IR 05000289/1985013
| ML20128D669 | |
| Person / Time | |
|---|---|
| Site: | Three Mile Island  |
| Issue date: | 05/14/1985 |
| From: | Dudley N, Keller R, Kister H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20128D651 | List: |
| References | |
| 50-289-85-13, NUDOCS 8505290159 | |
| Download: ML20128D669 (37) | |
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.. ., U. S. NUCLEAR REGULATORY COMMISSION REGION I OPERATOR LICENSING EXAMINATION REPORT EXAMINATION REPORT N /85-13 FACILITY DOCKET N FACILITY LICENSE N DPR-50 LICENSEE: GPU Nuclear Corporation Post Office Box 480 Middletown, Pennsylvania 17057 FACILITY: Three Mile Island, Unit 1 EXAMINATION DATES: April 5, 198 and April 18-19, 1985 CHIEF EXAMINER: h// / d I h.Dudley,LVad'Exainer Date REVIEWED BY: f) #
/f[ffh R. M. Keller, Chief, Projects Section 1C Date APPROVED BY: d'
HV B. Ki(t%F, Chief, Projects Branch N I Date SUMMARY: Three candidates were examined and one R0 and one SRO license were issue All candidates performed well on the simulator portion of the examinatio lgg52AD0! l9 G
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1: REPORT DETAILS P-TYPE OF-EXAMS: Replacement X , 1 ; EXAM RESULTS: l R0 l SRO I i Pass / Fail l Pass / Fail l l l l i
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L l' l l l 1 I I I i 10verall i 1/1 1 1/0 I I i I I _l I I Chief Examiner at Site: J. Huenefeld, PNL
- Other Examiners:' N. Dudley,-NRC
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' Personnel Present at Exit Interview:
NRC Personnel N. Dudley NRC Contractor Perse..nel J. Huenefeld Facility Personnel M. Ross R. Magg 2. Summary of NRC Comments made at exit interview: An exit interview was held for the simulator portion of the examination on April 5,1985 at Lynchburg, Virginia. The NRC stated that all candi-dates were clear passes and had performed well on a wide variety of difficult major casualties. The facility stated that the scenarios-were taxing and provided a good test of their candidate An exit interview was held by Mr. J. Huenefeld on April 18, 1985, at the 1MI-1 facility. It was stated that both candidates were clear passes on the oral portion of the examinatio . Changes Made to Written Exam During Examination Review: Answer N Change Reason Also accept "b. Both Training manual on sources are classified as Neutron sources Section regenerative neutron N-6 page 17 states sources" "THI-1 uses two . . . regenerative neutron sources". Change to "Nothing, orifice OPA's were removed for rod assembly (ORA) has been cycle 5 as indicated by removed from the guide tube." the cycle 5 reload repor .12 Include "MFW pump" Includes the MFW pump as a major component in the flowpath to feed a dry OTS .16 Full credit given if damper Damper is interlocked is not mentione with fan rather than with RM __
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.- . .. _ Answe'r N Change Reason 4.14 Not grade Item C did not appear in questio '
Attachment: Written Examination and Answer Key (RO)
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U. S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION 9'//f/t, -
/ O Facility: TMI-1 #
Reactor Type: B&W Date Administered: April 18, 1985 Examiner: Apley, Huenefeld, Dudley Candidate: INSTRUCTIONS TO CANDIDATE: Use separate paper for the answers. Write answers on one side onl Staple question sheet on top cf the answer sheet. Points for each question are indicated in parenthesis after the questio The passing grade requires at least 701 in each category and a final grade of at least 80%. Examination papers will be picked up six (6) hours af ter the examination start Category % of Candidate's % of Value Total Score Cat. Value Category 25 25 1. Principles of Nuclear Power Plant Operation, Thermodynamics, Heat Transfer and Fluid Flew 25 25 2. Plant Design Including Safety and Emergency Systems __ 25 25 3. Instruments and Controls 25 25 4. Procedures: Normal, Abnormal, Emergency, and Radiological Control 100 TOTALS Final Grade i All work done on this examination is my own; I have neither given nor received ai Candidate's Signature
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2 PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW (25 points) Labbi the following statements as TRUE or FALSE: Because of the delay in cooldown, isolation of one OTSG when both are leaking may increase the integrated dose since the release will continue from the unisolated 0TSG for a longer perio .
(0.5) The NPSH limit does not apply for RCP bump (0.5) The faster a pump rotates, the greater its required NPS (0.5) Keeping the zircaloy clad temperatures below 2200*F will prevent any zircaloy-water reaction from taking plec (0.5) If a 100 C1 Co-60 source is placed 1 foot b hind a 4 foot high shield that blocks all direct radiation, th the area 6 feet from the sheild would be a radiation area d e to air scattered radiation (sky-shine). (0.5)
i Decay heat following a reactor trip is caused primarily by __ fissions due to delayed neutron (0.5) For the questions ,below, choose the MOST CORRECT answer:
, A reactor trip occurs during a startup due to a station blackout; decay heat generation is minimal. Approximately how '
fast will primary system pressure decrease due to pressurizer heat losses? (.75) psi / minute (4200 - 9000 psi / hour) psi / minute (600 psi / hour) psi /hr (1.2 - 2.5 psi / min) psi /hr; (0.12 psi / min) s \
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3 Which one of the following statements about a small break in the Pressurizer Steam Space (open PORV) at power is FALSE? (.75) RCS pressure drops as the pressurizer steam space is vented out the break; pressurizer level increase Pressure drops to the RPS trip setpoint; the reactor trip When pressurizer fills solid, two-phase natural circulation is los Without isolation of the PORV, a solid water cooldown would be require .9 Which one of the following statements about the TMI-1 installed neutron source is TRU (.75) The sources are placed as close to the source range detectors as possibl Both sources are classified as regenerative neutron source Sources are necessary to start up a reactor since there are no intrinsic neutron sources in a shutdown reactor cor The sources are placed on opposite sides of the cor The sources are placed together, in the region of highest ~~ potential flux (core center).
1.10 Which of the following statements about water hammer is FALSE? (.75) There is usually more danger of water hammer in vertical water lines than in horizontal water line A good general rule to prevent serious consequences due to water hammer is to always open or close valves, which regulate the flow of any fluid, slowl Keeping vents or drains shut while cutting in a line helps to prevent water hamme . Where bypass valves are provided around large valves, the bypass should be used to equalize pressures and temperatures before opening the large valv Section 1 Continued on Next Page -
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Answer the following questions:
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1.11 AP-1203-1 (Load Rejection) states that if you have a significant load rejection between 230 to 280 EFPD, rod worth and boron worth may not be sufficient to overcome peak Xenon. Explain what action should be taken to maintain the reactor critical and why this action is effectiv (1.5) 1.12 Why is there a longer period (at least ten (10) minutes) prior to recording data from incore detectors, than there is for excore detectors, following any control rod group motion or power change? 12.0) 1.13 If initial count rate is 100 cps with a shutdown margin of 41, what is the new value of countrate if shutdown margin is reduced to 3%. Show method of calculatio (2.5)
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1.14 Why does Xenon peak later following a shutdown from high power than it does when foTTowing a shutdown from a low power level? (2.5) 1.15 SUR is 1 dpm. You insert an amount of negative reactivity (x) to lower SUR to 1/2 dpm. If you insert another identical amount of negative reactivity (x), will the SUR be exactly zero? , _ _ Explai (2.0) 1.16 Assuming no air leakage into the main condenser, where do the noncondensible gases in the feedwater come from? (1.0)
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1.17 The figure below shows a 1/M plot versus number of fuel assemblies being added. Curves are provided for three detector locations. Which detector is sited too far away from the fuel assemblies being added? Explain your answe (2.0)
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1.19 During power operations at 20% power with three (3) reactor coolant pumps (RCPs) in operation the forth RCP (loop A) is started. Briefly DISCUSS the final steady state value of the following parameters: (2.5) hot leg temp, Cold leg temp, and Delta T (in the loop with two pumps) Feed flow (Each OTSG)
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7 PLANT DESIGN, INCLUDING SAFETY AND EMERGENCY SYSTEMS (25 POINTS) el Labte4The following statements as TRUE or FALSE: The OTSG tube to shell Delta-T limit is a "one way" limit--that is, the concern is having the tubes colder than the shell NOT the shell colder than the tube (0,5) Either L.P. heater string may be bypassed for maintenance and plant operation at rated power continue (0.5) The MUT outlet valve, MU-V-12, closes automatically upon the presence of a High Pressure Injection actuation signa (0.5) The Decay Heat Closed Cycle cooling water system normally supplies the "B" makeup pum (0.5)
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For the questions below, choose the MOST CORRECT answer: One condensate pump is sufficient to supply condensate up to what maximum power level? (.75) .3% % % %.
< Upon loss of ICS/NN1 " Hand Power," how do the Turbine Bypass Valves fail? (.75) open mid-position as is shu Section 2 Continued on Next Page -
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8 According to the Diesel Generator procedure (OP-1107-3), which of the following is done to ensure that the diesel generator is lined up for Automatic Standby? (.75) Place the voltage droop switch to the " parallel" position, Set the droop knob on the engine governor at 70 percen Place the Prelube pump in the " Continuous Run" positio Place the Diesel Generator manual voltage control at the 45 percent settin .8 During shutdown operations on the DecayyHeat Removal System, what potential consequence results if Df-Y-1, 2 and 3 were opened and the Decay Heat System was operated while the Reactor Building Spray System was being used for recirculation of the BWST? (.75) Injection of NaOH into the RC Transfer of Reactor Coolant into the BWS , c'. Overpressurization of the Decay Heat Suction line, Loss of NPSH to the Decay Heat pump ~ Answer the following questions: How is core bypass flow minimized for those fuel assemblies that do not contain control rods or neutron sources? (1.0) l l 2.10 If a loss of Secondary Service Closed Cooling System pump i occurs, how is cooling water supplied to the instrument sir l compressors? (1.5) l
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2.11 According to the Turbine Generator Operating Procedure (OP 1106-1) the voltage regulator should always be in automatic operation whenever there is load on the machine. Why is this so? (1.5) 2.12 What flowpath is used to feed a dry OTSG when RCS temperature is
>200'F? (Include source of water, major components, and injection point) (2.5)
2.13 What three local actions must be taken to gain local manual control of the Emergency Feedwater control valves, EF-V-30A/87 (2.0) 2.14 Show, by making a sketch, the various sources of power to the K and NNI Power Bus "ATA." (3.0) 2.15 The following curve taken from the Makeup and Purification procedure (OP 1104-2) defines the maximum allowable MUT pressure vs. tank level . What is the purpose of this limit? . Is the allowable area above or below the curve? (2.5)
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2.16 Under what two (2) conditions will the standby Intermediate Closed C5oling pump start? (1.5) 2.17 Make a basic sketch of the Engineered Safeguards Actuation System showing the relation between the bistable cabinets, the relay cabinets and the actuation cabinets. (Note: It is not necessary to show the individual sensors that input into the bistable cabinets) (3.0) 2.18 Name the two types of Rod Position Indication and briefly state how they are sense (1.5)
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11 INSTRUMENTS AND CONTROLS (25 POINTS) at LabMhe following statements as TRUE or FALSE: There is no automatic cut off on low level for pressurizer heaters while powered from the ES bu (0.5) The High Pressure Injection " Bypass Reset" push-buttons have no effect when pressure is below the setpoint for the HPI Bypass Bistabl (0.5) The letdown isolation valve MU-Y-3 is automatically reset after a Reactor Trip Reactor Building Isolation, and may be reopened prior to defeating the Reactor Trip R.B. Isolation signa (0.5) If actuated, the LPI and 4 PSI actuations must be bypassed prior to bypassing HP (0.5) When RB pressure is greater than 4 psi, then no more than four of the six channels of RB Isolation and Cooling can be defeate (0.5) For the questions below, choose the MOST CORRECT answer: Which of the following will occur when the RCS high point vents are opened? (.75) The RCITS system will not provide accurate / reliable hot leg
' level or reactor vessel level indicatio The RCS pressure indication will continually indicate saturated conditions for T Primary-to-secondary heat transfer will immediately be reestablishe The RCPs by procedure will be running since the interlock trips will have been defeate Section 3 Contiued on Next Page -
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12 Which one (1) of the following would tend to place the ICS closer to a BTU limit? (.75) A decrease in feedwater flo An increase in feedwater temperatur An increase in OTSG pressure, An increase in T,y,. Answer the following questions:
. Match the following bypass / switch functions'(letter) with the appropriate location (number). (2.0) RPS Channel B Bypass CRD Safety Group Out Limit Bypass PORY Key Switch, RC-RV-2 Automatic Override Pressurizer Heater Lo-Lo Level Cutoff Bypass ICS/NNI Power Monitor Cabinet (Key Switch) CRD System Logic Cabinet No. 3 .
3 Panel Right Front (PRF) N1/RPS Sub Assembly. B Cabinet No. . CRD System Logic Cabir.et No. 2 (Relay Room) Center Console (CC) (Key Switch) iSS'? - How will rapid RCS depressurization (example: 2155 to 600@sig in several minutes) ef fect. pressurizer level indication? Why? (1.5) 3.10 The following condition exists during a plant startup: the startup Feedwater valves are in automatic and about 90% open, the Main Feedwater valves are in automatic and are just beginning to open, the running Main Feedwater pump is in manual with Feedwater valve Delta P being maintained at 70 to 80 psi Describe how you would place the Feedwater pump turbine in automatic, and how the Main Feedwater valves respond during this operatio (2.5) 3.11 Give four automatic functions of the turbine bypass valve (2.0) 3.12 What two (2) conditions will result in the automatic de-energizing of the Source Range detector? (1.5)
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3.13 Given that the Source Range starts at 0.1 CPS and pnds at 106 CPS and thaj the Intermediate Range starts at 10-12 amps and ends at 10- amps: Sketch the amount of overlap expected between the Intermediate Range and the Source Rang (1.5) Show what power level on the Intermediate Range corresponds with 1%, 10% and 100% F (1.5) 3.14 Which four (4) RPS trip signals are bypassed in the shutdown bypass position? (2.0) 3.15 What three (3) other ICS signals are transferable by individual toggle switches in the "A" RPS cabinet? (1.5) 3.16 What thr.ee (3) interlocks are associated with the " Auxiliary and FuiT Handling Building Exhaust Duct" monitor, RM-A (1.5) 3.17 With the use of the ICS Figure supplied at the end of this exam, describe in detail how the ICS would respond if the input from the Nuclear Instrumentation (NIs) failed high (max output).
Assume 100% power operation with all systems in their normal automatic lineup and no operator action. Take your discussion to the final steady state situation or until a reactor trip occurs, whichever comes firs (3.5)
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14 PROCEDURES NORMAL, ABNORMAL, EMERGENCY, AND RADIOLOGICAL CONTROL (25 POINTS) e4 Labletihe following statements as TRUE or FALSE: The " operator at the controls" may be assigned secondary responsibilities (i.e., switching and tagging) provided the plant is in a cold shutdown or refueling mode and a CR0 trainee is available to monitor the consol (0.5) CAUTION tags, DO-NOT-OPERATE tags, and Instrument OUT-OF-SERVICE stickers may be used interchangeably to indicate equipment statu (0.5) On a loss of the "A" DC distribution system, the DC tie switches must be closed to re-energize the "A" system from the "B" sid (0.5) If a total loss of the secondary River Water System has occurred, the Nuclear River Water System may be cross-connected with the Secondary Service River Water System to allow continued reactor operatio (0.5) For the questions below, choose the MOST CORRECT answer: , According to Emergency Plan Implementing Procedure 1004.10
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l (Onsite/Offsite Radiological Monitoring), above what airborne radioactivity level should respiratory protection be used? i E-9 Ci/cc E+9 pCi/cc E-9 pCi/cc E+9 ppCi/cc (.75)
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15 Which of the following would indicate that the tube leak was in the "B" OT5G? "A" OTSG has a' higher level than the "B" 0TS "A" OTSG has a higher feed rate than the "B" 0TS "A" 0TSG has a higher 1-133 and Cs-137 sample result than the "B" OTS "A" OTSG steam line radiation level is higher than "B" OTSG steam line line radiation leve (.75) Answer the following questions:
= Problems encountered during surveillance testing are recorded on an " Exception and Deficiency (E&D) Sheet." Explain the difference between an " Exception" and a "Deticiency." (2.0) In what order should the following fire fighting equipment be used for combatting an electrical fire? C07 extinguisher HaTon extinguisher Water in the form of F0 (1.0) According to EP 1202-37 (Cooldown from Outside the Control Room), what immediate manual actions should the operator complete before evacuating the control roo (4.0) - Section 4 Continued on Next Page - . - . .
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4.10 According to AP-1012 (Shift Relief and Log Entries) match the action that the Control Room Operator must take (letter) with the document type (number). (NOTE: There can be more than one number per letter.) (2.5) Prior to assuming the shift, the CR0 must review this documen The oncoming CR0 must initial this documen This document must be reviewed by the CR0 during each shif The CR0 signs this document prior to assuming the shift dut . Active Tagging Application Book Locked Valve Log Outstanding Surveillance Schedule ES Checklist Revision Review Book TCN and STP Books Operations Memo Book 8, . Control Room Lo .11 What actions should be taken if there is a #1 seal leak off flow , of 8 gpm and a #1 seal outlet temperature of 210*F on RCP 1A? Assume that the reactor is at 100% power steady stat (2.0) - 4.12 According the Reactor / Turbine Trip Abnormal Transient Procedure (OP-1210-1), what actions, if any, should be taken af ter a Reactor / Turbine trip in eacE of the following situation Offsite power is lost and only one DG start (1.5) Pressurizer level is being maintained at 120 inches and makeup tank level is 60 inche (0.5) I Generator / field breakes remains close (1.0)
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4.13 Explain the procedure to be followed by the operating shift upon discovery that a control room instrument indication is out of calibration or unreliabl (2.0) 4.14 Which of the following are addressed by your Technical Specifications. Answer YES if the item is addressed and N0 if --- it is not addresse (3.0) Source Range NIs during startup Core Flood tank level Diesel Generators Plant Computer Incore nuclear detectors Turbine-Generator speed control RCP Seal Injection system i. OTSG chemistry (Cl, F1,0 2) j. Containment air temperature 4.15 State the three (3) High Pressure Injection (HPI) Initiation Eriteria as given in the Abnormal Transients Rules, Guides, and Graphs procedure, (OP-1210-10). (2.0) ,
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_________. __...._......___. _____...__________...______._________________ EQUATION SHEET
. __________....__...._____.___________........__. __ ....___..______..... . .
Where mi = m2 (density)1(velocity)1(area)1 = (density)2(velocity)2(area)2 ___________________________ ..____ _...._______.._______.._____...__....__ KE = mv2 PE = mgh PEi +KEi +P1Vi = PE +KE where V = specific 2 +P 2 Y22
~7 volume P = Pressure
___....____________ ._____________________.. ___... _____________.._______ Q = ic (T j - Q = m(hi -h2 I
. .... . P. _9 6-T ".) . . .. .Q..=.U A ( T.____ay3,T,s,tm) ... . ,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,
P = Po 10sur(t) p , po,t/T SUR = 26.06 T = (B-p)t T (p) _________......________________________________..._.. ____________________ delta K = (Keff-1)/K,ff CR 1 (1-Keffi) = CR 2 (I-Keff2I M = (1-K,ffi) SDM = (1-K,ff) x 100% K (1-Keff2I eff ______ ________.._____________________________________.. ________..._____ decay constant = In (2) = 0.693 A = Ag e-(decay constant)x(t) _ t t 1 1
..______... ___________/2___.._____/_2 ..._______________. ____________________
Water Parameters Miscellaneous Conversions 1 gallon = 8.345 lbs 1 Curie = 3.7 x 1010 dps 1 gallon = 3.78 liters 1 kg = 2.21 lbs 1 ft3 = 7.48 gallons I hp = 2.54 x 103 Btu /hr Density = 62.4 lbm/ft 3 1 Mw = 3.41 x 106 Btu /hr Density = 1 gm/cm 3
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1 inch = 2.54 centimeters Heat of Vaporization = 970 Btu /lbm Degrees F = (1.8) x (Degrees C) + 32 Heat of Fusion = 144 Btu /lbm 1 Btu = 778 ft-lbf 1 Atm = 14.7 psia = 29.9 in Hg g=g32.174 f t-lbm/lbf-sec 2
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W % Wtr//Y 4/afes TMI-1 ANSWER KEY PRINCIPLES OF NUCLEAR POWER PLANT OPERATION THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW (26 PulNIS) True Ref: Abn Trans Proc, p.1 .2 True Ref: Abn Trans Proc, p.10 1210-10 True ' Ref: Lesson Plan 1, p. 85, Heat Transfer Fundamentals False - reaction starts at approx.1800'F; the 2200*F limit is to keep , reaction to less than 1% of available zircaloy. (Reason not required.)
Lesson Plan 2, p. 6, Large PWR Core Heat Transfer
. Tru Ref: TMI Radiation Protection Program, p. 205 False - it is due to decay of fission fragments (reason not required). -
Ref: ATTS, Vol 3, Heat and Fluid Power, p.203 psi /hr
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Ref: EP 1202.2A, p. 5 - , 'l c. - Its never lost (reason not required).
Ref: Small Break LOCA Lesson Plan, p.1 .9 want them far from SR tr. only 1 is regener: tic there are intrinsic neutron sources; safety is issue not ability 3 to S/U sources are on outer edges be .We m. ... ....;, . a.. . m .m. m .. c_ * .
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(reasons not required)
Ref: Reactor Theory Lesson Plan, p. 6 1.10 they should be open (reason not required).
Ref: ATTS, Vol . 3, Heat and Fluid Power, p. 20-21 1.11 The reactor power must be increased (0.75) to burnout xenon (0.75).
Ref: AP-1203-1, p. 4 1.12 To allow detector output signals to reach steady state. The Rhodium has a half-life in the in-core which requires time to establish equilibriu Ref: Abn Proc 1203-7, p. 2 1.13 Ki= 1 = 1 = .962 1+5DM y 1+.04
= = .971 K2= 1 1 1+5DM
1+.03 CR 3 = 1-K = 1 .971 LM 2 / # 1 .962 CR2
= 100 = 131.03 .767 1.14 Equilibrium iodine is proportional to power, while equilibrium xenon is not. Therefore, you have a higher ratio of I to Xe at higher power level s. The greater the I to Xe ratio, the longer it takes for sufficient I to decay to Xe such that an equilibrium production and decay of Xe is occurring (i.e., the peak).
Ref: TNI Reactor Theory Lesson Plan, p. 49, 54, 59 1.15 No, S uA ;$ non ltne.w w;A re%t;,;q . Ma rs %te:& v 7 is ne.e. esp.g te g o .f r 4 F, D PNt y, O DPM +.k n S <om +i DPNt to + Js. DP . e W . ve 94 W- 6e O qba 9% -
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1.16 Disassociation of or breakdown of chemicals used for secondary water trea tmen (1/2 credit given if states liberation of dissolved feedwater gases in ' the steam generator.)
Ref: ATTS,Vol 3, Heat and Fluid Power, p. 46 1.17 Detector 3 was initially placed too far from the source. As a result its initial countrate was quite low and probably unreliable. In addition, the effect of moderator displacement causes the detector to grossly overestimate the effect of the first two increments. After the third increment of fuel is added, however, this detector will begin to give fairly reliable results since it sees the core very well and the source-core detector geometry is no longer being altered appreciabl Ref: ATTS, Vol 2, Reactor Theory, p.127 and 128 1.18 Saturated ~~~_ Subcooled ~ s s Superheated Saturated superheated Saturated Ref: Steam Table .19 Th and Delta T will decrease,cT will increase. This results from the energy balance Q=M C p (Th-T).
c Feed flow will be adjusted by the ICS to maintain Tc 's equal. The OTSG in the loop that gained flow will be increased, the feed flow int the other OTSG will be decreased with the final feed flows balanced between the two OTSGs.
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ANSWER KEY PLANT DESIGN, INCLUDING SAFETY AND EMERGENCY SYSTEMS (25 POINTS) Fals It is a "two way" limi Ref: OP 1106-2, p. 6, p. 20
- True Ref: OP 1106-2, p. 31 Fal se Ref: OP 1105-3, p. 18 Fal se Ref: OP 1104-2, p. 8
^
2.5 - Ref: OP 1106-2, p. 8 Shut Ref: OP 1105-4, p. 5 . Place the Diesel Generator manual voltage control at the 45 percent setting.- Ref: OP 1107-3, p.19, 20,18,17 Transfer of reactor coolant to the BWST Ref: OP 1104-4, p.10 Hu BcrAm.re Eru, OsuollyiadL orifice rod assembly -(ORA) 1 #r.;t:11cd inethe guide tub l'.rrvra Ref: Vil Cycle 5 Reload Report, p. 6-1 , . 2.10 Four valves open (SC-V57A+B/SC-V58A+B - #'s not needed) supplying cooling
.
h & W L & & M
.
.
.. - . ,
water from the fire service syste Ref: Abn. Proc. 1203-21, p. 2 2.11 Damage to the transformer would result if a trip were to occu Ref: OP 1106-1, p. 8 M m fe h kt r fummf+ f 2.12 Hotwell, condensate pumps, condensatje polishing demineralizer, gland seal condenser, condensate booster pumps,12th-6th stage low pressure heaters, 2nd-4th stage high pressure heaters, feedwater block valve, feedwater control valve, main feedwater nozzles, (need five of the eight components
,
for full credit).
Ref: OP 1210-10, C-302-81, CC-302-101
2.13 Align holes and insert pi . Position Auto-Manual switch on controller box to " Manual." Open equalizing valve located on outside of the diaphrag Ref: OP 1106-6, Enclosuree III, p. 25 2.14 Figure on p. 33 of OP 1107-2 (Attached) 3 seur6 n re.gviesd : V8A Ref: OP 1107-2, p. 33 and E-206-051 y.9 y;g g, gde, w;eA 1AA vin * e wL temak %s:Q 2.15 It assures that gas entrainment into the MU pumps will NOT occur in the event of Emergency Injection without isolating h the MU Below the curv Ref: OP 1104-2, p. 4 2.16 Low ICCW flow and if the running pump's circuit breaker trip Ref: ICCW Lesson Plan 2.17 See the figure %d4""'r followin AM
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Ref: I-TD-012 k 2.18 Absolute ana Relativ . hQ:m cA4aade 3 2.4A5L
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Absolute is sensed by reed switches h . Relative is sensed by a stepping motor in parallel with the CRDM motor p%to,
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ANSWER KEY INSTRUMENTS AND CONTROLS (25 POINTS) True Ref: EP-1202-29, p. 18 False Ref: Drawing 1-TD-010 or OP 1105-3, p. 2 True Ref: OP 1105-3, p. 12 True
~Ref: OP 1105-3, p.13 True Ref: OP 1105-3, p.14, Dwg 1-TD-01 a Ref: Abn Trans Proc 1210-8, p. 3 . An increase in OTSG pressure.
t j Ref: ICS training material, Fig IV - 4 _ l l: l Ref: AP 1013, Encl. 1 l l l It will indicate erroneously high offgassing and water ejection from the reference leg.
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Ref: Abn Trans Proc 1210-10, p. 8 3.10 Slowly lower the operating Feedwater pump speed with its ICS hand / auto controller. FW-Y-17A and B demand will increase and they should open maintaining a fairly constant Feedwater flo When Feedwater valve Delta P is.about 35 psid, check that the measured variable position shows no error, then place the Feedwater turbine in automati Ref: OP 1106-3, p.116 3.11 When <15% power they maintain 895 psig in the main steam heade Provide a high pressure relief if steam generator pressure exceeds 960 psi Provide an independent high pressure relief that operates proportional to OTSG pressure when >1027 psi Provides pressure control at 1010 psig after a tri Ref: OP 1106-5, p. 4, 5 3.12 When both IR channels >10-9 amps
, or when NI-5 or 6 and 7 or 8 are >10% F Ref: OP 1105-1, p. 5 3.13 See Figure 1 of OP-1105-1 Ref: OP 1105-1, P. 11, Figure 1
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3.14 Nuclear overpower based on flow and imbalance, percent maximu Nuclear overpower based on pump monitors, percent maximu Low Reactor Coolant System pressure, psig minimu Variable low Reactor Coolant System pressure, psig minimu Ref: OP 1105-2, p. 5 3.15 RC flow, RC pressure, and neutron flux ! Ref: OP 1105-2, p.15 3.16 The Aux Building vent damper _ and supply fa The Fuel Handling Building vent damper and supply fa The waste gas discharge valve (WDG-V47).
Ref: OP 1105-8, p. 56, Figure .17 The ICS goes into " Track" due to the crosslimit Rods will start driving in. Feed flow will start increasing to get within 5% of indicated Reactor Power. Reactor pressure and temperature and steam superheat will start decreasing. RCS low pressure
.will cause the Reactor to tri .
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ANSWER KEY 4.0 - PROCEDURES: NORMAL, ABNORMAL, EMERGENCY,ANDRADIOLOGICdLCONTROL (25 POINTS) True >, s Ref: AP-1028, p. 4 False - Caution tags not to be used in place of instrument out-of-service tags (reason not required).
Ref: AP-1037, p. 2
- False - Ties must be left open to preclude losing both sides (reason not required)
Ref: EP 1202-9A, p. 3 False - cannot cross-connect unless reactor shut down (reason not required).
Ref: An. Proc. 1203-19, p. 4
, ' c - other values are ridiculously high Ref: EPIP-1004.10, .- b Ref: Abn. Trans. Proc.1210-5, ;/ A deficiency is defined as an equipment problem or malfunction encountered during surveillance testing, or a test not completed by the late performance dat ,
An exception is ~ defined as a change in the procedure which does not alter the scope or intent of the procedur Ref: AP-1001A, p. 12, 17 Halon CO 2 ~ Water-(last resort) ,
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Ref: EP 1202-31, p. 9 Depress REACTOR TRIP pushbutton on console C Verify turbine tri Start the motor driven EMERGENCY FEED PUMPS from console CL and C , d.. Depress 1A FEEDPUMP TURBINE and IB FEEDPUMP TURBINE TRIP push buttons on CL-(auto starts steam driven EFP). Reduce number of REACTOR COOLANT PUMPS to one per loo Cross-tie the Nuclear and Turbine Plant channels of the M and I sound powered phones in the I and C Foreman's office or in the rear of Panel PLF g. ' Start emergency boration depending on Emergency Source Tank either by: Open MU-V51, set max strokes on the strokes counters and start both boric acid pumps, or Set max batch size and pre-shutdown on batch controller, clear controller, go to start, open MU-V10, insure MU-V9 is closed, open WDL-V61 have aux operator at LWDS Panel open WDL-V49(50) and close WDL-Y93(94) and start WDL-P13A(B) if not running.
' Maintain makeup pump in operation and pressurizer level and seal injection control automati Ref: EP-1201-37, p. 1, 2 4.10 . 25 pts each Ref: AP-102, p.13 4.11 Close the seal leakoff valve, reduce power to 75% and secure the pum Ref: OP 1203-16, p. 1 4.12 Verify one DG starts and loads [0.4], Restore makeup [0.3] seal injection [0.3] and EFW [0.3], Refer to the Station Blackout procedure
[0.23
. No action require Manually trip the generator output breakers and the field breaker .
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Ref: OP 1210-1 pg 1, and .13 SS/SF/CR0 are responsible for identifying and logging instrument 005, assuring that a work request for repair is submitted, and placing a yellow 005 tag or sticker on instrumen Ref: AP 1036 4.14 Yes f. Yes Yes No Me S h. No Yes 1. No No j - Yes Reference: Technical Specifications . 84.15 psig ESAS has auto initiated or_ Subcooling margin is less than 25 Deg F oj Neither OTSG is available as a heat sink !
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