig?
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b. What are the THREE conditions that will cause the "LTOP System Misaligned" alarm to actuate?
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. BUD _ BOD 1QLQQ1G86_GQUIBQL OUESTION 7.01 (3.00)
The following concern OP-3324, Appendix B, "Criteria for Emergency '
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Exposure".
a. List the THREE individuals (by title) who may authorize emergency exposure in excess of 5 Rem.
b. What is the acceptacle Emergency Re11ation Dose for each of the following emergency conditions, include both Whole Body dose AND Total A!.aowable doses t 1. Stable conditions , 2. Severe conditions . 3. Extreme conditions
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i h ' OUESTION 7.02 (2.50) While maintaining the plant in a Hot Standby condition, system 1 parameters are to be maintained as shown belowl state the basis for maintaining each parameter as shown, according to OP-3018 "Plant Shutdown with the SSS" procedure.
1. SG Levels............) 10 feet (in at least 2) 2. Pressurizer level . . . 60 inches or as f ound (whichever is greater) 3. MC Temperature. . . . . . .Consi stent wi th Temp P-T li mits 4. SG Pressure..........< 900 psig and consistent with Tc , 5. Source Range. . . . . . . . .Not increasing
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i CUESTION 7.03 (2.00)
- You are the Refueling SRO during a fuel shuffle when you are notified ;
that the level in the Spent Fuel Pit is decreasing. I'i accordance with I OP-3117 "Refueling Accidents", what are the FOUR Immediate Operator Actions 7 i $ l ! J l
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QUESTION 7.04 (3.50) The following concern OP-3107, "Steam Generator Tube Rupture" procedure.
a. State THREE methods used to idertify the faulted Steam Generator (S/G). (1.5) b. What is the criteria for scramming the plant? (0.53 , c. What is the reason / bases for tripping,the RCP associated with the faulted S/G7 (0.C) , d. After SI has been terminated, what is the SI re-initiation criteria? THREE criteria requir ed. (1.0)
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OLESTION 7.05 (3.00) : The following concern OP-3105, "Emergency Boration Injection" procedure.
a. State the THREE conditions which may require immediate borir acid l i n j ect' on . b. List FIVE of the seven required immediate coerator actions.
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a. A dedicated operator at the Main "ontrol Board is responsible to monitor the status of what THREE separate indications / systems? (1.5) ; I b. What is the limit on MCS pressure when LTOP is in service, and MCS I temperature is less than or equal to 380 degrees-F7 (0.75) I t c. Why must MCS pressure be greater than or equal to 200 poig before [ operating the control rod drives? (0.75) l (+++++ CATEGORY 7 CONTINUED ON NEXT PAGE *****)
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OUESTION 7.07 The following concern OP 3535, "H4gh T-Average" alarm procedure.
. a. List FOUR separate poss$ bin causen foi* the alarm. (1.0) b. What are the TWO immediatu operator actions associated with this alarm? (1.0)
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OUESTION 7.00 (3.50) The f ollowing concern CP-3002, "Less of Control Air Supply" procedure.
, a. Explain why the reactor will eatomatically scram due to a continu7d decrease in control air presdure. (1 0) 6. For a complete loss of control air, prompt operator action is directed to what FOUR principle objectives? (2.0) c. This prompt operator action, in b. above, is required to avoid ,
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which particular situation / condition? (0,5) OUESTION 7.09 (2.00)
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The following concern OP-3054, "Natural Circulation" procedure, a. What FOUR parameters are monitored, for verification that NC is proceeding normally? l i b. What is the basis f or the f ollowing requirements / limits? l
' "If it is desired to perform a cooldown on NC, limit the cooldown rate to F.O F/Hr and ensure that a subcooling maratn of at least 40 F is maintained."
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QUESTION 8.01 (3.00) f The concentration of the boric acid solution in the Safety injection j Tank (SIT) shall bw verified once per 7 days in accordance with ! Technical Specification 3.5.4. The chemist sampled the S!T on the [ following schedule. (All samples taken at 1200 hours). ! l a July 25 --- Aug 1 --- Aug 8 ---h g 16 --- Aug 24 --- Aug 31 {
a. EXPLAIN why surveillancu time interval requirements were or l were not exceeded on Aug 16.
t b. EXPLAIN why surveillance time interval requirements were or l were not exceeded on Aug 24. i ! [ ] } 4 i j QUESTION 8.02 (3.00) } l I Answer the following in accordance with AP-9017 "Switching and Tagging of l t .; Plant Equipment": I
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a b. WHO .nay perf orm the independent verification f or equipment that i
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j requires Qur~ atty Assurance? (0.50) 1 l ! c. When equipeint is to be returned to service, HOW is the verification l ] of propv' equipment / system alignment accomplished on equipment t i requirirg Quality Assurance? (TWO methods required) (1.00) } ' i
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- According to Technical Specifications, What are the THREE provisions i i
that must be met whenever a temporary change is made to an approved [
- operating procedure? Include applicable titi.7s and time limitations. !
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6SD_ Lid 1IGI1Qua CUESTION 0.04 (2.00) What are the operator actions required by Technical Specifications, if the safety limit for RCS pressure has been exceeded during the following? Include applicable time limitations.
a. Mode 1 operation.
b. Mode 3 operation.
QUESTION 0.05 (3.30) Answer the f ollowing in accordance with AP-0006 "Radiation Work Permits Requests and Use": a. What does the Shift Supervisor's 6.gnature on the RWP signify? (1.0) b. State FIVE areas / activities that require an RWP? (2.5) QUESTION 0.06 (1.50) What is the bases / reason for the Technical Specification requirement to be in Hot Standby with Tavg (, 514-F when the specific activity of the RCS is above the TS limit? OUESTION 0.0/ (2.50) For each of the following, indicate the type of RCS leakage classification as defined in Technical Specifications.
a. Leakage through a valve packing that is routed to a coolant drain tank.
b. Steam generator tube leakage.
c. Slight seepage through an elbow socket weld on a RCS instrument line.
d. Valve packing leaks of unknown origin.
e. Reactor vessel flange leakage.
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000.6101IGIIQU2 OUESTION 0.00 (2.50) Given Attachment /, Technical Specification (TS) 3/4.5, "Emergency Cor e Cooling System", IDENTIFY the applicable Action statement, if any for each of the f ollowing sets of conditions listed below. Consider each case separately.
l a. SI-MOV-1 cannot be confirmed open.
b. Accumulator baron concentration is 2100 ppm.
c. Accumulator nitogen supply pressure-regulating valves are set at 475, 465, and 460 psig, respectively.
d. Accumulator nitrogen covee pressure is 20 psig AND accumulator level (PR-LT-3) is < 260".
e. TEN 48 cubic foot nitogen bottles are > 1400 psig, EIGHT 48 cubic foot nitrogen bottles are > 1350 psig.
QUESTION 0.09 (2.00) Answer the following in accordance with Yankee Technical Specifications.
Assume the plant is in a Hot Standby C(nditions a. What action (s) is/are required if operating with minimum crew composition and one of the R0s becomes incapacitated? Includo
'plicable time limits.
b. Is the following action proper by the Shift Supervisor? Justify.
15 minutes before scheduled arrival of the on-coming shift, an oncoming RO calls in sick. The on-shift SS decides, due to his shift's preaent overtime situation, to call in a replacement.
The SS also decides that since the replacement should arrive shortly after shift change (about 30 minutes), to send his people home and let the next shift start one person short of minimum.
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The following concern OP-3315, Control Room Operations During An Emergency procedure, a. Who by job title / position assumes the datias of the Plant Emergency l Director (PED) if the Shift Supervisor is unavailable or ! incapacitated? (0.5) I b. During a backshift, how is the Yankee Emergency Response ' Organization notified of a plant emergency? (0.5) c. How is the Massachusetts State Police notified? Include the normal and backup methods AND any time limits associated with this notification. (1.5) l d. Who performs the Emergency Center Habitability procedure? (0.5) , i e. Can the event be classified and reported at a lower EAL, if plant conditions ha're returned to a lower EAL before any i notifications have been made? (0.5) , l l l l
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ANSWER 5.01 (1.00)
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REFERENCE ! I YkEC 200911 EO 911.2
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KAI 3.1/3.1 192004K106 ..(KA's) ANSWER 5.02 (1.00) d.
ItEFERENCE YAEC 200912 EO 912.2
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KAI 3.1/3.1 192006K105 ..(KA's) ANSWER 5.03 (1.00) a.
REFERENCE YAEC 200906 EO 908.2 KAI 3.2/3.3 l 19:003K106 ..(KA's) l ANSWER 5.04 (1.00) b.
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f REFERENCE YAEC 200913 EO 913.2 f 200914 914.2 TS Bases 3/4.1.1 ,
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ANSWER 5.05 (1.50) a. Increasing. i b. Decre :g . c. Increasing. CO.5 each3 (1.5) . REFERENCE
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YAEC 200912 EO 912.1 .5 i
;
KA! 3.4/3.4 3.4/3.4 19:006K106 192006K107 ..(KA's)
!
r ANSWER 5.06 (2.00) i f a. SDM is increased. CO.53 [ i b. -n, 5, ^_ ? r rr' 2 A (
,
'
-RCS avg temp EO s3 -SamariumEDI2-Fuel burnuple.63 -Poww- defect 4
~ Xenon concentration 9 -Power level $
VE E ENCE ' ~ " ~ f"'s * * I**f * * ** * "W * lIEN* I YAEC 200913 EO 913.2. 3 KA! 3.8/3.9 f 192002K114 ..(KA's) i f I l ANSWER '5.07 (1.00) I k c ;
[
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Us__IUEQbY_QE_UUCLEeB_EQWEB_ELOUI_QEEB9IICU2 Pego 23
. ELVIDS400D_IUEBdQDYU001GS REFERENCE YAEC 200909 EO 909.4 KA1 3.8/3.9 2.9/3.1 192008K106 192002K114 ..iKA's) * ANSWER 5.08 (1.50) ,
1. a 2. b 3. a CO.5 each3 REFERFGCE YAEC 200911 EO 911.2 l KA! 3.1/3.1 , 19:004K106 ..(KA's) , ANSWER 5.09 (2.00) a. 3 l b. 4 [1.0 each] l l l REFERENCE l YAEC 200908 EO 908.4,.5 KA1 3.8/3.8 190000K104 ..(KA's) ANSWER 5.1( (1.00) c REFERENCE YAEC 200908 EO 908.3 KA1 3.3/3.4 . 192008K110 ..(KA's)
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Dz__IUEQBY_QE_UUGLEeB_EQWEB_ELOUI_QEsBeI1QU2 Pcgo 24
. ELUIDS20SD IUEBDQDYued1Ga ANSWER 5.11 (1.00)
b REFERENCE YAEC 200911 EO 911.4 KA! 3.8/3.9 2.9/2.9 19:004K113 192002K114 ..(KA's) ANSWER 5.12 (1.00) l 1. To insure minimum shutdown margin is maintained. (MSLB) 2. Minimi:e tt.e reactivity consequences of an ejected red OR potesitial effects of red misalignment on associated accident analysis are limited
,
3. Maintain acceptable axial flux distribution. (power distribution limits)
> (LOCA). Cany 2, 0.5 each3 REFERENCE I
i YAEC 200910 EO 910.5 KAI 3.4/3.9 19:005K115 ..(VA's) ANSWER 5.43 (1.00) " a. Increase ! b. Decrease Co.5 each3
.
CEFERENCE YAEC 200506 EO 506.5 .7 GP HTFF p.328 KAI 2.9/3.0 193006K105 ..(KA's)
(***** CATEGORY 5 CONT!NUCD UN NEXT PAGE ****+)
- . - _ _ _ _ _ _ _ _ _ . , * Pcgo 25 Ut__IOEQBY_DE_UUGLE0B_PQWEB.ELGUI_DEESGI19di . ELUIDaa00D IUE6 BOD!b901G2 ANSWER 5.14 (1.00)
a. FALSE b. TRUE Co.5 each] REFERENCE YAEC 200506 EO 506.7 ' GP HT&FF. p 155,320 and Subcooled Liquid Densi ty Tables.
KA! 2.5/2.6 2.4/2.5 193004K111 193005K103 ..(KA*r) ANSWER 5.15 (2.50) a. From the Stm Tables, Tsat for 2200 psia = 649.5 F SCM= Tsat-Th= 649.5-580= 69.5 F (+/-1 F) Co.5 ea3 (1.0) b. drerease Co.253 Th increasesAas unit delta T increases with power (0.53 (0.75) c. 1 (all MCf to.253 deYrelstres Intrence) Core Unita T during natural circulation cooldown will approach l full load delta T. (Thot is greater than in the other 2 cases.)CO.53 I
(0.75)
I t REFERE'?E LP 20^*02 "Characteristics of Water and Steam" EO 502.5,6 GP HTFF p 3561 Steam Tables KA! 3.6/3.0 193000K115 ..(KA's) l ANSWER 5.16 (1.00) a. Saturated.
b. Superheated.
(+++++ CATEGORY 5 CONTINUED ON NEXT FAGE +++++) I
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _.
. D&_.IdEQ6f_QE_UUGLE88_EQWEB ELGUI.QEE60I1QU2 Pego 26
. ELW103400D.IdE6dQDYU0dIGU
,
REFERENCE LP 200302 "Characteristics of Water and Steam" EO 502.7 Steam Tahden, Mollier diagram GP HTFF p 03,94.
KAI _.8/2.0 i 193004K115 ..ts,^'s) i
,
i ANSWER 5.17 (1.00) , t In the secondary system there is a phase change CO.53. A phase enange requires a large delta h. With the larger delta h of the secondary, the same heat can be transferred with a lower flow rate CO.53.
) REFERENCE l YAEC 200507 EO 507.4(6.c) [ GP HTFF, Section 3.2 l $ KA! 2.8/3.0 I q 193008K101 ..(KA's) i ) ANSWER 5.10 (1.50) ! . I 1. Density difference (or DELTA T) CO.333 created by heat addition by ; ! the heat source C0.333 and heat removal by the heat sink Co.333. ; 2. The heat sink must be eleva^.ed physically above the heat < ! scurce. Co.53 i REFERENCE YAEC 200510 EO 510.1,.2 KA! 3.9/4.2 193008K121 ..(KA's) ) ,
(***** CATEGORY 5 CONT 1NUF.D ON NEXT PAGE +++*+)
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5t__INE98Y_DE_UUGLE68_EQWEB_EL66I_QEE68I196, Pega 27
. ELUID320ND_ISEBdQDYNedIGS ANSWER 5.19 (2.00)
a. Turbine power remains constant (or decreases slightly due to decreased steam pressere). [0.43 b. Tavg - Loop i increases Co.23 Final value will be equal to core outlet temperature (Th)
(524 F)CO.23 c. Tavg - Loop 4 decreases CO.23 Final va14e => (total reactor power has not changed; however, the power that each of the non-affected loops must transfer to the S/Gs has increased by 1/3 to compensate for #1 NRV going shut.)
0=mCp(Delta T) Since Q increased by 1/3, Delta T is the ona. factor which can increase.
Initial Delta T was given as 18 F, and must increase by 1/3
-> new Delta T = 24 F Final Tavg = Th - (Delta T)/2 = 512 F CO.23 d. Pstm - Loop 1 increasca Co.23 Final value is saturation pressure for Loop i Tas g (= 826 psig) C0.23 e. Pstm - Loop 4 decreases CO.23 ,
Final value - as with part c above, the appropriate Delta T must increase by 1/3. Q=UA(Tavg - Tstm) initial Delta T = 515 F - 496.5 F = 18.5 F
'3aturation temp for 645 psig = 496.5 F)
Final Tstm = Tavg - Delta T = 512 F - 18.5(4/3) F
= 487.3 F Final Pstm = 591 2 psig (Saturation for Tutm) CO.23 REFERENCE STM, Chpt 2, pg- 1-2 Westinghouse "Thermal-Hydraulic Principles" Chpt 5, pg 3 RO/SRO LP #37 "Secondary Plant Heat Balance" E.O.200513 KAI 4.4/4.6 3.8/4.0 3.2/3.4 3.2/3.6 035010K601 035010A203 035010K109 035010K301 ..(KA's)
(***** END OF CATEGORY 5 *****)
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- Pcgo 28 6___EL8dI_SYSIEUS_RE51002_GOUIB962.86D_INSIBudgNIBIlQU
.
ANSWER 6.01 /.1. 50 ) a. The pressure input is used to compensate the level indication for density differences within the pressurizer. C1.03 NOTE: Pressurizer pressure is used to compensate both the water the pressurizer.
and steamdrip p{ortions of
$fetol wi$
b. The charging pudps willfgo to minimum).cpredf-CO.5J REFERENCE STM 14-25; 15-28 EO 14C KAI 3.7/4.0 3.3/3.7 3.8/3.9 011000A203 011000K406 011000K103 ..(KA's) ANSWER 6.02 (1.50) a. WL-1 Manually SIAS-A Manually SIAS A-1 Electrically CO.5 sach] REFERENCE STM 19-71 thru 19-73 EO 16C, 16D KAI 3.9/4.3 913000K401 ..tKA's) ANSWER 6.03 (2.00)
(sn IR-3 o r - 4)N a. High SUR of greater than 1.5 DPM cr eith-- charm:1.CO.BJ b. (Once the high SUR signal u9 cleared), the rod stop is reset by depressing the reset pushbutton on the MCD.CO.53 c. 1. Rod Operations Selector switch to the all in position.
2. High Tave while in automatic.
3. Manual Rod Selector Switch to the IN position with the Rod Operations Selector Switch in MANUAL. f4.27 ::ch2 V. $ cram EIhree, a b 0 33 etc k (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
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6t__ELONI_SYSIEdS_QES1 Qui _QQUIBQLi_8ND_IN3IBWdEUIGIION Pego 29 c.
. s REFERENCE STM 34-13, -15 E0 11C, 11F
:
KAI 3.7/3.8
.
001000K407 ..(KA's) ANSWER 6.04 (1.50) a. Pressurizer Wide Range Pressure.
Main Coolant System LTOP Pressure.
Core exit thermocouples.
Reactor Head Thermocouple. Co.25 each3 b. The red dot'means that the unit is in test. [0.53 RE:#ERENCE STM 14-31,-32 E0 12C KAI 4.3/4.6 3.9/3.4 002000A104 000074A113 ..(KA's)
:
ANSWER 6.05 (1.50's a. Restart with a (10 sec.) time dulay.
i b. Restart immediately.
' c. Will not start. Co.5 each3 l l
'
RE .tENCE STM 19-20, 15-1' E0 14C, 16C ! f I e KAT 3.5/3.9 r
- 000056K301 ..(KA's) l
. I
i
l i (***** CATEGORY 6 CONTINUED ON NEXT PAGE *++**) l
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*f - . 16x__EL8NI_3YSIgd5_Qgg1QN2 QQUIBQL2_6NQ_1N$IBydgNI8IlQU' Pcgo 30- .
ANSWER 6.06 (1.50) a. Main Coolant System over-pressure.to.53 b. Uncontrolled rod withdrawal.
Loss of turbine load. Co.5 each] REFERENCE STM 33-19 EO 21A, 21B KAI 3.9/4.3 p v8 f f 012000K402 ..(KA's)
"
ANSWER 6.07 (2.00) 'I a. The purpose of the Non-Return Valve Scram is to limit.the cooldown CO.53 of the MCS following a main steam line break accident. [0.53 b. The trip is reset by holding the trip switch in the RESET position
.
Co.53 and turning the block switch to BLOCK. CO.53 REFERENCE ' F.TM 33-14, -17 EO 2iA, 21B
'
i KAI 3.9/4.3 3.3/3.6 012000K604 012000K402 ..(KA's) .4 - _, ANSWER 6.08 (2.00) Loss of IA causes I/P to indicate a high level (3 psig = 135") Co.403 High level indication causes chg pumps to trip (63X-HL relay) CO.403 Bleed continues (620 gpm) causing Pzr level to decrease Co.403 Decreasing MC pressure causes Rx trip on low pressure Co.403 Decreasing MC pressure causes SI on low pressure Co.403 (***** CATEGORY 6 CONTINUCD ON NEXT PAGE *****) f
_ .__;_
* . * 6t__E48NI_EYSIEdE_DESIGNi_GQUIBQL4_8ND_INSI6WdEUIGI196 Pags 31 ..
REFERENCE Systems Training Manual, Chpt 15, pgs 7-12, 32-35, & Fig 15-15,
.& Study Questions 21, 23 -
Lesson Plan 004: CVCS.' EO 22B,C KAI~3.2/3.7/4.1 004020K302 004000A207 OOOO65A208 ..(KA's) ANSWER 6.09 (3.00) a. Low pres with-level >= norual Air compressor start C0.53 Low pres with level < normal Makeup pump starts Co.53 b. Solenoid operated valve (SOV-700) Co.53 Safety valve back-up (SV-200) Co.53 c. Engine overspeed (2050 rpm) Co.53 Take control switch to OFF Co.53 REFERENCE System Training Manual, Chpt 8, pgs 8, 10-12, Fi gs 8-2, 8- 6 & 3tudy Questions 15, 16, & 17 NEO r . KAf 3.4/3.1 086000A201 006000K402 ..(KA's) I ANFKER 6.10 (2.50) a. (1) NO Co.2S3 (2) YES Co.253 Tank outlet valve (VD-LCV-408) goes shut Co.25.1 (3) YES CO.253 Vent SOV shuts Co.253 (4) NO Co.253 I b. (1) YES CO.253 (2) YES Co.253 '
(3) YES CO.253
(4) M ES CO.253
! l l
(***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
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6t__E68dI_SYSIEdS_ DES 19U2_L'QUIBQL2_8UD_INSIBUdEUIGIl0U Pegs 32 ;
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REFERENCE l) lh STM Chpt 35, pfgO-13f6,17,23,24 and 25 RO LP 1073: "Process HMS" E0 1073.2,3 KAI 4.3 073000K401 ..(KA's) ANSWER 6.11 (3.00) a.
MCS OR ,, a pres ) 1650 psi' aa rathh*n (safety injection) G.,[OS ley ne *4' %", al o.53 E[f ["U"N; b. Manual CO.43 (6)
.VC pressure CO.43 qmestrr t'-a ne T_ r ! trg3 psig CO.23.
c. (1) Valve will be shut CO.353 Valve will remain shut CO.43 (2) Valve will be open- CO.353 Valve will remain open CO.43 REFERENCE
'M cc T s, Table 3. 3 - 3 STM Chpt 25, p 23 & 24.
RO LP 1103 "Vapor Centainer Systee,"- EO 44C,0 KAI 3.8/3.3/4.2/4.1 103000A101 103000A301 103000A401 103000K109 . . (!(A 's ) ANSWER 6.12 (3.00) a. At 500 psig increasing, Co.253 both valves receive an openin(, signal C'O.253 PR-50V-90 will open CO.253 PR-MOV-512 should open if closed Co.253 At 470 psig decreasing CO.253 only PR-SOV-90 receives a closing signal Co.253 PR-SOV-90 should close CO.253 b. PR-MOV-512 not full open, with Co.253 MCS pressure < 450 psig (LTOP armed) Co.253 MCS pressure < 450 psig, with CO.253 LTOP not armed CO.253 Loss of power to the LTOP pressure channel CO.253 (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
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6___ELGUI_SYSIEUS_DE91984_G9 BIB 962_8U9_103I890EUI8I193 . Pegu 33 . REFERENCE STM Chpt 14, p 30 & 31, & Question #16 RO LP #010: "Pressure Control & Relief System" EO 20 C,D KAI 3.7/4.1/3.8 010000A403 010000K403 010000A107 ..(KA's) _
. . (***** END OF CATEGORY 6 ***++)
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Z2__BBQGEQUBEE_:_NQBd862_0ENdBd862_EdEBQENGr
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Pegol34
, OND_B001QLQQ1GOL_GQUIBQL
,
f
. ANSWER 7.01. (3.00)
a. Recovery Manager TSC Coordinator Emergency Director (Shif t Supervisor) Co.5 each3
:
b. Whole Body Total Stable -12.5 Rem 50 Rem Severe , 25 Rem 100 Rem Extreme 100 Rem 300 Rem C6 required, 0.25 each3 i REFERENCE
OP-3324, Appendix B-3 RO LP 2004 "Exposure Control" LP 3001 "Emergency Plan and Emergency Director" EO 3001.10 KAI 4.4/3.4
'
194001K103 194001A116 ..(KA's) T i ANSWER 7.02 (2.50)
,- 1. SG Lev - ensure NC flow is not interrrupted CO.33
- , '2. Pzr level - 60" is a buf f er against level oscillations due to l
inexact control of SG press via steam camps CO.53
.
(-As found minimizes changes to primary pressure)
' 3. MC Temp - ensure NLT limits are not violated Co.253 ,
'
l p,g,,provido f or adequate subcociing CO.253 ' 4. SG 4ner - < 900 psig to keep secondary saf nties from openingCO.253 5. SR - any incenase is indicative of a lost, od SDF, or . an increase in temp in ex vessel downcomer CO.53 .L
,
'
REFERENCE OP-3018, pg 3, Att A pg 2 RO/SRO LP #27 "Natural Circulation" E O. 200503 #4 RO/SRO LP 3004 "Emergency Procedures" E.O. 304.'
'
KAI 4.5/4.4 000068A211 000069K318 ..(KA's)
,
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I i t i t r
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-Zr__ESQGEDWBEE :_NQBt!8La_8aNQBt!8Li_EMEBQENGY
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Pago 35
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GND 88Q1QLQQ1GOL_GQNIBQL i i-
!
!
ANSWER- 7.03 (2.00)
{
4: 1. Return radioactive components to core or spent fuel pit and/or ' suspend core alterations.
2. Place fuel chute carriage above lower lock valve and close lower lock i valve.
3. Visibly check the Shield Tank Cavity fuel chute clapper valve closed.
~
4. Notify the Control Room and plant emergency director (3S).
C4 required, 0.5 each3 ' REFERENUt O P - 3 1 .'7 , pg 13 SRO _P "Refueling Operations, E.O. 300148, 304.1
'
KAt 1.5 000036K303 ..(KA's) .
!
4- ANSWER 7.04 (3.50) : a. -UnexpectdkriseinoneS/Gwithfeedwaterflowstoppedorreduced.
-A decrease in feedwater flow prior to reacter trip.
~High radiation from steamline monitor or handheld survey instrument. ! , Co.5 each] . i b. The leakrate greater than the capacity of one charging pump. CO.53 - c. To minimize heat transfer to the faulted steam generator. Co.5] I l d.
-MCSpressuredrps(below1700))
-PZR 1evel drops below 50 inches I
,
-MCS subcooling drops (below 40 degrees-F) CC.33 ea:h3 f
- REFERENCE
-
' YAEC OP-3107 and Attacment A EO 304.1 RO LP "Emergency Pracedures" #RO-1999-005-1 , KAI 4.2/4.5/4.6/4.3 000038G011 000039A203 000038K306 000038K308 ..(KA's) l ,
(***** CATEGORY 7 CONTINUED ON NEXT PAGE *****) . . . . _... ._ - _- :., -
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sit __EBQGEQUBEH_ _UQBd8L2_8EUQBd8Li_EdEBGENGY Page 36
. GUQ_B8Q1QLQQ1G86_GQUIBQL ANSWER- .7.05 (3.00)
a. 1. Uncontrolled plant cooldown.
2. Failure of two or more control rods to drop after a scram.
3. Unexplained or uncontrolled reactivity insertion (also considered an ATWS event) [0.5 each3 b. 1. Scram the reactor.
2. Lineup charging pump discharge to normal charging line.
3. Open boric acid mix tank valve,(CS-MOV-529) , 4. Start all charging pumps at maximum flow.
5. Close the following valves to the charging pump suction-Low press surge tank (CH-MOV 521)
-Safety injection tank (CS-MOV 540) -Purification ion excnangers PU-FICV-202) -Primary water storage tank (DW-MOV-655)
6. Establish sufficient bleed flow to prevent PZR level from increasing to the charging pump auto trip twtpoint. [ 7. Initiate OP-3300, "Classification of Emergencies".
l
- C5 required, 0.3 each3 REFERENCE
YAEC OP-3105 EO 1009.4 RO/SRO LP 3004 "Emergency Procedures" E.O. 304.1
,
KAI 4.4/4.4 ' 000024K302 000024K301 ..(KA's) ,
;
i ANSWER 7.06 (3.00) a. MCS pressure.
PZR heaters.
SI pumps and valve positions (as prevention or mitigation of a LTOP event) Co.5 each]
.
b. 450 psig CO.753 c. To prevent control rod housing seal weld deformation. Co.753 (***** CATEGORY 7 CONTINUED ON NEXT PAGE ***++)
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* Zs__EBDGEDUBE2_:_UQBdeL4_02UQBdeb2_EUEB9EUGX Paga'37 . GUD_B091QLQO1GOL_GQUIB96 REFERENCE YAEC OP-2100, p 4-6 EO 1056.4,.6 LP 3002 "Operating Procedures General Plant Operations" EO 3002.1 KAI 3.9 0020SG0010 ..(KA's) (2. 00)
ANSWER 7.07 ' 2 . " '? ) a. -Improper rod motion-Improper load change-Reactivity addition by dilution-Reactivity addition by Xenon buring out-Instrument malfunction C4 required, 0.25 each3 b. Check Tc and Th in all loops CO.53 Check reactor power and load CO.53 c. A dedicated operator shall be at the rod control section of the MCB. C0.53 REFERENCE C !C 6 . YAEC OP-3535 EO 3Q4.1 KAI 4.0/3.8 0010SGK001 001010A101 ..(KA's)
ANSWER 7.09 (3.50) a. The BFP trips due to low suction pressure (DF-CV-405 fails open) CO.53, resulting in a S/G low level trip CO.53 b. -plant shutdown-supplying feedwater (to assure adequate decay heat removal)
-placing CC return header on emergency supply (prevent MCP damage)
-performace of required valving operations to maintain main cond. vacuum (for steam dump to avoid lifting S/G SV'S. CO.5 each3 c. To avoid lifting the PZR solenoid relief valve. CO.53
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. BND_B8Q1QLQQ1G86_GQUIBQL REFERENCE l
YAEC OP-3002 p 1,2. EO 304.1 KAI 3.6/3.0 0780SGK013 078000K303 ..(KA's) ANSWER 7.09 (2.00) a. Loop Delta T (less 6han f ull power Delta T) Loop Tc' (constant > accreasing)
(following Tsa:.for SG conditions)
Loop Th (stable not ir .reasing) CET's (No abnormal di es ence between CET's and loop Th)CO.25 each3 b. Prevent void formation Co.53 under the reactor head CO.53.
REFERENCE OP-3054, p 2,3. EO 304.1 RO/SRO LP "Shutdown Cooling" EO 200507
$
KAI 4.2/4.4 000074K311 000074K301 ..(KA's)
;
E i
;
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, ' ' ' , .y, l= , , - -,.,n., = . , . , . _ , , , , - . . - , . .- ,. - - - , , , , . -
- . - _ . _ _ _ _ _ _ . _ - . . _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ ~ . . . -* Page 39 St__8Dd1NISIB8IIME_ESQGEDWBES2_GQND1I1QUS2 . 8ND_L161I8I1QNS ANSWER 8.01 (3.00)
a. Interval requirement not exceeded CO.53. Eight days does not exceed 1.25 times the specified interval C1.03.
' b. Interval requirement exceeded CO.53. The last'3 consecutive intervals exceed 3.25 times the specified interval C1.03.
REFERENCE' YAEC TS, p. 3/4 0-2 -
.LP 3006 "TS" EO 501325 KAI 3.9 0640SG0005 ..(KA's)
.
k ANSWER 8.02 (3.00) ,
'
a. Will not jeopardize safety of personnel or equipment Does not violate TS (license, codes, regulations, or orders) Does not effect safe operation of plant C3 items 9 0.50 each) . b. Licensed RO/SRO Co.503 ' c. Licensed RO/SRO verify removal of tags, or Performance of a Functional test C2 items G 0.50 each3 REFERENCE I AP-0017, pg 2, & APF-001 7.1, side 1 i RO LP "Administrative Controls" E.O. 201208 194001K101 194001K102 ..(KA's) ANSWER 8.03 (1.30) l 1. The intent of the procedure is not altered CO.53.
2. The change is approved by two members of the plant management staff, at least one holds a SRO license CO.53
- 3. The change is documented, reviewed by PORC and approved within 14 days
! of implementation by the Plant Manager Co.53.
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REFERENCE
-
E YAEC TS, p 6-14. . , LP 3005 "Administrative Procedures" EO-3005.1 : KAI 3.4/3.9 194001A102 194001A101 ..(KA's)' I e : I ANSWER 8.04 (2.00) ; a. Hot Standby and pressure in limit within 1 hr. , !
b. Pressure within limit in 5 min. C1.0 each3 l REFERENCE j
; '
YAEC TG, 2.1.2.
' LP 3006 "TS" EO 501302
!
KAI 4.1
- 0020SG0005 ..(KA's)
! 1 i ANSWER 8.05 (3.50) t i j a. He has reviewed the RWP for completeness , He has reviewed for any conditions which may adversely affect the plant i i CO.5 each3 i ' b. Hi rad area ' ! VC
- Airborne Radioactivity areas Areas posted with "RWP Required" Fuel Handling Ops .
Maint/insp of equip with smearable levels > 10,000dpm/100sqcm ! When RP Mgmt deems necessary Cany 5 0 0.5 each3 { t I i l a REFERENCE
.
[;
j AP-0806, pgs 2, 4 b RO LP 2004 "Practical Applications of kP Practices" E.O. 200413
[
194001K103 ..(KA's)
!
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* az__0Dd1012IBOI1YE_EBQGEDWEES2_GQUD1I1963, Paga 41
. 00D 6151I0I1965
:
' ANSWER 8.06 (1.50) l.0 75.7 1 To prevent the release of activity Obdtr in event o'r the saturation pressure of the RCS is below the lift
[0.75]hi DDWR3
;;re of the nce e
- atmospheric steam relief valveshf.52."- [
i REFERENCE I i
. YAEC TS, B 3/4.4.7 E0 1056.5 f
' KAI 3.8 * 0020SG0006 ..(KA's) ! i
- i ANSWER 8.07 (2.50)
a. Identified 1 b. Identified
- c. Pressure boundary P
- d. Unidentified
, e. Identified Co.5 each] , REFERENCE YAEC TS, 3.4.5.2 E01056.5 i KAI 4.1 0020SG0005 ..(KA's) ANSWER 8.00 (2.50) a. 3.5.1.b.
b. 3.5.1.a.
c. 3.5.1.c.
d. 3.5.1.a. , e. none. Co.5 each3 REFERENCE YAEC TS 3.5.1 E0 1006.5 KA! 4.2 0060SG0005 ..(KA's)
(****a CATEGORY 8 CONTINUED ON NEXT PAGE ***++)
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. . * 'Hi__0Dd1N15IBBI1YE_BBQGEDUBES2_GQUD1Il0051 Pcga242 4 00D_L1d1I0I1905 ANSWER 8.09 (2.00)
a. Obtain a relief CO.53 within two hours Co.53 b. No Co.53 may not intentionally leave a position vacant CO.53 REFERENCE Yankee TS, p 6-5 LP 3006 "Technical Specifications" E.O. 501325 KAI 3.4 194091A103 ..(KA's) ANSWER 8.10 (3.50)
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a. Supervisory Control Room Operator.CO.533 Cd.2 s] b. (01and10) they plant radio ppge system. C0."2A dtHI Initiate (ou a p) gage on use of commenial lek fhone [0.25.1.
c. The N depressing 210)CO.53, backup - commercial telephone (800-24 -2249) and ask for the State Police Dispatcher CO.53 wii:hin 15 minutes of the class,1fication Co.53.
. d. AO CO.53 e. No Co.53 REFERENCE YA EC O P'33 YY > Ag* E.
'fkc oP-3sto, Ag.2.
YAEC OP-3315 ahd Attachments LP 3001 "Emergency Plan and Emergency Director" EO 3001.4,.3,.8 E-Pien .%% 7.0, Foy. ?:I KAI 4.4 194001A116 ..(KA's)
(***** END OF CATEGORY 0 ***** (********** END UF EXAMINATION ***s**#***) .
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* TEST CROSS REFERENCE Pcgo 1
. QUESIl0S _YeLUE BEEEBEUGE_ 5.01 1.00 ZZZ0000085 5.02 1.00 ZZZ0000006 5.03 1.00 ZZZ0000087 5.04 1.00 ZZZ0000088 5.C5 1.50 ZZZ0000089 5.06 2.00 ZZZ0000090 5.07 1.00 ZZZ0000091 5.08 1.50 ZZZ0000092 5.09 2.00 ZZZOOOOO93 5.10 1.00 ZZZ0000094 5.11 1.00 ZZZ0000095 5.12 1.00 ZZZ0000096 5.13 1.00 ZZZ0000097 5.14 1.00 ZZZOOOOO98 5.15 2.50 ZZZ0000099 5.16 1.00 ZZZOOOO100 5.17 1.00 ZZZ0000101 5.18 1.50 2Z20000102 5.19 2.00 ZZZ0000103 ______ 25.00 6.01 1.50 ZZZ0000104 6.02 1.50 ZZZ0000105 6.03 2.00 ZZZ0000106 6.04 1.50 ZZZ0000107 6.05 1.50 ZZZ0000108 6.06 1.50 IZZ0000109 6.07 2.00 ZZZ0000110 6.08 2.00 ZZZ0000111 6.09 3.00 ZZ20000112 6.10 2.50 ZZZ0000113 6.11 3.00 Z220000114 6.12 3.00 ZZZ0000115 ______ 25.00 7.01 3.00 ZZZ0000116 7.02 2.50 ZZZ0000117 7.03 2.00 ZZZ0000118 7.04 3.50 ZZZ0000119 7.05 3.00 ZZZ0000120 7.06 3.00 ZZZ0000121 7.07 2.50 ZZZ0000122 7.08 3.50 ZZZ0000123 , 7.09 2.00 ZZZ0000124 ______ 25.00 8.01 3.00 ZZZ0000125 0.02 3.00 ZZZ0000126 0.03 1.50 2ZZ0000127 8.04 2.00 22Z0000128 8.05 3.50 ZZZ0000129 0.06 1.50 ZZZ0000130
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* TEST CROSS REFERENCE Pcgo 2 l
995HI19N _YeLUE BEEEBEUGE_ G.07 2.50 ZZZ0000131 8.08 2.50 ZZZ0000132 8.09 2.00 ZZZ0000133 8.10 3.50 22Z0000134 ______ 25.00 _ ____ ____ _ 100.0 DOCKET NO 29
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, ATTACHMENT / /
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jf4.5 EMttGENCY CORE C00tfMG $YSTEMS (ECCS) _ L ACCUMULATOR
.
I LIMITINGCON0!T!0NFOROPERATION
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* 3.5.1 The low pressure safety in,1ection accumulater shall be C?:43LE , with: ,
a.. Isolatten valves $!-MOV-1 and $1-TV-608 open.
b. A minimum useable contained berated water volume of 700 cub'ic l feet of borated water, equivalent to an indicated level of 261" in the accumulator. . c. A minimum beron concentration of 2200 ppm. . d. An accumulator nitrogen sever-pressure of less than 15 psig.
l (' .
" : e. The nitrogen supply system with three supply pressure regulating I .
valves set at 4731 10 psig and at least:
' ; 1. Sixtgen 44 cubic foot nitrogen bottles t 1330 psig, or ( , -
2. Sever.:een 48 cubic foot nitrogen bottles 3,1340 psig, or 3. Eighteen 48 cubic foot nitrogen bottles 3.1234 psig, f. - Two CPER/3LE low level venting system, and 3 Timers set to operate between ,11.8510.23 seconds. - l l
. ; APPLICABILITY: MODES 1, 2. 3* 4* and l'.-
f AE19.N., .
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I i s. With the accumulator inoperable, except as a result of a , t alesed ivelation valve er as a result of one inoperable l - pressure regulating valve er one inoperable low level venting system, restore the inoperable accumula'ter to OptRA8Lt status
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within 15 minutes or be in at least NOT SHUTDOW with main coolen' pressure < 1000 psig within the ment 8 hours.
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. b. With the occumulater inoperable due to ene isolation valve ; being closed either immediately open the isolation valve or -
be. in at'least NOT STANDBY within one hour and be in at least C: j - NOT SHUT 00W with main coolant pressure < 1000 psig within the mest 8 hour,s.
f * nein coolant pressure 3,1000 psig.
} , YANUE ROK 3/46-1 Amendgent M. H, 54 1 .- .
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, l DER 4tNCY CORE COOLING SYSTEMS j i .
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J.!MIT!NG CONDITION FOR OPERATION (Continued) .
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c. With one inoperable supply pressure regulating valve er with one i
, inoperable low level wnting system, reston the inoperable : ' .
regulating valve or venting system to 0PERA8LE status within ' i 8 hours or be in at least NDT STAN0tY within one hour and be in - at least MDT SNUTDOWN with main coolant pressure < 1000 psig
, within the following 8 hours.
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SURYt!LLANCE REQUIREMENTS
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i 4.5.1 The accumulator shall be demonstrated OPERA 8LE:
,s. At least once per 12 hours by:
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' . . 1. Verifying the cantained berated water volume accumulator altrogencour-passure and the supply pressur,e regulator
,; .
discharge pressure, and
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2. Verifying that accustator isolation valves 3! MOV-1 and .
. 31-TV-604 are open. ' *
i . h, At least once per 31 days and within 4 hours after each sotstion I w1ume incessie of * 15 by verifying the boron concentration of
,
the accumulator seliitton, i
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, ) c. At least once per 31 days by: l 1. Verifying the nitrogen supply bottle pressures, l
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2. Verifying the actuation of each accumulator time delay reley. i s The acceptable rundown time is 11.85 f,0.13 seconds.
, l g , . . i
. ; d. At least once per 18 months during shutdown by: '
1. Verifying CPERA8!Lm of the nitrogen supply systesi by
- observing operatisc of each regulating valw.
l 2 Verifying CPERA8!LTTY of each low len1 venting system
e
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when the lowl switch colum water lowl is lowereds at . I , the same time, verify closure of 5!.MDY,1 and 5!-TY.408 1 [
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a
g t Verify that 3!.TV.'604 S! TV.605 and $!-TV.404 open whea RS 30Y 48 is energized and again then N5 50Y-47 is energized.
), ' YAMXII-ROWE 3/4 5-2 Amendment No. H. (( 54
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1-EQUATION SHIET
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_ I = as
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y = s/t v = as 2 Cycle efficiency = _ Net Work (out) - s = v,c + lsac
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E = aC .
, , g,g , ,g)f, l Kg = l yev t y A = AN A = A,e g,y ,, ,,
PE = msh w = e/t A = in 2/tq = 0.693/eq W = VAP' AE = 9314e . tq(eff) = (t,)(ts) -
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Q=[ SCATp , I.Ieg *E8
,k=UAAT g=g *VX
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* Pvr = V g' [s" , I=I g to**M
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y=y tq 5UR(tl. Tvt = 1.3/u y=y H7L 6 0.693/u o .t/7 SUR = 26.06/7 ~ T = 1.44 DT 3CA " 8/(1 ~ K.gg) fa SUR = 26 g
*p,s) CR, = S/(1 - K,ggx)
II eff)1 " b (I
~ ~~
T " '(t*/o ) + {(gi *o)/1,g,,) eff)'2 t ,= t*/ ( , . p
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M = 1/(1 - K,gg) - Cat /can T * II ~ ')! A sif # M = 0 - K,gg)O/ (l * Xeff)1 8 " (5eff'IIIIeff * #sifMeff SDM = (1 - K,gg)/K,gg p= [t*/TK,'gg .] + [I/(1 + A,gg?)] t' = 1 x 10" seconds
,
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y = I67/(3 x 1010) 1,gg4 0.1 seconds t = Ne i
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Idgg=Id22 UATTP, PARAMETERS Id =Id2 g 1 sal. = 8.345 lba R/hr = (0.5 ct)/d 2 g,,,,,,) , 1 sal. = 3.78 liters R/hr = 6 CI/d24g,,c) , 1 fc3 = 7.48 gal. _HTsc21.t.Mit005 coNytRSIONS . I Density = 62.4 lbs/ft 3 1 Curia = 3.7 x 1010dps Density = 1 ss/cm i kg = 2.21 1ha j ' Heat of vag orization = 970 teu/lbre 1 hp = 2.54 1 103 BtV/hr Heat of fusien = 144 Stu/lbra 0 1 N = 3.41 x LQ Btu /hr , 1 Ata = 14.7 psi = 29.9 in. I's. 1 Blu = 778 f t-lbf 1 ft. H 2O = 0.4333 lbf/in !' inch = 2.54 cm j r = 9/ 'c + 32
*C = 3/9 (*r . m /
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. f ATTACHMENT 3 o Telephono (61P) 8V2 8100 TCx P10 380-F619 YANKEE ATOMIC ELECTRlC COMPANY
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y % -, 1671 Worcester Road, Framit.gham. Massacnusetts 01701 September 20, 1988 FYR-88-128 TR-88-320.5.2 Regional Administrator Region I U. S. Nuclear Regulatory Comission 475 Allendale Road King of Prussia, PA 19406
Dear Sir:
On September 13, 1988, Reactor Operator (RO) and Senior Reactor O p rator (SRO) written examinations were administered at the Yankee Nuclear Power Station in Rowe. During a review of the exam by facility personnel, t>enty-two (22) questions were identified as needing additional input or change. It is requested that the coments on these questions be given due consideration (or inclusion prior to the grading process. The twenty-two (22) questions, attached, are Nes 1.05 (5.05), 1.06 (5.06), 2.01, 2.05, 2.08, 2.09, 2.12, 3.01, 3.02, 3.03 (6.01), 3.04, 3.07, (6.03), 3.10 (6.07), 4.01 (7.04), 4.04 ( 7.07), 4.08, 4.11, 4.12, 6.10, 6.11, S.08, and 8.10.
If additional information is needed, please contact Russ Cla-k, Training Manager. Thank you for your cooperation.
/ Very yours,
& dh Bruce L. Dr ridge Vice President Manager of Operations BLD/16.460 Attachments cc: P. Bissett, NRC '
F. Jagger EC&G N. Jensen EG&G N. St.Laurent, YNPS T. K. Henderson, YNPS C. R. Clark, YNPS G. Papanic YAEC
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o A. Question 1.05(1.50), 5.05(1.50) B. Comments: Part b. This question could be answered correctly as "Increasing" or "Docreasing" depending on the power ramp rate assumed in attaining 50% power.
If a power increase rato equivalent to that specified in the root of the question (5% per hour) is assumed, then the Xenon trend would be
"Increasing". If a step increase to 50% is assumed, then the Xenon trend is "Docreasing".
Part c. It is not clear from the working of the question as a whole whether the 3 parts are to be considered separately or in sequence. This confusion is compounded by the acquence of a, b and c, as they do support this sequentir.1 trend (reactor trip, restart, and maintenance or power.
operation). If the question is to be answered sequentially, then the answer for part c is dependent upon the ramp rate to be assumed in part b. As stated in review of part b, above, a slow ramp rate would find Xenon "Increasing" upon attaining 50% power, while the prompt jump to 50% would result in Xenon burnout predominating even throughout the first hour of operation at this power level.
C. Ref. N/A _ _- A. Odestion 1.06(2.00), 5.06(2.00) B. Comments: Part b. This question is ambiguous in its reference to the shutdown margin, SDM, calculation. Review of the YAEC Enabling Objectives referenced in the answer key for this question indicates that a portion of the lesson plan (200913) which addresses Reactivity Balances was misconstrued as portaining to the SDM calculation. In actuality, the basis for the paramotors to be considered for SDM is the YNPS Technical Specifications Surveillance 4.1.1.1.1.1.c, wnich specifics 6, parameters (including rods and boron) to be considered in evaluating SDM. It should also be noted that procedurally (OP-4708) Xenon concentration is assumed to be o for conservatism. Thus, while all answers listed in the answer key reflect paramotors which affect SDM, they do not all represent paramotors used in SDM calculations. Logically, the question asks for those which meet both criteria, but due to the number of responses requested (fivo),
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:o thiclteck cannot be cchisvsd, cnd cdditional examinto rocponcos can be expected. Those parameters which meet both criteria are:
RCS Ave. Temp, Fuel burnup and Samarium C. Ref. (1) YNPS Procedure OP-4708, Rev. 13, Determination of Shutdown Margir (2) YNPS Technical Specifications Surveillance 4.1.1.1.1.1.e (3) YAEC Lesson Plan 200913, Sbutdown Reactivity Considerations e A. Question 2.01(2.50) . B. Comments: Third section of the answer key.
Cross outt- (Emerg Gen 93 - BKR -> Emerg Bus 53 -> BKR) Insert; 15 Station Service Transformer C. Ref. Systens Training Manual, Figurn 37-7, Figure 40-7
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l A. Question 2.05(2.00) B. Comment: Answar as listed is "piggy-backed" pressure, question asks for design and should read a. 187 gpm (+/-10 gpm); 825 psig (+/-50 psig) C. nof. Systems Training Manual, 19-26 I
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A. Question 2.06(2.00) , B. Comment: Should be ablo to uso valvo function or nu aer.
b. BAMT -> outlet valvo (CS-MOV-529) -> cross connect valvo (CS-V-702) -> Charging pump suction-2-
. - _ - _ . _ - .. . . * .. . C. . Same es listed !
n k A. -Question 2.08(2.50)
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B. Comment: . > Question asks for valve between EDG and Day Tank. l b. The valve from the day tank to the diesels is a * fuseable valve that closes in case of a fire. ; C. Ref. Print YM-C-1 I
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A. '
; Question 2.09(2.00)
- B. Comments l Response is incorrect, should be
- t b. True
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C. Ref. OP-3209, Att A, B, C, D and E I i f I ;
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i A. Question 2.12(2.00) r 4 l j B. Comments 5 i > j The queation does not ask for suction chango. The LPSI j pump dischargo is normally directed to the suction of the J HPSI pumps.
I ! The LPSI flow path (CS-MOV-533, CS-MOV-535) is closed,
the HPSI Rocirculation Valves (SI-MOV-48, SI-MOV-49) aro [
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closed.
lI i l No chango should also be acceptable as an answer.
l C. Ref. Systems Training Manual, 19-55, Figuro 19-42 I i
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A. Question 3.01(1.50)
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B. Comment: Answer should read: i Over compensation is more conservative during a reactor startup becausa the power increase as indicated on the , intermediate range would be rapid and result in a High , SUR Scram. The actual peak power reached would be lower than for an undercompensated signal. , Undercompensation keeps the Intermediate Range Inst. from i seeing the actual reactor power for a longer time than an i overcompensated detector. Since the Reactor Protection '
(SUR) from this channel will be blanked out longer in an *
undercompensated detector, the reactor power buildup will go on for a longer period before the detector sees actual power. This will still result in a high SUR Scram, but [ the power peak will be higher. ' ' ' C. Ref. Systems Training Manual, Figurc 31-19 ,
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A. Question 3.02(1.50) B. Comment: ! e , ! a. 1, 2, Although the Nuclear Instrumentation Tech. ! , Manual and I&C personnel state that the Scram ! 3 Bistablos will roset automatically given a largo ,
- onoug'n signe.1 change plant orotating practice has
j bcon to roset the Biotables manually. l
i We accept answer as written although the question wording (must b2) creates confusion.
C. Ref. N/A l
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1 A. Quost.an 3.03(1.00) 6.01(1.50) , B. Comment: W ' b. Answor should also accept: Charging pumps will trip.
< ! Loss of density compensation from pressurc wide range 1 pressure channol (PR-700) will cause indicated pressuro i narrow rango (NR) level to increase (fail high). The i level increase will signal the charging pump controllers i to go to minimum speed.
l In parallcl to the charging pump controllers (or the same ! ) -4-i'
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! * cignal-lins) cro preenure switchno, one of which will trip the charging pumps on a high level signal. When the jl level fails high, it will also t. rip the charging pumps.
l i C. Ref. (1) Systems Training Manual, Figures 15-14 & 15 (2) OP-3111 A.- Question 3.04(2.50) B. Comment: l b. Vapor Container Isolation trip valscs (HV-SOV-1&2) j
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should be deleted from answer.
i These valves are no longer considered Conrainment
; Isolation Valves. . (1)
' C. Ref. YAEC Tech. Spoes. 3.6.2 Table 3.6-1 (2) Systems Training Manual, Figurc 25-16 j (3) Systems Training Manual, Figure 25-15 !
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i i A. Question 3.07(2.50) 6.03(2.00) ! B. Ccmmentt l' ' c. Scram should be added as an acceptable answer.
! ] C. Ref Systems Training Manual, 34-1 ! ! ! ! ! A. Question 3.10(2.00) 6.07(2.00) i B. Ccmmonts ! b. Answer should hava a statomont that all individual ! HRV control switches must be placed in the CLOSE
- position before any trip can be resot.
j C. Ref. (1) Systems Training Manual, 33-17 i
(2) Systems T, raining Manual, 33-18
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_ . _ f e A. Question 4.01(2.50) 7.04(3.50) B. Comment: d. Solicits response for subsequent actions. Our Enabling Objectives require knowledge of subsequent actions using the appropriate material. Although SI i criteria is considered important, it is not a set of l standard critoria, it is different for different ' situations as can be seen from question 4.12. As an acceptable answer, the three parameters, prorsure, level and subcooling should be acceptable for full credit, no setpoints required.
C. Ref. N/A i A. Question 4.04(1.75) 7.07(2.50)
't l B. Comment:
c. The question does not solicit the response as written. Eart B asks for immediate cporator responso and Part C for additional operator response - this lends itself for asking subsequent actions. Rcqucst that any operator response given be acceptabic or Part C De stricken and the points added into Part B.
, 1 C. Acf. N/A _ _ _ _ A. Qucstion 4.08(2.75)
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B. Comment b. 1200 psig is no longer listed in procedure. Roquest that second part of B be stricken from ans.cor key.
C. Ref. OP-3000, Rev. 32
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A. Question 4.11(2.00) , ' i B. Comments b. Toch Spocs requiro ECCS to be operable in modos 1, 2, 3, 4 and 5 if pressure is greator than 1000 psig.
OP-2652, Rev. 30, and OP-2653, Rev. 21, requirc auto at 1800 psig and greater than 490 degree F.
Thorofore, ECCS must be in manual betwoon 1000 psig and 1800 psig. The question asks for modes and thorc 6-
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t i o 10 no correct cncwar. Howaysr, it ic porciblo in mod 3c 3,4,5 if < 1800 psig cnd > 1000 p2ig.
C. Ref. (1) Tech. Specs 3.5.2 (2) OP-2652, Rev. 30, 2653, Rev. 21 t A. Question 4.12(1.50) B. Comments c. Same as 4.01 d C. Ref. N/A A. Question 6.10(2.50)
B. Comment: ' b (4) Answer should bc YES.
, All 'us. :'lannels listed have "f ail safe" relaying.
Will e Latio on loss of power. - C. Ref. (1) Systems Training Manual, 35-15 (2) systems Training Manual, 35-7
i A. Question 6.11(3.00) B. Comment: a. Answer should be changed tor MCS press. 1 (greater than) 1650 psig (SI); or,
< (loss than) 5 psig in VC or manual initiation of SI any responso acceptable for full credit as questien asks for conditier. (singular)
b. Change: VC pressure groa'tcr than or equal to 5 puig to: VC pressure loss than or equal to 5 psig, C. Ref. YAEC Tech Specs 3.3.2, Tabic 3.3-3-7-
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l i O l A. Question 8.08(2.50) B. Comments c. As our heador is common, having different pressures could infer that it is 10 or 8 bottles. No change in answer is requested but answer key should reflect this possibility.
C. Ref. N/A A. Question 8.10(3.50) B. Comment b. Commercial telephone is also used for actification.
c. NAS is commonly referred to as Orungo Phonc.
C. Ref. (1) OP-3344, Rev. 9, Att. B, E-Plan Section 7.0, Fig. 7.1 (2) OP-3320, App 2, Rev. 4
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O ATTACHMENT 4 NRC Response to Facility Comments Question Number: 1.05 (1.50), 5.05 (1.50) HRC Resolution: Comments acknowledged. Since a step increase to 50% at Yankee Rowe is highly undesirable, it is not expected that candidates would view this as a viable option. No change will be made to the answer key.
However, consideratien will be given to any written assumptions a candidate may provide with his answer. The clarity of this question will be improved before loading it into the Examination
- Question Bank (EQB).
, Question Number: 1.06 (2.00), 5.06 (2.00) Agree with comment. Answer key changed to require RCS average temper ture, fuel burnup, and samarium for full credit, each being worth 0.5 point. Any additional candidate answers will be graded on a case basis, with no credit deducted for xenon concentration, ELwer level, and/or power defect, if ! the three required answers are also evident.
, Question Number: 2.01 (2.50) NRC Resolution. Agree. Answer key corrected as recommended.
Question now worth 2.10 points total credit.
" Quertion Number: 2.05 (2.00) l FRC Resolution: Agree. The examiner confused "shutoff" with
"design" in writing the examination. Although this error was corrected and clarified to all candidates l durir.g exam proctoring, it was judged that examinee confusion might still exist. Accoriingly, this question is deleted from the examir.ation.
Question Number: 2,06 (2.00) NRC Resolt. ion: Agree with comment. Valve function (noun name) is acceptable in lieu of velve number for full credit.
Unless otherwise specified, this is normal grading practice.
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o Attachment 4 2 Question Number: 2.08(2.50)
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NRC Resolution: Agree with comment. Answer key changed to read:
"The outlet valve (0.4] is a fusible valve (fusible (
yoke)[0.6]. A fire will melt the fusible yoke and i
, thevalvewillclose(0.6]." [
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Question Number: 2.09(2.00) ,
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NRC Resolution: Agree. Answer key changed as recommended; point , values remain the same. l
Question Number: 2.12(2.00) NRC Resolution: Agree. Key answer revised to read. "The flow nath !
into the i.CS does not change." Point value remains [ at 1.0. '
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, Quest'on Number: 3.01(1.50) [ NRC Resolution: Disagree with comment. The question asked which condition provides a more conservative indication of [ . power. In an undercompensated condition, indicated ' I power is higher, thus more conservative. No change l j made to the answer key, ;
.
- Question Number
- 3.02(1.50) '
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' MRC Resolution: Comment acknowledged. Because of the potential for i candidate confusion which results from the poor [ l werding of this question, and because of the i
- difference between plant operatinc practice and the j referenced training material, this question is }
l deleted from the examination.
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j Question Number: 3.03(1.00),6.01(1.50) l 1 t
- NRC Resolution: Agree with com.aenz. Answer key changed to read:
,
"The charging pumps will trip (speed will go te minimum) {
j [0.5]. i
! I i Question Number: 3.04 (2.50) [
t
- NRC Resolution
- Agree witt comment, HV-50V-1 and -2 are removed !
from the list of required answer:. with the [ l ' remaining three answer components worth 0.33 poir,t ! { each (total: 1.0). Yankee Rowe Training Department ! is strongly encouraged to correct the error which l appears on page 73 of Systems Training Manual, i Chapter 19, concerning the designation of these i valves, j i h I
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_ _ _ - _ _ _ _ _ __ - _ _ _ _ _ _ _ _ _ _ _- _ ___ o o Attachment 4 3
- Question Number
- 3.07(2.50),6.03(2.00)
NRC Resolution: Agree with comment. "Scram" added to list of
- acceptable answers, with any three of the four listed items required for full credit.
Question Number: 3.10 (2.00), 6.07 (2.00) NRC Resolution: These questions (3.10 and 6.07) are deleted from the examinations because there is no "Non-Return Valve Scram" as indicated in the question verbage.
i Question Number: 4.01 (2.50), 7.04 (3.50) 1 NRC Resolution: Agree. Answer key changed accordingly. Point values remain unchanged.
Question Number: 4.04 (1.75), 7.07 (2,50) i NRC Resolution: Agree. Part C of the answer is deleted from the exam. Candidate answers for Part C will not be gradd. Question value reduced to 1.50 (R0 exam) and 2.00 (SRO exam).
! Question Number: 4.08 (2.75) i NRC Resolution: Agree with comment. The second part of B is deleted I from the answer key. Candidate anwers regarding
- action (s) at 1200 psig wi1? not be graded. Question
' value remains the same wit.i .C poin';s being redistributed among part A and tha first part of B.
! Question Number: 4.11 (2.00) l NRC Resolution: Comment acknowledged. Becaum the question did not i refer to a specific procedure, and because the YAEC j procedures furnished to the examiner (OP-2652 and i OP-2653) are in conflict, this question is deleted I from the examination.
! Note: The facility's attention is directed to l Limitation No. 5 of OP-2652, Rev. 30, which states,
- "The entire ECCS shall be operable in the manual i mode in modes 1, 2, and 3 and in mndes 4 and 5 with MCS pressure >1000 psig." This appears inconsistent with the requirements of OP-2653, Rev. 21.
- - - - - - - - - - - - - - -- - - - - _ - - - - - - - - - - _ _ - - - - - - - - - _ _ _ _ _ - - - - - - - ._ _ _ _ _ _ , e o Attachment 4 4 Qucation Number: 4.12 (1.50) NRC Resolution: Same as 4.01d Question Number: 6.10(2.50) NRC Resolution: Agree with comment. Answer key changed as recommended. Point values remain unchanged.
Question Number: 6.11 (3.00) NRC Resolution: Agree both comments; answer key changed accordingly.
Question Number: 8.08(2.50) > NRC Resnlution: Comment acknowledged. Prior to loading this question to the EQB, the answer will be revised to indicate 10 bottles and 8 bottles Question Number 8.10 (3.50)
NRC Re;olution: Agree with both comments. Commercial telephone notification added as a second component to Part B, with each of the two components worth 0.25 point.
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"Orange Phone" added to Part C as an alternate acceptable answer in place of "NAS."
The following edditional changes were made to the written examinations as a result of the informal verbal review mentioned previously, and during the grading process, to improve the accuracy snd , quality of the answer keys. Note: editorial / grammatical changes which do not change intent or meaning are not listed here.
- Answer 1.15.b and 5.15.b:
, Included the following parenthetical phrase, "(all MCS temperatures
- increase)," following "T h i"C"'5'"
Answer 2.13a: Changed to read: "Water can be supplied from the fire water storage tank (1.0)."
Answer 2.09: l ' Included as alternate correct answers "Tk.39" for PWST," and "Tk.1" l for "0WST."
Answer 3.04.a: Corrected point breakdown values from 0.75 to 0.50 in two places.
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O o Attachment 4 5 Answer 3.07.a: Placed the phr:1s # 3n either IR-3 or -4" in parentheses.
- Answer 4.01.a and 7 'h 4
'
Inserted the wo+ io < C4 faro the word "rise."
, Answer 6.03.a: Replaced "on either s'"el ,2 with "(on IR-3 or -4)," t- Answer 7.02: Iteia 4, changed "SG ls to "59 ress."
i ' Answer 8.00: The third part of this answer was placed in parentheses, because the information contained therein is not elicited by the question.
< Points were redistributed so each of the first two parts is now worth > 0.75 ooint.
. References to further support answers which were modified were added to the reference listings as appropriate for each answer.
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