ML20205G354
| ML20205G354 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 11/07/1985 |
| From: | Gore B, Huenefeld J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20205G332 | List: |
| References | |
| 50-346-OL-85-01, 50-346-OL-85-1, NUDOCS 8511130226 | |
| Download: ML20205G354 (51) | |
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U.S. NUCLEAR REGULATORY COMISSION REGION III Report No. 50-346/0L-85-01 Docket (s) No. 50-346 License No(s). NFP-3 Licensee:- Toledo Edison Compa'ny
. Facility. Nan'e: Davis Besse
- Examination Administered At: Davis Besse Examination Conducted: September 24, 25, 26, 1985
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Examiner (s): f.C.Huenefeld Date V
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f.Y1b F. Gore Daye/
Approved By: (dR)gAhh ///7/ 0 j, Dqte f (f .
Examinatfor. Summary.
Examination administered on September 24, 25, 26, 1985, (ReportNo. 50-346/0L-85-01) to six reactor operator candidates.
Results: All six candidates passed the examination.
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.. REPORT DETAILS s'
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- 1. Examiners - - - ~
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J..C. Huenefeld, PNL . -
B. F. Gore, PHL -
' 2. Examination Review Meeting ~
l4 The examination rev,1ew meeting was conducted in conjuncIion with the exit ,
1 meeting. -
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- 3. Exit Meeting At the conclusion of,:the examinations, an exit meeting was held with the licensee. Persons'in attendance were: -
Examiners: . .s J.C.Huenhfeld B. F. Gores -
~ Toledo Edison Pe'rsorinel:-
R. Sirrpkins, Training Supervisor T. Bergner, Quality Instructor '
L. Storz, Plant Manager . _
ss J. Michallis, Operations Superintendent
, 4 M. Stewart, Training Directot ,
TAe facility was. informed of one candidate who was not allear pass. In addition, the facility comments concerning the written examinations were
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discussed. Those coments and their resolutions are attached to this report.
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ATTACHMENT 1 1
The following are the examiner responses to the facility comments made regarding the reactor operator examination of September 23, 1985.
QUESTION 1.5 How does the boron concentration affect the accuracy of criticality estimates provided by a 1/M plot? Exolain why.
CONCERN 1.5 The reference document is a correct reference, Licensing Info Manual. The concern is, however, this' type of analysis has been considered as a SRO item.
The' licensing manual does not indicate this as a SRO item and properly should not. The Davis-Besse philosophy of when to address the differences of SRO versus R0 duties starts at the Task List items with further clarification at the lesson objective level. During the last Complete Defuel/ Refuel, the Tech-nical Engineers determined 1/M plots were not required, therefore, suggest 1/M plots not a viable task to test to.
RESPONSE 1.5 No response.
QUESTION 1.6 Irug or False. The peak value of Samarium following a trip from 100% power is exactly twice the peak value following a trip from 50% power.
CONCERN 1.6 The answer as indicated on the key is in error. The 100% peak is indicated as -1.4% delta k/k while at 50% is -1.2% delta k/k. This does not indicate a value twice as high. If the question's intent was to look at the increase above the equilibrium value, I would understand how the response would be true.
The question, however, did not with sufficient clarity do this. License Info Manual, Vol. 1, Pg. 1-69.
RESPONSE 1.6 The answer key was corrected.
1
2 QUESTION 1.7 Irm or False. If the ratio thennal flux at some position to the average thermal flux in the core changes by a factor of 2, the rod worth at that posit-ion will change by factor of 2.
CONCERN 1.7 A concern exists that a student who understands rod worth is proportional to flux would(Flux formula. quite/ Flux probably)
Avg. piss thisbeen It has itemour if he did not knowdue understanding thetocorrect pervious NRC exam standards that formula sheets would be provided with exams and there-fore rote niemorization for formulas would be excluded as a lesson objective.
In fact, associated Reactor Operator Tasks indicate the Reactor Operator may perform calculations of rodworth with the procedural direction which would include any applicable formulas necessary. While testing of a candidate's ability to use a formula would be seen as proper, rote recall of that formula would not. See Nureg 1021 ES 202, Scope of Written Exams Administered to Reactor Operators, Page 6 of 6, . Item #22, which states all equations required to answer parts of the exam should appear on equation sheet or as part of the question.
RESPONSE 1.7 I agree with the utility that thir mestion rests on somewhat of an esoteric point; however, only one can(ideh c <t of the six missed the answer. No action was taken on this.
QUESTION 1.17 Keff is 0.99. Is the shutdown margin:
- a. 0.1%
- b. 0.99%
- c. 1.01%
- d. 10%
C0fjCERN 1.17 This question,. as #1.7, requires rote memorization of formulas. This is not consistent with past NRC examination practices as no formula sheet was prov-ided. The answer key suggests as a reference, use the equation sheet. Possibly
-it was an oversight during the exam's construction. Refer to Question 1.7 for reference to Nureg 1021.
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3 RESPONSE 1.17 The relationship of Keff to shutdown margin is fundamental. Only one of the six candidates had trouble with this question. No action was taken.
OUESTION 1.18 State whether each of the following statements is true or false:
- a. If the reactor period is cut in half startup rate will be doubled.
- b. It will take the same amount of time to increase reactor power from 20%
to.40% as it will to go from 40% to 60% if the startup rate is constant.
CONCERN 1.18 See explanation of Concern 1.17.
RESPONSE 1.18 This question requires more of an " operational feel" for the relationship between SUR and period rather than a calculation. I do not agree with the facility..
QUESTION 2.10 According to the Turbine Operating Procedure, SP 1106.01, the turbine control system and the turbine bypass valves are expected to permit a trip from a maximum of load without safety valve actuation. (Selectone.)
- a. 20%
- b. 40%
- c. 60%
- d. 80%
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CONCERN 2.10 The specific concern is that the procedure step referenced itself is in error.
In fact 40% is correct if the Atmospheric Vent Valves are also considered functional.
Valve- % Steam Dump Capability AVV(2) 7.5% each
-TBV (6) 25% total 40% Totai Dump John Johnson, Operations Engineering Supervisor, has been notified of the dis-crepancy and will take actions to correct the procedures. The concern is that candidates knowledgeable of the above Table may select 20% using the TBV's as the sole method of Steam Dump. It is requested you allow full credit at this time for resp?nses a or b. Ref: SP 1106.01, Pg. 2.
RESPONSE 2.1Q I am not convinced that the procedure is in error. The procedure states that the greatest power that the reactor can be at and still not lift reliefs is 40%. Because the power generated by the reactor ic decaying rapidly after a trip, it is reasonable that the 25% capacity of the TBV's would be sufficient to prevent reaching the stream reitef setpoint. The facility's response relates more to the hypothetical situation of the turbine tripping with the reactor remaining at 40% power.
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5 0UESTION 2.15 Describe what happens when a diesel generator operating at full speed receives a stop signal.
CONCERN 2.15 The: concern is the clarity of intent to exactly what portions of the diesel are to be-looked at. Quite possibly a description of Fuel Rack movement, output breaker operation (if closed at moment of stop signal), SFAS conditions, etc., could be developed by the examinee. If the intent was to test the know-ledge.of the idle stop circuit, why not ask for that. '
In addition, if the student uses the "stop signal" assuming an emergency stop button was depressed the idle stop circuit will not function. This also applies to protective trip stop signals as listed in the System Procedure. Ref: SP 1107.11.13, Pg. 33, Section 7.4.
RESPONSE 2.15 No candidate missinterpreted the intent of this question. No action was taken.
QUESTION 3.6 What are the reactor trip setpoints for the following: ,
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- a. RC high. temperature - F
- b. RC high pressure - psig
- c. RC low pressure - psig
- d. High flux (three pumps) - %
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CONCERN 3.6 The actual setpoints are as follows:
RC high temperature - less than or equal to 618 F RC high pressure - less than or equal to 2300 psig RC low pressure - greater than or equal to 1983.4 psig High Flux (3 RCP's) - less than or equal to 79.7%
In addition, the actual setpoints at which the parameters trip would be more conservative and thus different from the Tech Spec setpoint. It is recommended that above setpoints be used as the absolute maximum or minimum as applicable and a tolerance band be allowed in the other direction per Setpoint Index.
This has been a continuous problem and we would very much like to reach an agreement which will lay setpoints and acceptable response issues to rest.
DB Tech Specs, Table 2.2.-1, and attached Setpoint Index.
RESPONSE 3.6 The only candidate that missed points put down 610 F for RC high temperature.
I agree with the facility's suggestion.
QUESTION 4.10 List the five-(5) automatic actions that should occur as a result of a reactor trip from high power.
CONCERN 4.10 Procedure EP 1202.01 was not referenced in the question as a guide to the student, therefore we request the additional items below be included as possible correct responses.
RESPONSE 4.10-
-I agree with the facility that the procedure should have been referenced in the question as a guide to the candidate. However, since the question is in j
the procedures secticn'and since it says list "the" five actions, the impli-cation was according to the EP. No credit was given for the facility suggested )
answers; however, it'would have been seriously considered had it have made the difference between passing and failing.
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MASTER EVRM .
U. S. NUCLEAR REGULATORY C0t911SSION l REACTOR OPERATOR LICENSE EXAMINATION Facility: Davis Besse-1 Reactor Type: B&W Date Administered: September 24, 1985 Examiner: J. C. HuenefeldN. J. Apley Candidate:
INSTRUCTIONS TO CANDIDATE:
. Use separate paper for the answers. Write answers on one side only.
Staple question sheet on top of the answer sheets. Points for each question are indicated . in parentheses af ter the question. The passing grade requires
- at least 70%'in each category and a final grade of at least 80%. Examination papers will be picked up six (6) hours af ter the examination -starts.
Category 1 of Candidate's % of '
Value Total Score Cat. Value Category 25 25 1. Principles of Nuclear Power Plant Operation, Thermodynamics,
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Heat Transfer and Fluid Flow 25 25 2. Plant Design Including Safety and Emergency Systems l
25 25' 3. Instruments and Controls 25 25 4. Procedures: Normal, Abnormal.
Emergency, and Radiological
' Control i
100 TOTALS Final Grade %
All work done on this examination is my own; I have neither given nor received aid.
Candidate's 5ignature
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[ 1 DAVIS BESSE September 24, 1985
.1.0 PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, THERMODYNAMICS HEAT TRANSFER AND FLUID FLOW (25 Points)
'1 1.1 LDc--ing a reactor startup, explain why:
- a. _A continuous rapid startup will result in criticality occurring at a . lower count rate than an interrupted, slow startup. (1.0)
- b. Rod speed will have no effect on the critical rod posi tion. (1.0) 1.2- Assume you have a reactor trip from 100% power. In Case A all rods go in, power initially decreases to about .64%, and after two minutes the rate of decay.is at a -80 second period.
1In Case B only two safety groups go in. Explain how neutron
, count rate would behave in Case B (compared to Case A) for the first ten minutes following the plant trip. (2.0) 1.3 The moderator temperature coefficient of reactivity is
_g reater at 500 F than at 400"F. Why? (1.0) 1.4 ' Doppler coefficient is primarily affected by the following parameters:
- a. Moderator Density
- b. Initial Fuel Temperature Explain how an increase in each of those parameters would affect the Doppler Coefficient (increase or decrease) and wh. (2.25)
, 1.5 How does the boron concentration affect the accuracy of
. criticality estimates provided by a 1/M plot? Explain why. (2.0)
, 1.6 TRUE or FALSE. The peak value of Samarium following a trip from 100% power is exactly twice the peak value following a trip from 50% power. (0.75)
~1.7 TRUE or FALSE. If the ratio of thermal flux at some posi-tion to the average thermal flux in the core changes by a factor of12,.the rod worth at that position will change by a factor of 2. (0.75)
!- 1.8 The operator is throttling the flow rate of a D.H. pump.
If cavitation is detected at the flow control valve,'should
' flow be increased or decreased to stop the cavitation.
Explain. (2.0) d 4
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2 DAVIS BESSE September 24, 1985 1.9 General limits and precautions state:
Before initiating cooling water flow on either side of heat exchangers or coolers in a system: The. cooler, all con-necting piping and components shall be filled and vented at reduced flow rates (preferably gravity flow). Why? (1.0) 1.10 Quadrant Power Tilt (QPT) values may be substantially higher than normal during a three RCP start. Explain why? ^ (1.0) 1.11 Fill in the blank: The full effect of an APSR move will not be seen until approximately ? hours after .
- a move. (1.0)
- a. 2 to 4
- b. 6 to 8
- c. 12 to 16
- d. 20 to 24 1.12 During an RCS natural circulation cooldown, why is it important to control the pressurizer level at a steady or slightly increasing trend? (2.25)
-1.13 Fill in the blank: When the RCPs are stopped, coolant circulation in the head region of the reactor vessel ceases.
The reactor head will ? losses to the containment-atmosphere.
- a. not cooldown at all by
- b. cooldown at 1.5'F/hr by
- c. cooldown at 30*F/hr'by
- d. cooldown at any rate the rest of the RCS does by (1.0) 1.14 WA doesn't the temperature of the steam leaving the OTSG exactly parallel T-hot as reactor power increases from 25
- to 100%? (1.25) 1.15 A venturi is used to mix foam and water of the Subsurface Foam Injection System in the Fire Protection System. Explain the principle of operation of a venturi as it applies to this system (i.e., how are the foam and water automatically mixed in the correct proportion). (1.5) 1.16 The limitations and precautions section of System Procedure SP 1104.02 (Makeup and Purification System) instructs the operator to "whenever possible, minimize the number of times the 16'down system is isolated." Why is this precaution
-included? (1.0)
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3 DAVIS BESSE September 24, 1985 1.17. K,ff is .99. .Jstheshutdownmargin:
- a. .1%
- b. .99%
- c. 1.01%
- d. 10% (0.75) 1.1d ' State whether each of the following statements is TRUE W LSE:
- a. If the reactor period is cut in half, startup rate will be doubled. (0.75) -
,b. It will take the same amount of time to increase power from 20% to 40% as it will to go from 40% to 60% if the startup rate is constant. (0.75)
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4 DAVIS BESSE September 24, 1985
~ 2. 0 PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS (25 Points) 2.1 WhJ is it not possible to operate the SFP pumps when cooling the SFP with the DH pumps? (1.0)
List the normal operation loads off the service water pump
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2.2 for: (2.7)
- a. Primary Side (3 loads)
- b. Secondary Side (6 loads) 2.3- Describe two (2) plant conditions which might require the operation of two CCW pumps. (2.0) .
2J4 WhJ are the Clean Waste Receiver Tanks (CWRTs) recirculated through the Degasifier? (1.5) 2.5 What is the purpose of the Containment Recirculation System? (0.8) 2.6 The capacity of the Startup Feed Pump is sufficient to provide flow up to: (Select one.) (1.0) a) 1% power b) 74 MLB/hr c) 5% power d) 240 MW thermal power 2.7 If an SFRCS trip occurs, the Steam Generator level will be controlled at 7 inches on the Startup Range. If an SFRCS and an SFAS level 2 trip is present, the Steam Generator level will be controlled at ? inches on the Startup Range. (1.0) 2.8 What three (3) sources of water can supply the Auxiliary Fiedwater pumps? - (1.5) 2.9 State ten (10) of the fourteen (14) malfunctions, faults, or actions that will cause a turbine trip. (2.0) 2.10 According to the Turbine Operating Procedure SP1106.01, the turbine control system and the turbine bypass valves are expected to permit a trip-from a maximum of ?
'oad without safety valve actuation. (Select one.) (1.0)
- a. 20%
- b. 40%
- c. 60%
- d. 80%
--Category 2 Continued on Next Page-
5 DAVIS BESSE September 24, 1985 2.11 What-purpose does the back pressure control valve, CD 2796, in the condensate pump discharge line serve? (1.0) l 2.12 If two condensate pumps are capable of handling full steam generator feed flow under full power conditions, why are three pumps normally run to maintain 100% power? (1.5)'
2.13 State the purpose of the Main Steam Isolation Valves and the Main Steam Non-Return Valves. (1.5) 2.14 Draw a basic one line diagram of the 4160V system from the "K" and "B" bus to the "C1" and "D1" bus. Include the diesel generators and major breakers in your drawing. You do not .
need to show electrical loads. (3.0) 2.15 Describe what happens when a diesel generator operating at full speed receives a stop signal. (1.5) 2.16 TRUE or FALSE. The diesel generators are not large enough to carry both a MU pump and an LPI pump during a LOCA coincident with a loss of power to essential buses. (0.5) 2.17 Describe how to take local control of a SU FW valve. (1.5) f
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-.- . September 24, 1985 3.0 INSTRUMENTS AND CONTROLS (25 Points)-
3.1. When pressurizer heater banks 2, 3, or 4 control switches are placed in "0N", will they respond to either the-
. pressure control signals or the low level interlock? (1.0)
- leak. and RCS pressure has stabilized around 1500 psi (55'F saturation margin). As reactor operator you note
'that core flood tank pressure is the same as before, but that level has i. creased 4 inches. Explain why. (1.0) .
3.3 TRUE or FALSE. Pushing the stop button locally or using pistol grips in the Control Room or at the Breaker will
, NOT stop a Circ Water Pump if the Discharge Valve is NOT NT1y closed first. (1.0) 3.4- Indicate each CCW pump trip below which will Ng occur if an unblocked SA signal for that pump exists. (1.0)
- a. CCW outlet-temperature on the operating heat exchanger 4 is greater than 125'F.
i b. Pump outlet flow of less than 1000 gpm.
. c. Bus Fault Lockout
- d. Ground Fault
- e. Overcurrent 3.5 Limits and precautions for the Turbine Plant Cooling Water System (TPCWS) warn that derivative action con-troller manual setpoints must be changed very carefully.
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Why?, (1.0) 3.6 What are the reactor trip setpoints for the following: <
a.- RC high temperature - *F (0.5)
! b. RC high pressure - psig (0.5) psig (0.5)
- c. RC low pressure -
- d. High flux (three pumps) - % (0.5) 3.7 When energizing ICS cabinets, which power source is turned on first: AC or DC7 p.,&. g i n . (1.0) e i
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7 DAVIS BESSE September 24, 1985 3.8 a. List the four (4) requirements for Rapid Feedwater R E ction (RFR) (1.0)
- b. Describe how the feedwater system will respond to RFR. (1.0) 3.9 Which of the following statements is TRUE regarding the Non-Nuclear Instrumentation (NNI) System as described in the NNI 0perating Procedure, SP1105.06. (Select one.) (1.0)
- a. -Only the Y NNI cabinets are required for normal operation.
- b. The Y NNI cabinets contain both, redundant and non-redundant instrumentation.
- c. The X NNI cabinets contain both redundant and non-redundant instrumentation.
- d. Only the X NNI cabinets are required for normal operation.
3.10 The RCP Seal Injection Flow hand / auto station: (Selectone.) (1.0)
- a. indicates flow in "gpm" when in " Meas Var" and demand (0-100%) to MU 19 when in "Pos".
- b. indicates demand (0-100%) to MU 19 when in " Meas Var" and "gpm" when in "Pos".
- c. indicates demand (0-100%) to MU 19 when in both " Meas Var" and "Pos".
- d. indicates "gpm" when in both " Meas Var" and "Pos".
3.11 Briefly describe the function of the T avg selector (HS-RC7) if flow is lost in both loops, (),3) 3.12 TRUE or FALSE. A majority of the control room indicators and recorders are powered from NNI Y. (0.5) 3.13 Briefly state two major reasons why the selectable NNI hand stations are posdtioned in accordance with list "A" of the NNI Operating Procedure. SP1105.06. (2.0) s
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-, ,- September 24, 1985 3.14 The Victoreen control roon radiation instrumentation reading out in CPM has a bottom scale. The units of that bottom scale are: (Splect one.) (1,0)
- a. in micro-curies per milliliter
- b. in CPS
- c. in voltage (used for testing only)
- d. in ar/hr equivalent 3.15 On the front of each Victoreen control room module is a grown " FAIL" lamp. Under normal operating conditions what should the status of this light be? 0% % &q<j _(1.0)
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3.16 Which of the fallowing process radiation monitors will per-form automatic interlock or control functions upon actuation of a HIGH alarm? (There may be more than one.) (1.8)
- a. Reactor Coolant Purification System failed fuel detector (RE1998).
- b. Clean Radwaste Channel RE 1770A and/or RE 17708.
- c. Miscellaneous Radwaste Channel RE 1878A and/or RE 18788.
- d. Radioactive Waste Gas Discharge RE 1822A and/or RE 18228.
- e. Component Cooling Water Channels RE 1412 and RE 1413.
- f. Service Water Discharge Header RE 8432.
- g. Station Effluent RE 8433.
- h. Penetration Rooms, Purge System RE 5052 A, B and C.
- 1. Control Room Emergency Ventilation System RE 5327 A, B, C and RE 5328 A, B and C.
3.17 State the four (4) inputs to the Steam and Feedwater Rupture Control System. (2.0)
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9 DAVIS BESSE September 24, 1985 3.18 Briefly explain why the reactor demand station should be placed in " HAND" if the Rod Control Panel is placed in
" MANUAL". (1.5) 3.19 TRUE or FALSE. With CRDM breakers A, B, C, and D all shut, .
tripping open breaker D will result in a trip of breakers A, B, and C. (0.5) 3.20 TRUE or FALSE. According to the Precautions and Limitation Section of the Control Rod System Operating Procedure.. -
Group 8 may be moved at the same time other groups are (0.5) moving in AUTO.
3.21 What bias (psig) is supplied to the turbine bypass valves for the following situations?
- a. Reactor trip (0.2)
- b. Turbine Trip (No Reactor Trip) (0.2)
- c. Unit Load Demand >15% (0.2) 3.22 TRUE or FALSE. The Main Steam Line RAD monitors will R67 accurately respond in analyze mode with the reactor shutdown. (0,5)
- End of Category 3 -
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10 DAVIS BESSE September 24, 1985
4.0 PROCEDURES
NORMAL, ABNORMAL, EMERGENCY, AND RADIOLOGICAL CONTROL (25 Points) 4.1 The Nuclear Steam Supply System Limits and Precautions Procedure (PP1101.01) lists nine (9) circumstances requiring venting of the Reactor Coolang System. State two (2) of these nine (9) circumstances. (2.0) 4.2 If both seal injection and CCW are lost; within what maximum time must RCPs be tripped? (1.0) a., 30 seconds ~
- b. 90 seconds
- c. 4.5 minutes
- d. no time limit 4.3 A Core Flood (CF) line braaks downstream of the LPI tie-in: This renders one LPI string inoperable. The Diesel supplying the second LPI amp fails. The operator opens the motor operated LPI crassover valve (DH 830 or DH 831),
but forgets to close the suction valve on the disabled pump.
What will happen? (2.0) 4.4 Containment vessel pressure increases to 18.4 psi.
The Containment Spray Automatic Control Valves do not operate correctly, and have to be opened manually from panel C-5716.
Assuming containment pressure increases to above 38.4 psia, what must be done with the control valves when suction transfer from the BWST to the Emergency Sump is made? (1.0) 4.5 For each of the following, state under what conditions that safety equipment's initial position or state may be overridden,
- a. Containment Gaseous and Particulate Monitors Sample Line Isolation Valves. (0.5)
- b. Reactor Coolant Pump (RCP) Seal Injection and Return Isolation Valves. (1.0)
- c. Stopping of High Pressure Injection (EP1202.01, specific rule #2). (1.0)
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11 DAVIS BESSE
, . September 24, 1985 iV 4.6- a) 'At what level is the OTSG to be considered dry? (0.5) b)' What action is required to recover level and why? (2.0)
'4.7 TRUE or FALSE. The diesel generator power factor must be maintained at 0.8 to ensure proper mechanical loading. ,
(0.5) 4.8 TRUE or FALSE. Lubricating oil may be added to the
-diesel engine while it is running.- (0.5) 4.9 T_g LE or JFAL E. According to the Diesel Generator Operating be operated
- Procedure at idle speed (5P1107.11),
of 400 rpm the fromdiesel engine the idle startmay/stop control panel'for an unlimited period of time. (0.5) 4.10 List the five (5) automatic actions that should occur as a result of a Reactor Trip from high power. (2.5)
~4.11 After a reactor trip, off-site electrical power is lost.
The diesel supplying the bus with the previously running makeup pump fails to auto str.rt. What r"st be done prior to attempting a manual' start of that diesel to power up the bus? (1.5) 4.12 a. With initial switch lineup on X indicators,, loss of X AC will cause loss of the Pressurizer low level heater interlock and the MU Tank low level transfer interlock. How can these interlocks be regained? (1.0)
- b. Will this action regain pressurizer and MU tank level indication? (0.5) 4.13 Briefly state two (2) sources of boron for emergency boration. (1.0) 4.14 -What action is required by Emergency Procedure EP1202.01 IT TW flow will net decrease to a SG with increasing level? (1.0) 4.15 What two (2) conditions, as specified in Emergency Procedure EPTl02.01, constitute adequate primary to secondary heat transfer?- (2.0) 4.16 What immediate operator action is required if the pressurizer spray valve sticks open and the spray line isolation valve will not shut (assume 100% FP)? (1.5) 4.17 What is the meaning of " Bump an RC pump"? (1.0) 4 i
- Category 4 Continued on Next Page -
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12 DAVIS BESSE
. - September 24, 1985 9
4.18 TRUE or FALSE. The purpose of the Control Room Evacuation Frdcedure T 203.12, is to bring the plant to a cold shutdown condition using only controls outside of the control room. (0.5)
- End of Category 4 -
- End of Exam -
__ a
M A STE<< A AlsWER Kol -
U. S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION Facili ty: Davis Besse-1 Reactor Type: B&W Date Administered: September 24, 1985 Examiner: J. C. Huenefeld/W. J. Apley Candidate: Answer Key INSTRUCTIONS TO CANDIDATE:
Use separate paper for the answers. Write answers on one side only.
Staple question sheet on top of the answer sheets. Points for each question are indicated in parentheses after the question. The passing grade requires at least 70% in each category and a final grade of at least 80%. Examination papers will be picked up six (6) hours af ter the examination starts.
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 Flow 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 %
All work done on this examination is my own; I have neither given nor received aid.
Candidate's Signature
1 DAVIS BESSE September 24, 1985 1.0 PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, THERMODYNAMICS HEAT TRANSFER AND FLUID FLOW (25 Points) 1.1 During a react'or startup, explain why:
- a. A continuous, rapid startup will result in criticality occurring at a lower count rate than an interrupted, slow startup. (1.0)
- b. Rod speed will have no effect on the critical rod position. . (1.0)
ANSWER 1.1 a. As you get closer to criticality the generation time gets longer because of the higher multiplication rate.
Therefore it takes longer for equilibrium count rate to be achieved. A rapid startup will result in criticality being achieved before the count rate has had time to achieve a higher equilibrium.
- b. Rod speed may affect the rate at which delta K is changed, but it does not impact total reactivity added which is what determines criticality.
Ref: Licensing Info Manual Vol. I, p. 1-16&17 1.2 Assume you have a reactor trip from 100% power. In Case A all rods go in, power initially decreases to about .64%, and after two minutes the rate of decay is at a -80 second period.
In Case B only two safety groups go in. Explain how neutron count rate would behave in Case B (compared to Case A) for the first ten minutes following the plant trip. (2.0)
ANSWER 1.2 The initial prompt drop would not be as great, it would take longer +.o settle out at a -80 second period, and count rate would be higher during the transient and at the eventual steady state source level. 2/3 point each item.
Ref: Licensirg Info Manual, Vol. I p. 1-31
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l l
l
2 . DAVIS BESSE September 24, 1985 1.3 The moderator temperature coefficient of reactivity is greater at 500*F than at 400*F. Why? (1.0)
ANSWER 1.3 -At higher temperatures the rate of change of density with respect to temperature is greater than it is at lower tem-peratures.
Ref: Licensing Info Manual, Vol. I, p. I-38 1.4 Doppler coefficient is primarily affected by the following parameters:
- a. Moderator Density
- b. Initial Fuel Temperature Explain how an increase in each of those parameters would ,
affect the Doppler Coefficient (increase or decrease) and why. (2.25)
ANSWER 1.4 a. The doppler coefficient would decrease because the moderator is being made more effective in thermal-izing neutrons, and therefore fewer neutrons would be affected by the change of f and p in the fuel,
- b. The doppler coefficient would decrease. If fuel temperature is increased, the average energy of the thermal neutrons in the fuel region also increases.
The increased thermal energy reduces the probability of thermal absorption of these neutrons by the fuel, thus decreasing f. The rate of decrease in f becomes lower as temperature (fuel) increases, thereby reducing the doppler coefficient. Also reducing the doppler is the change in resonance escape probability (becomes smaller). The neutron energies covered increases, but the individual absorption reaction probability at a specific energy close to the resonance peak will actually decrease. ,
1.0 for." decrease" for each 0.25 for reasons why Ref: LicensingInfoManual,Vol.I,p.1-40,41,j2
.h 1
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3 DAVIS BESSE September 24, 1985
- 1. 'f How does the boron concentration affect the accuracy of criticality estimates provided by a 1/M plot? Explain why. (2.0)
ANSWER 1.5 The greater the boron concentration, the poorer the 1/M plot criticality estimate. The distant placement of the detectors requires a relatively large fast neutron flux to provide sufficient thermal neutrons to the detectors to show K,ff for the core.
This is because the reactor reflector contains borated water which prevents thu.nal neutrons from exiting the reactor to reach the detectors. When criticality is imminent the fast neutrcn flux has increased enough to provide a true picture of conditions in the core to the detectors.
The greater boron concentration, the less thermal neutrons reach the detectors.
1.25 answer /.75 reason Ref: Licensing Info Manual, Vol. I, p. I-51, 53 1.6 TRUE or FALSE. The peak value of Samarium following a trip from100%Towerisexactlytwicethepeakvaluefollowinga trip from 50% power. (0.75)
ANSWER 1.6 TME /AL.56 - 3 e.e. 6lh43 4., , m m -c .
Ref: Licensing Info Manual, Vol. I, p. I-69 1.7 TRUE or FALSE. If the ratio of thermal flux at some posi-tion to the average thermal flux in the core changes by a factor of 2 the rod worth at that position will change by a factor of 2. (0.75)
ANSWER 1.7 FALSE. Rod Worth = AL/K (FLUX / FLUX-AVG)*
Reason not needed.
Ref: Licensing Info Manual, Vol. I, p. I-71
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4 DAVIS BESSE September 24, 1985 1.8 The operator is throttling the flow rate of a D.H. pump.
If cavitation is detected at the flow control valve, should flow be increased or decreased to stop the cavitation.
Explain. (2.0)~
ANSWER 1.8 Increase the flow. Throttling causes localized velocity to go up, localized pressure drops allowing flashing or cavitation.
1.0 answer / 1.0 reason Ref: PP1101.01.5, p. 38 1.9 General limits and precautions state:
Before initiating cooling water flow on either side of heat exchangers or coolers in a system: The cooler, all con-necting piping and components shall be filled and vented at reduced flow rates (preferably gravity flow). Why? (1.0)
ANSWER 1.9 This precaution is necessary to prevent impact or water hammer forces on tubes and baffles.
Ref: PP1101.01.1, p. 41 1.10 Quadrant Power Tilt (QPT) values may be substantially higher than normal during a three RCP start. Explain why? ^ (1.0)
ANSWER ,
1.10 Large Delta Tc's Ref: PP1102.02.21, p. 40
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5 DAVIS BESSE
. . September 24, 1985
, 1.11 Fill in the blank: The full effect of an APSR move will not be seen until approximately 7 hours after a move. (1.0)
- a. 2 to 4
- b. 6 to 8
- c. 12 to 16
- d. 20 to 24
- ANSWER 1.11 b.
^
Ref: PP1102.14.16 1.12 During an RCS natural circulation cooldown, why is it important to control the pressurizer level at a steady or slightly increasing trend? (2.25)
ANSWER 1.12 To prevent any outsurge of hot pressurizer water into the hot leg where it could flash to steam and cause a loss of natural circulation.
Ref: PP1102.10.9. p. 37 1.13 Fill in the blank: When the RCPs are stopped, coolant circulation in the head region of the reactor vessel ceases.
The reactor head will 7 losses to the containment atmosphere.
- a. not cooldown at all by
- b. cooldown at 1.5'F/hr by
- c. cooldown at 30'F/hr by
- d. cooldown at any rate the rest of the RCS does by (1.0)
ANSWER 1.13 b.
Ref: PP1'02.10.13 p. 52
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' ~
6 DAVIS BESSE ,
September 24, 1985 1.14 -Why doesn't the temperature of the steam leaving the OTSG exactly parallel T-hot as reactor power increases from 25 to 1 M 7 (1.25)
. ANSWER 1.14 The superheat' region length decreases, requiring a higher.
delta-T for the same heat transfer. Therefore, steam tem-perature peaks at about 88% power (up till then it parallels T-h well), then dips slightly to about 595'F at 100% power.
p Ref: Lidensing Info Manual, Vol. I, p. 11-35 "
~
. 1.15 A venturi is used to mix foam and water of the Subsurface Foam Injection System in the Fire Protection System. Explain the principle of operation of a venturi as it applies to this system (i.e., how are the foam and water automatically mixed
't in the_ correct proportion). (1.5)
ANSWER 1.15. The operating head is constructed internally in the form of i
a venturi with a siphon tube connected to the low pressure j area of the venturi and extending to the bottom of the tank.
Water under pressure passes through the operating head where
~part of of it is diverted into the tank to pressurize the 4 foam liquid inside. This forces the foam liquid up the siphon tube and into the low pressure area of the venturi, where
'it joins in the proper proportion with the water flowing to
. .the foam maker.
i Ref: Licensing Info Manual, Vol. 2, p.11-334 1.16 The limitations and precautions section of System Procedure SP 1104.02 (Makeup and Purification System) instructs the i operator to "whenever possible, minimize the number of times the letdown system is isolated." Why is this precaution i- included? (1.0)
ANSWER [
l 1.16 There have been numerous failures of heliflow-type letdown
~
coolers at other B&W plants, believed to be caused by thermal stress.
Ref: SP1104.02, Temporary Modif. Request, 2.18 i
i i
l
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7 DAVIS BESSE September 24, 1935 1.17 K,ff is .99. h the shutdown margin:
- a. .1%
b.- .99%
- c. -1.01%
- d. 10% (0.75)
ANSWER 1.17 c. .SOM = 1-K,ff/K,ff x 100%
= 1 .99/.99 x 100% = 1.0101%
Ref: Equation Sheet / General Reactor Theory 1.18 State whether each of the following statements is TRUE W LSE:
- a. If the reactor period is cut in half, startup rate will be doubled. (0.75)
- b. It will take the same amount of time to increase power from 20% to 40% as it will to go from 40% to 60% if the startup rate is constant. (0.75) l ANSWER 1.18 a. TRUE ,
Ref: Formula Sheet / General Reactor Theory
- b. FALSE - change in power must be logarithmic not linear to stay on constant SUR. At constant SUR, it takes less time to go from 40 to 60% than it does to go from 20 to 40% (reason not required).
Ref: Formula Sheet / General Reactor Theory
- End of Category 1 -
c 8 9 *
. 4 DAVIS BESSE
,- September 24, 1985
.- .- ,1
'2.0 ; PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS (25 Points):
2.1 .WhJ is it not possible to operate the SFP pumps'when cooling the SFP with the DH pumps? ,
(1.0)
ANSWER',
- 9 ,
s
,,2,K,p?foperatedsim01taneously,thesuctionpressureaftheSFP' 4
- .- ump would drop below the NPSH required and the SFP p' ump would cavitate. ,
m .
Q /; Ref:j SP1104.06.8, p. 3.
n .
2.2 . List the normal operation loads off the service water pump
.for: (2.7)
I
- a. Primary Side (3-loads)
- b. Secondary Side (6 loads) <
' ANSWER
' 2. 2 a. Durino normal operation one Service Water Pump (Primary
- b. Side) provides water to one CCW Heat Exchanger and two
'\, Containment Air. Coolers. This pump is also lined up to one 3 Control Room Emergency Condenser Unit and ECCS Room Cooler Coils with their associated motor operated outlet valves on temperature control (normally closed). ,
? b. The other' Service Water Pump (Secondary Side) provides DT water to th'e TPCW Heat Exchangers, Water Jet Exhausters of the Main Deaerators Auxiliary Boiler Blowdown Mixing
,,_ *. h Condenser 1-1 Steam Vent Mix Condenser 1-1. Service Water:
L,a - Supply tci Backwash Receiving Tank Sump Pump Discharge, ECCS
{ Room Cooler Coils and one other Containment Air Cooler, f
.- ~ .3 pts each (3'of 4 for a. + 6 of 7 for b.)
- Ref: SP1104.11.13, p.1
'2.3 Describe two (2) pifnt conditions which might require the operation of.two CCW pumps. (2.0)
,,x ANSW{R ,
-w ,
2.3 1. The station is undergoing a reactor shutdown and cooldown.
p .*,'
w% 2. Operating both Diesel Generators at the same time or operating
the Diesel Generator cooled by the Essential Loop opposite that which is already operating.
' Ref: ' SP1104.12.8, p. 13 ~
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.+ ,
t
)1 v , s3 t ,
y
9 DAVIS BESSE September 24, 1985 2.4 WhJ are the Clean Waste Receiver Tanks (CWRTs) recirculated through the Degasifier? (1.5)
ANSWER er Q non.edsee,iMr.4 o 2.4 1. Remove 20 ,to reduce CRUD and radiation levels. (1.fpt)
- 2. Allow decay of noble gas. (.5 pt)
NOTE: Full credit if just answer #1 given.
Ref: SP1104.29.7, p. 11 2.5 What is the purpose of the Containment Recirculation System? (0.8)
ANSWER 2.5 The Containment Recirculation System is designed to draw from areas of potentially high hydrogen concentration in the Containment dome and discharge to lower sections of the Containment vessel to provide a more uniform dispersion of hydrogen throughout the Containment vessel following a loss of coolant accident.
Ref: SP1104.54.4, p. 1 2.6 The capacity of the Startup Feed Pump is sufficient to provide flow up to: (Select one.) (1.0) a) 1% power b) 74 MLB/hr c) 5% power d) 240 MW thermal power ANSWER 2.6 a) ,
Ref: Main Feedwater System, SP1106.07, p. 2
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E 10 DAVIS BESSE
. . September 24, 1985 2.7 If an SFRCS trip occurs, the. Steam Generator level will be controlled at ? inches on the Startup Range. If an SFRCS and an SFAS level 2 trip is present, the Steam Generator level will be controlled at ? inches on the Startup Range. (1.0)
ANSWE_R 2.7 46, 124
Reference:
Auxiliary Feedwater System, SP1106.06, p. 3 2.8 What three (3) sources of water can supply the Auxiliary G water pumps? (1.5)
ANSWER 2.8 Condensate storage tanks Service water system Fire protection system
Reference:
Auxiliary Feedwater System, SP1106.06, p. 1 2.9 State ten (10) of the fourteen (14) malfunctions, faults, or actions that will cause a turbine trip. (2.0)
ANSWER 2.9 a) Generator faults b) Main and auxiliary transformer faults c) Low condenser vacuum d) Excessive thrust bearing wear e) Low bearing oil pressure f) Turbine overspeed g) Turbine protection for generator motoring h) Reactor trip i) Manual trip-j) Low hydraulic oil trip k) Prolonged loss of generator stator coolant
- 1) High moisture separator level m) Backup overspeed n) SFRCS actuation.
Reference:
Turbine Operating Procedure, SP1106.01
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11 DAVIS BESSE
. - September 24, 1985 2.10 According to the Turbine Operating Procedure, SP1106.01, the turbine control system and the turbine bypass valves are expected to permit a trip from a maximum of ?
load without safety valve actuation. (Select one.) (1.0)
- a. 20%
- b. 40%
- c. 60%
- d. 80%
. ANSWER 2.10 b)
Reference:
Turbine Operating Procedure, SP1106.01, p. 2 2.11 What purpose does the back pressure control valve, CD 2796, in the condensate pump discharge line serve? (1.0)
ANSWER 2.11 It protects against pump runout when starting the first pump or when operating with only one pump by maintaining a minimum pressure in the discharge line.
Reference:
Condensate System, SP1106.10, p. 2 2.12 If two condensate pumps are capable of handling full steam generator feed flow under full power conditions, wp are three pumps normally run to maintain 100% power? (1.5)
ANSWER 2.12 Three condensate pumps are required to handle the cascading of drains back to the condenser from one high pressure heater '
train or one high pressure plus one low pressure train at turbine full power. Three pumps are also required at full load if both LP heater drain pumps are out of service.
Reference:
Condensate System, SP1106.16, p. 1
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12 DAVIS BESSE September 24, 1985 2.13 State the purpose of the Main Steam Isolation Valves and the Main Steam Non-Return Valves. (1.5)
ANSWER 2.13 The MSIVs limit an excess reactor coolant system cooldown rate and the resultant positive reactivity insertion follow-ing a main steam line break downstream of the valve.
The MSN-RVs prevent reverse flow of steam out a rupture upstream of their position.
Reference:
Main Steam System OperaLing Procedure, SP1106.24, p. 2 2.14 Draw a basic one line diagram of the 4160V system from the W and "B" bus to the "C1" and "D1" bus. Include the diesel generators and major breakers in your drawing. You do not need to show electrical loads. (3.0)
ANSWER 2.14 See attachment.
Reference:
4160V System Switching Procedure, SP1107.05, Attachment 1 2.15 Describe what happens when a diesel generator operating at full speed receives a stop signal. (1.5)
ANSWER 2.15 The idle stop circuitry will energize the hydraulic governor speed control motor and drive it to its low speed stop of 400 rpm. The diesel will continue to idle at this speed for approximately 10 minutes and will then automatically shutdown.
Reference:
Diesel Generator Operating Procedure, SP1107.11, p. 8 2.10 TRUE or FALSE. The diesel generators are not large enough to carry both a MU pump and an LPI pump during a LOCA coincident with a loss of power to essential buses. (0.5)
ANSWER 2.16 TRUE
Reference:
Emergency Procedure EP1202.01, p. 28
-Category 2 Continued on Next Page-
4160V SYSTEM SIMPLIFIED ONE LINE DIAGRAft .
~
i
- BUS B BUS A N B BD NA X M BD XFIS AC i WW *
- Un
- i A BD D2 A AC C2
)
d 8
DIESEL BUS D2 905 C2 DIESEL n GEIIER TOR 2 GENERATOR I
$ Start-up Feeduater Pump Condesaste Pump 1
$ -< condensate Pump 2 Condensate Pump 3 -<
l Aug. Boiler Forced Draft Fan Cooling Tower Make-up Pump 1
- N Coq (ing Tower Make-up Pump 2 Cooling Tower Pump I l m- Hester Drain Pump 2 Cooling Water Pump 3 n Suitchyear Feeder 2 Ileater Drain Pump 1 W
- E Lighting Substa. Trans. DE5 Suitchyard Feeder 1
" Cooling Water Pump 2 Lighting Substa. Trans. CF5 ,
@ Ser. Bldg. Substa. Trans. DF6 Bachap Service Water Pump I -
g PPF; via DSC205 E . . .
- = ,
a y A AC DI A DI 01 A Dl'80 A Cl 10 A BD Cl un ,
a a 3= a4lACl10 +o y
o, M
E BUS Di BUS Cl l ~
8 ij % $ Nigh Pressure Injection Pump 2 Nigh Pressure Injection Pump 1 *
' o 4
. Decay Neat Pump 2 Decay Neat Pump I y
.. Censponent Cooling Pump 2 Component Cooling Pump 1
- j Service Water Pump 2 Service Water Pump 1 Makeup Pump 2 Makeup Pump I vi o l l Transformer DFl-1 Transformer CEl-l 4$ '
1 Transformer DFI-2 -
Traa='ar=*r cEi-2 gG Di Feed to Service Water Pump 3 El Feed to Service Wats r Pimmy *l a Di Feed to Component Cooling Pump 3 Cl Feed to componeut Cooling Pump 3
{h
=
' ~
l'4 DAVIS BESSE September 24, 1985
.2.17 Describe how to take local control of a SU FW valve. (1.5)
ANSWER 2.17 To take local manual control of the SU FW valve, free-wheel the handwheel until the hole in the shaft sleeve lines up with the hole in the stem, insert the pin, and open the diaphragm equilizing valve. The valve can then be positioned with the handwheel.
Reference:
Emergency Procedure EP1202.01, p. 56
- End of Category 2 -
~ e --- +-~ - ew -w -nw am.,- -, -,, , - ,, y
15 DAVIS BESSE
- September 24, 1985 3.0 INSTRUMENTS AND CONTROLS (25 Points) 3.1 When pressurizer heater banks 2, 3, or 4 control switches are placed in "0N", will they respond to either the pressure control signals or the low level interlock? (1.0)
ANSWER 3.1 No Ref: SP1103.05.17, p. 2 3.2 A LOCA is occurring. HPI pumps are keeping up with the leak, and RCS pressure has stabilized around 1500 psi (55'F saturation margin). As reactor operator you note that core flood tank pressure is the same as before, but that level has increased 4 inches. Explain why. (1.0)
ANSWER 3.2 Elevated refer- leg temperature; lack of pressure change means r .al level same as before.
Ref: SP1104.01.13 3.3 TRUE or FALSE. Pushing the stop button locally or using pistol grips in the Control Room or at the Breaker will NOT stop a Circ Water Pump if the Discharge Valve is NOT---
tut 1y closed first. (1.0)
ANSWER 3.3 TRUE Ref: SP1104.09.9, p. 2 l
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16 DAVIS BESSE September 24, 1985
- 3. 4 - Indicate each CCW pump trip below which will NOT occur if an unblocked SA signal for that pump exists. (1.0)
- a. CCW outlet temperature on the operating heat exchanger is greater than 125'F.
- b. Pump outlet flow of less than 1000 gpm.
- c. Bus Fault Lockout
- d. Ground Fault
- e. Overcurrent ANSWER 3.4 a,b Ref: -SP1104.12.14, p. 4 3.5 Limits and precautions for the Turbine Plant Cooling Water System (TPCWS) warn that derivative action con-troller manual setpoints must be changed very carefully.
Why? (1.0)
_ ANSWER 3.5 To prevent very rapid control valve opening and closing; this is because the rate of setpoint change affects the rate of valve operation.
Ref: SP1104.39.9, p. 3 3.6 What are the reactor trip setpoints for the following:
- a. RC high temperature - *F (0.5)
- b. RC high pressure - psig (0.5)
- c. RC low pressure - psig (0.5)
- d. High flux (three pumps) - % (0.5)
ANSWER 3.6 a. 618'F
- b. 2300 psig
- c. 1983.8 psig
- d. 78.85%
Ref: SP1105.02.7, p. 4
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17 DAVIS BESSE b September 24, 1985 .
3.7 'When energizing ICS cabinets, which power source is
- turned aon first: AC or DC? (1.0)
ANSWER' 3.7. AC-
_. Ref: - SP1105.04.9, p.1 3.8 a. List the four (4) requirements for Rapid Feedwater Re3uction (RFR) (1.0) b.. Describe how the feedwater system will respond to RFR. (1.0).
' ANSWER 3.8 a. 1. At least one MFP not tripped.
-2. All control valves in auto.
- 3. RFR defeat switch-in "0N" position.
L4. Reactor trip.
- b. Proper actuation of RFR.is indicated by both main FW valves going shut and both startup FW valves closing to the point that allows OTSG level to decrease until low level-limits are reached. The MFPs will target their speed to approximately 4600 RPM as indicated on
-the control room panel. .
The RFR will remain turned on' (Activated) for approxi-mately 2.5 minutes or until low level limits (both loops) have been reached, whichever occurs first.
NOTE: 'If low level limits have been reached on one loop and'not-the other while RFR is still activated, the loop reaching low level. limits will go on level control and.the other will remain on RFR until low level limits have been obtained or'2.5 minutes have expired at which time it will go on level control.
Ref: SP1105.04.9. p. 3 & 4
+
I
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t t r- = $ y s y w- -,- . .,gr , ,,.w---, .-..--g w- -.yw-,-,.,,. . . . .. ,, , , ~ , , - , y,.. e.,_,., ..-,., ,--.-,..,y -- --m..
18 . DAVIS BESSE Ssptember 24, 1985
- 3.9 Which of the following statements is TRU" regarding the.
Fon Ruclear Instrumentation.(NNI) System . iescribed in the NNI Operating Procedure. SP1105.06. (Se16ct one.)- (1.0)
- a. 'Only~the Y NNI cabinets are required for normal
~
-operation.
b; -The-Y NNI cabinets contain both redundant and non-redundant instrumentation.
- c. The X NNI cabinets contain both redundant and ncn- .
redundant instrumentation.
- d. . Only the X NNI cabinets are required for normal operation.
ANSWER-
. 3.9 c.
Ref: NNI Operating Procedure SP1105.06, p.1
- 3.10- The RCP Seal Injection Flow hand / auto station: (Select one.) (1.0) a.' . indicates flow in "gpm when in " Meas' Var" and demand (0-100%) to MU 19 when in "Pos".
b..Lindicates demand (0-100%) to MU 19 when in " Meas Var"
.and "gpm" when in "Pos".
- c. indicates demand (0-100%) to MU 19 when in both " Meas Var" and "Pos".- -
Id. . indicates "gpm" when in both " Meas Var" and "Pos".
- ANSWER 3.10 c.
Ref:. NNI Operating Procedure, SP1105.06, p. 6 3.11 Briefly describe the function of the T selector (HS-RC7)
"V9
'if flow is. lost in both loops. - (1.1) i ANSWER 3.11 If both loop flow signals are low the operator may manually select'any of the three signals.
L Ref: NNI Operating Procedure, SP1105.06, p. 7 l
i e
m
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- y. - e , + , . , . . + - - . , - _ .-,_..,,~,y
, - . , . . + . ,,.,,y ,.,n . , , . . - ~ ,,.---.,y.,
1.3 DAVIS BESSE September 24, 1985 3.12 TRUE or FALSE. A majority of the control room indicators and recorders are powered from NNI Y. (0.5)
ANSWER 3.12 FALSE Ref: NNI Operating Procedure, SP1105.06, p. 7 3.13 Briefly state two major reasons why the selectable NNI hand stations are positioned in accordance with list "A" of the NNI Operating Procedure, SP1105.06. (2.0)
ANSWER.
3.13 1. To maximize NNI-X dependence.
- 2. The abnormal procedure (AB1203.41) for loss of NNI power assumes an initial lineup in accordance with list "A" of SP1105.06.
Ref: NNI Operating Procedure, SP1105.06, p. 7 Loss of NNI Power, AB1203.41, p. 19 3.14 The Victoreen control room radiation instrumentation reading out in CPM has a bottom scale. The units of that bottom scale are: (Select one.) (1.0)
- a. in micro-curies per milliliter b.- in CPS
- c. in voltage (used for testing only)
- d. in mr/hr equivalent ANSWER 3.14 c.
Ref: Process and Area Radiation System, SP1105.07, p. 19 3.15 On the front of each Victoreen control room module is a green " FAIL" lamp. Under normal operating conditions what should the status of this light be? (1.0)
ANSWER 3.15 On.-
Ref: Process and Area Radiation Systems, SP1105.07, p. 20
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20 -
DAVIS BESSE
, , September 24, 1985 3.16 Which of the following process radiation monitors will per-form automatic interlock or control functions upon actuation of a HIGH alarm? (There may be more than one.) (1.8)
- a. Reactor Coolant Purification System failed fuel detector (RE 1998).
-b. Clean Radwaste Channel RE 1770A and/or RE 17708.
- c. Miscellaneous Radmaste Channel RE 1878A and/or RE 1878B.
d.- Radioactive Waste Gas Discharge RE 1822A and/or RE 18228.
- e. Component Cooling Water Channels RE 1412 and RE 1413.
-f. Service Water Discharge Header RE 8432.
- g. Station Effluent RE 8433.
- h. Penetration Rooms. Purge System RE 5052 A, B and C.
- i. Control Room Emergency Ventilation System RE 5327 A, B, C and RE 5328 A, B and C.
ANSWER 3.16 b,c,d,e,h Ref: Process Area Radiation System, SP1105.07, p. 21 1
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21 DAVIS BESSE
.- - September 24, 1985 3.17 State the four (4) inputs to the Steam and Feedwater Rupture Control System. (2.0)
ANSWER
- 1) Steam pressure
- 2) Steam /feedwaterAP
'3) Steam generator level
- 4) RCP pump power Ref: Steam and Feedwater Rupture Control System Operating Procedure SP1105.16, p. 2 3.18 Briefly explain why the reactor demand station should be placed in " HAND" if the Rod Control Panel is placed in
" MANUAL'!. (1.5)
ANSWER 3.18 This allows reactor demand to track actual neutron power (tieback circuit) to limit upsets when returning to AUTO.
Ref: Control Rod System Operating Procedure SP1105.09, p. 6 3.19 TRUE or FALSE. With CRDM breakers A, B, C, and D all shut, tripping open breaker D will result in a trip of breakers A, B, and C. (0.5)
ANSWER 3.19 FALSE Ref: Control Rod System Operating Procedure SP1105.09, p. 3 3.20 TRUE or FALSE. According to the Precautions and Limitation
-Section of the Control Rod System Operating Procedure, Group 8 may be moved at the same time other groups are moving in AUTO. (0.5)
ANSWER 3.20 TRUE Ref: Control Rod System Operating Procedure SP1105.09, p. 5
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DAVIS BESSE September 24, 1985 3.21; What bias (psig) is supplied to the turbine bypass valves for the following situations?
F
- a. Reactor trip (0.2) b.. Turbine Trip (No Reactor Trip) (0.2)
- c. Unit Load Demand >15% (0.2)
. ANSWER 3.21 a. 145 psig
- b. O psig
- c. 50 psig Ref: Main Steam System Operating Procedure, SP1106.24, p. 3 3.22 TRUE or FALSE. The Main Steam Line RAD monitors will NUT accurately respond in analyze mode with the reactor shutdown. (0.5)
ANSWER 3.22 TRUE Ref: Emergency Procedure EP1202.01, p. 2
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23 DAVIS BESSE
. . September 24, 1985
4.0 PROCEDURES
NORMAL, ABNORMAL, EMERGENCY, AND RADIOLOGICAL CONTROL- (25 Points) 4.1 'The Nuclear Steam Supply System Limits and Precautions Procedure (PP1101.01) lists nine (9) circumstances requiring
-venting of the Reactor Coolant System. State two (2) of these nine (9) circumstances. (2.0)
ANSWER 4.1 Any two of the following:
A. Following complete. fill or refill from a partially filled condition of the RC System.
B. Following initial operation of reactor coolant pumps after any fill (5 minutes RCP operation is minimum).
C. Following loss of level in the pressurizer below 0 inches with nitrogen in the pressurizer.
D. If the RC pressure is below the minimum pressure required to keep dissolved gases in solution.
E. Following a loss of pressure indication during which it cannot be shown that the RC pressure has not fallen below the minimum allowable.
F. Following draining and refill of core flood lines and/or loss of level in either Core Flood Tank.
G. Following draining and filling of any piping system connected to the reactor which has unvented high points communicating with the reactor coolant system.
H. Following loss of level in the makeup tank unless valved off during drain and refill.
I. Following operation of the pressurizer spray with nitrogen
,y in the pressurizer.
Ref: Nuclear Steam Supply System Limits and Precautions PP1101.01, p. 4
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24 DAVIS BESSE September 24, 1985 4.2 If both seal injection and CCW are lost; within what maximum time must RCPs be tripped? (1.0)
- a. 30 seconds
- b. 90 seconds
- c. 4.5 minutes
- d. no time limit ANSWER 4.2 b. 90 seconds Ref: SP1103.06.9, p. 7 4.3 A Core Flood (CF) line breaks downstream of the LPI tie-in: This renders one LPI string inoperable. The Diesel supplying the second LPI pump fails. The operator opens the motor operated LPI crossover valve (DH 830 or DH 831),
but forgets to close the suction valve on the disabled pump.
What will happen? (2.0)
ANSWER 4.3 Pressurize pump suct;on piping and lift emergency sump relief valve.
Ref: SP1104.04.19, p. 4 4.4 Containment vessel pressure increases to 18.4 psi.
The Containment Spray Automatic Control Valves do not operate correctly, and have to be opened manually from panel C-5716.
Assuming containment pressure increases to above 38.4 psia, what must be done with the control valves when suction transfer from the BWST to the Emergency Sump is made? (1.0)
ANSWER 4.4 The control valvas will have to be manually throttled.
Ref: SP1104.05.15, p. 2
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25 DAVIS BESSE
. . September 24, 1985 4.5 For each of the following, state under what conditions that safety equipment's initial position or state may be overridden.
.a. Containment Gaseous and Particulate Monitors Sample Line Isolation Valves. (0.5)
- b. Reactor Coolant Pump (RCP) Seal Injection and Return Isolation Valves. (1.0)
- c. Stopping of High Pressure Injection (EP1202.01, specific rule #2). (1.0)
ANSWER 4.5 a. The associated sample line isolation valves may be opened as soon as it is necessary to sample the CV.
Eb. The RCP Seal Injection and Return Isolation Valves may be overridden to the open position when RCS pressure is greater than 400 psig.
- c. MU/HPI Termination HPI may be stopped if the LIP system has been started and flow has been 1000 gpm/line for 20 minutes.
If core cooling is NOT being provided by MU/HPI cooling (at least one SG is available as a heat sink) HPI may be stopped and normal MU flow established when adequate subcooling margin has been restored and pressurizer level is 100" and increasing.
Ref: SP1105.03.9, p. 3&4 and Emergency Procedure EP1202.01, p. 141 4.6 a) At what level is the OTSG to be considered dry? (0.5) b) What action is required to recover level and why? (2.0) i ANSWER i
i 4.61 a) 8 inches b) Feed with auxiliary feed through the upper nozzles. (1.5 pts)
To minimize thermal shock to the lower tube sheet. (0.5 pts)
Ref: Main Feedwater System, SP1106.07, p. 8
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DAVIS BESSE September 24, 1985 4.7 TRUE or. FALSE. The diesel generator power factor must be maintained at 0.8 to ensure proper mechanical loading. (0.5)
' ANSWER 4.7 FALSE Ref: Diesel Generator Operating Procedure SP1107.11, p. 15 4.8 TRUE or FALSE. Lubricating oil may be added to.the diesel engine while it is running. (0,5)
ANSWER 4.8 TRUE
.Ref: Diesel Generator Operating Procedure, SP1107.11, p. 11 4.9 TRUE or FALSE. According to the Diesel Generator Operating PFo"cedure 7 1107.11), the diesel engine may be operated at idle speed of 400 rpm from the idle start /stop control panel for an unlimited period of time. (0.5)
ANSWER 4.9 TRUE Ref:- Diesel Generator Operating Procedure, SP1107.11, p.11
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27 DAVIS BESSE
. . September 24, 1985 4.10 List the five (5) automatic actions that should occur as a result of a Reactor Trip from high power. (2.5)
ANSWER 4.10 1. All control rods drop to the bottom, in-limit lights come on.
- 2. Main Turbine trips, all turbine MSVs, CVs, IVs, and ISVs close.
- 3. TBV setpoint transfers to 1015 psig individual S/G. -
- 4. Rapid Feedwater Reduction actuates to increase MFP speed and target positions the main feedwater control valves and startup feedwater control valves.
- 5. The generator field breaker and generator breakers trip. The 13.8 KV buses A and B fast dead transfer to the startup transformers per the reserve source selector switch.
Ref: Emergency Procedure EP1202.01, p. 3 4.11 After a reactor trip, off-site electrical power is lost.
The diesel supplying the bus with the previously running makeup pump fails to auto start. What must be done prior to attempting a manual start of that diesel to power up the bus? (1.5)
ANSWER 4.11 Either trip the MVP breaker or close Mul9 (seal injection valve).
Ref: Emergency Procedure EP1202.01, p. 10
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28 DAVIS BESSE
<'
- September 24, 1985 4.12 a. With initial switch lineup on X indicators, loss of X AC will cause loss of the Pressurizer low level heater interlock and the MU Tank low level transfer interlock. How can these interlocks be regained? (1.0)
- b. Will this action regain pressurizer and MV tank level indication? (0.5)
ANSWER 4.12 a. Transferring Pressurizer level and temperature selector switches and MU Tank level switch to Y.
- b. No Ref: Emergency Procedure EP1202.01, p. 14 4.13 Briefly state two (2) sources of boron for emergency boration. (1.0)
ANSWER 4.'13 Shift MVP suction to the BWST or Boric acid addition to the MUT.
Ref: Emergency Procedure EP1202.10, p. 20 4.14 What action is required by Emergency Procedure EP1202.01 IT TW flaw will not decrease to a SG with increasing level? (1.0)
ANSWER 4.14 Trip both MFPTs.
Ref: - Emergency Procedure EP1202.01, p. 23, 24
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- 29 DAVIS BESSE o6*- September 24, 1985 4.15 What two (2) conditions, as specified in Emergency Procedure EPTf02.01, constitute adequate primary to secondary heat transfer? (2.0)
ANSWER 4.15 1. Plant is stable in or approaching the post trip target box, OR
- 2. Plant is stable outside the post trip target box, AND Tc and SG pressure are coupled, indicating heat transfer to SG. . Coupled means Tc and TSAT SG are about the same value.
Ref: Emergency Procedure EP1202.01, p. 34 A.16 What immediate operator action is required if the pressurizer spray valve sticks open and the spray line isolation valve will not shut (assume 100% FP)? (1.5)
ANSWER 4.16 Reduce power to 72% and stop RCP 1-2-2 and begin a plant shutdown.
Ref: Pressurizer System Abnormal Procedure AB1203.19, p. 4 4.17 What is the meaning of " Bump an RC pump"? (1.0)
ANSWER 4.17 Start the pump, observe as the starting current drops off, allow it to run for 10 seconds, and then stop it.
Ref: Emergency Procedure EP1202.01, p. 64 4.18 TRUE or FALSE. The purpose of the Control Room Evacuation Procedure AET203.12, is to bring the plant to a cold shutdown condition using only controls outside of the control room. (0.5)
ANSWER 4.18 FALSE
Reference:
Control Room Evacuation Procedure AB1203.12, p. 9
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