ML20126L249
| ML20126L249 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 07/26/1985 |
| From: | Burdick T, Higgins R, Mcmillen J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20126L236 | List: |
| References | |
| 50-255-OL-85-01, 50-255-OL-85-1, NUDOCS 8507310130 | |
| Download: ML20126L249 (149) | |
Text
p U.S. NUCLEAR REGULATORY COMMISSION l
l REGION Ill Report No. 50-255/0L-85-01 Docket No. 50-255 License No. DPR-20 l
Licensee: Consumers Power Company Rt. 2, Box 154 Covert, MI 49043 Facility Name: Palisades Examination Administered At: Palisades Generating Station and Midland Training Center Examination Conducted: July 3, 10, and 11, 1985 7/Q([T5' Examiner (s): R L H Date flhlh \\
y_y-ff~
}T.M.Burdick Date i
'7M/df Approved By:
J.
. Mc Mi len, f
Operating Licensing Section Date Examination Sumary The written examinations were administered on July 3, 1985_(Report No. 50-255/0L-85-01)
The simulator examinations were administered on July 10, 1985. The plant walk-through examinations were administered on July 11, 1985. Written, simulator and plant walk-through replacement examinations were administered to 2 instructor certification candidates. Written requalification examinations were administered to 5 Senior Reactor Operators and 3 Reactor Operators. The written SR0 requalification examination was identical to the SR0 replacement examination administered to the two instructors except for Section 5, which was developed by the licensee. The written R0 requalification examination was similar to an NRC replacement examination, except for Section 1, which was developed by the licensee.
Results: Both instructors passed all three portions of the replacement examination. Four Senior Reactor Operators passed the written requalification examination.
8507310130 8507P6 PDR ADocn 05000255 G
I REPORT DETAILS 1
1.
Examiners j
R. L. Higgins, Region III, Chief Examiner T. M. Burdick, Region III 2.
Examination Review Meeting On July 3, 1985, at the conclusion of the written examination, the examiners met with the following facility personnel to review the SR0 and R0 examinations:
L. Schmiedeknecht, Simulator Instructor J. Watson, Nuclear Instructor II M. King, Shift Engineer S. Wawro, Shift Supervisor N. Pope, Nuclear Operator Training Consultant D. Turcott, Nuclear Operator Training Consultant R. Heimsath, Simulator Supervisor j
The following facility comments and NRC responses were made concerning l
the R0 examination:
QUESTION 2.19 Which one of the following is most accurate regarding the fuel handling system?
a.
The refueling machine interlocks include an upmotion hoist stop if the local area monitor exceeds a predetermined radiation setpoint.
b.
In order to receive a new fuel bundle in the new fuel elevator the interlock for raising the elevator to the surface of the pool must be overridden.
c.
Withdrawal, insertion and transfer procedures for control rods are identical to those for fuel except the mast must be rotated 180 degrees with respect to the angular position used for handling fuel
- bundles, i
i d.
Fuel transfer interlocks require that both tilt machines be in the horizontal position to perform a transfer and transfer travel will i
be stopped if cable tension exceeds the high limit.
FACILITY COMMENT:
i It ap] ears that both B & D could be correct. Along with the key answer, j
Attaciment 1 should be considered.
I f
l 2
I
Reference:
Attachment 1 Lesson Plan Module 29, Refueling System and Equipment, Section c, Reactor Side Fuel Handling Machine, Page 13.
NRC RESPONSE:
Agree. The answer was modified to award full credit for either response "b" or "d".
QUESTION 3.02 a.
What four types of detectors are used in the nuclear instrumentation systems?
l b.
Why are there two detectors used in each of the power range safety channels?
FACILITY COMMENT:
There are only three types of detectors utilized in the Palisades Nuclear Instrument System. The proportional detectors are not utilized.
Reference:
Attachment 2 System Lesson Note, Page 7.6-8 i
NRC RESPONSE:
Agree.
" Proportional detectors" were eliminated from the answer.
QUESTION 3.04 State the meaning of the following annunciator window conditions, a.
fast flashing b.
slow flashing FACILITY COMMENT:
The correct answer is " anytime the alarm condition has cicared either before or af ter acknowledgement."
Reference:
Attachment 3 i
SOP-40, Palisades Nuclear Plant System Operating Procedure, Annunciators, Page 3 i
NRC RESPONSE:
l I
i Agree. The answer for part "b" was modified to eliminate the phrase "before acknowledgement."
3 l
QUESTION 3.05 What does it mean to " time integrate" as described in the steam generator water level control system chapter? Why is this necessary?
FACILITY COMMENT:
This question is outside of the kncwledge requirements as listed in NUREG-1021, Section ES-202, Part 3. page 2 of 6.
The question is specific to Steam Generator Level Control, but the answer is generic in nature.
NRC RESPONSE:
Disagree.
" Time integrate" is a term describing the operating characteristic of a control system used at Palisades and is clearly within the scope of operator knowledge as enumerated in NUREG-1021.
QUESTION 3.07 a.
How is the regulation of steam pressure to the AFW pump turbine assured during a loss of instrument air?
b.
In what mode must the FIC and HIC be in to facilitate automatic AFW flow control?
c.
When is the FIC placed in the pseudo-automatic mode?
FACILITY COMMENT:
The term " pseudo-automatic" is neither used in our procedures, nor is it used as conson jargon in our Plant.
The Procedures used is ' Manual / Auto Control.'
NRC RESPONSE:
Disagree. The term " pseudo-automatic" is used several times in the reference provided by the licensee. The licensee should revise its reference material to replace inaccurate terminology with terminology actually used at the facility.
QUESTION 4.09 a.
What are the heatup AND cooldown rates for the primary coolant system AND the pressurizer?
b.
What is the minimum primary coolant system pressure for operating primary coolant pumps?
c.
What plant condition (excluding accidents) does not allow all primary coolant pumps in operation?
4
I FACILITY COMMENT FOR PART A:
The Technical Specification limits for heatup and cooldown rates (100*F/hr in the Primary Coolant System and 200*F/hr in the Pressurizer) should also be acceptable answers for this question.
Reference:
Attachment 4 Palisades Technical Specifications, Section 3.1.2, Page 3-4 NRC RESPONSE:
Agree. The answer was expanded to award full credit for the Technical Specification limits.
FACILITY COMMENT FOR PART B:
According to SOP-1, 250 psia is an acceptable answer.
Reference:
Attachment 5 50P-1 Palisades Nuclear Plant System Operating Procedure, Primary Coolant System, Page 2 NRC RESPONSE:
Agree. The answer was changed to 250 psia.
l QUESTION 4.11 l
a.
Why should the boron concentration be equalized between the shutdown 2
cooling system and the SIRW tank PRIOR to decreasing the PCS pressure below 300 psia?
b.
At what point in the draining of the primary cooling system does cavitation of the shutdown cooling system pumps become a concern?
FACILITY COMMENT:
According to 50P-1, "below the centerline of the hot leg" should also be an acceptable answer.
Reference:
Attachment 6 SOP-1, Palisades Nuclear Plant System Operating Procedure, Primary Coolant System, Page 17 NRC RESPONSE:
Agree. The answer for part "b" was ex:)anded to grant full credit for the response "below the centerline of the lot leg The following facility coments and NRC responses were made concerning the SR0 examination:
5
e j
l QUESTION 5.04b 1
When is the violation of the rod power dependent insertion limits acceptable?
l FACILITY COMMENT:
An additional / alternate answer is "during low power physics testing and CRDM exercising, but only for the duration of the test."
Reference:
Attachment 7 Technical Specifications, Section 3.10.7, Page 3-61 NRC RESPONSE:
Agree. The answer was modified to include " low power physics testing and CRDM exercising" as acceptable responses.
QUESTION 5.10 One method of introducing lithium 7 into the PCS is by charging using the chemical addition tank. Name two other ways in which lithium 7 enters the PCS.
FACILITY COMMENT:
An additional answer is "by injection cf Lithium via the Chemical and Volume Control System Chemical Addition Tank and Metering rump."
Reference:
Attachment 8 COP-1, PCS Chemical Additions for Hydrazine and Lithium, Page 1 NRC RESPONSE:
Disagree. The question required two methods besides the chemical addition tank. The answer was not changed.
QUESTION 6.01 What three trips will be defeated by the zero power mode bypass?
FACILITY COMMENT:
The answer key has three trips listed:
1.
Steam Generator Pressure 2.
Iow Primary Coolant System flow i
3.
TMLP l
k i
I 6
r-System Lesson Note #14, page 23 has the Steam Generator Pressure Trip l
listed as "A" Steam Generator Pressure or "B" Steam Generator Pressure Trip.
An acceptable answer should be any three of the following:
1.
"A" Steam Generator Pressure l
2.
"B" Steam Generator Pressure 3.
low Primary Coolant System flow l
Reference:
Attachment 9 f
System Lesson Note #14, Reactor Protective System, Page 23 1
NRC RESPONSE:
t Disagree.
"A steam generator pressure" and "8 steam generator pressure" are both " steam generator pressure" trips. The answer was not changed.
QUESTION 6.03 What will cause the incore detectors to generate a signal when the l
reactor is shutdown and subcritical?
FACILITY COMMENT:
This question is misleading in that it does not ask if the signal is measurable or not.
If the signal is measurable then the answer key is correct.
If the signal is not measurable then decay or source neutrons must be taken into account to generate a signal.
With the reactor shutdown and no other parameters stated in the question, l
decay or source neutrons will also generate a signal in the in-core detectors.
l
Reference:
Attachment 10 lesson Plan Module Prevention / Mitigation of Core Damage, Section F.4.A.11 1
NRC RESPONSE:
l Disagree. The facility reference states that detector sensitivity is low enough that no output is normally measurable when the core is shutdown, but a signal may be generated if the temperature of the incore exceeds l
600*F. The source neutron flux is extremely low, nearly a factor of one l
billion less than the full power flux, so there would absolutely be no l
signal generated by decay or source neutrons. The answer was not l
changed.
7
)
QUESTION 6.06 Name the three relief valves which discharge to the Quench Tank.
FACILITY COMMENT:
Answer key lists:
1.
letdown line relief 2.
SIT drain relief 3.
shutdown cooling relief Additionally, there are other relief valves that discharge into the quench tank. These are the PORV's and Safety Relief Valves from the Pressurizer. The answer key should reflect these additional valves.
Reference:
Attachment 11
'M-201, sheet 2, rev. 3 and sheet 3, rev. 1, Piping and Instrument Diagram, Primary Coolant System NRC RESPONSE:
Agree. The answer was modified to give credit for the PORV's and safety relief valves.
QUESTION 6.16 What is the starting sequence of the fire system pumps? Include setpoints.
FACILITY COMMENT:
There are conflicting setpoints between the answer key and the S0P-21, Section 7.1.
This section has the following setpoints:
P9A - 90 psig P9B - 80 psig P41 - 65 psig
Reference:
Attachment 12 50P-21, Palisades Nuclear Plant System Operating Procedure, Fire Protection System, Section 7.1, Page 2 NRC RESPONSE:
Agree. The answer was modified to accept either 80 or 75 psig for P98, and either 65 or 60 psig for P41. The facility should revise its reference material to make the information accurate and consistent.
QUESTION 6.20 What three conditions will cause the emergency diesel generator breaker to automatically open?
8
l FACILITY COMMENT:
There are more than three conditions which open the breaker. They are as follows:
loss of generator excitation overload engine trip generator differential relay 2400V bus transfer The question did not state under what conditions the Diesel Generator was running. The examiner could also list diesel engine trips and have the following acceptable answers:
overspeed low bearing oil pressure overcrank The 2400 V bus transfer relays (faster transfer) trip the output breaker and this breaker cannot be closed for 1.5 seconds. Again the question did not state the conditions under which the diesel was running.
Reference:
Attachment 13 Palisades Schematic Diagram, E-139, sheet 1, rev. 15 and Palisades Logic Diagram, E-17, sheet 2, rev. 8 NRC RESPONSE:
Agree. The answer was modified to accept the following responses in addition to those already listed: 2400 V bus transfer, overspeed, low bearing oil pressure and overcrank. The System Lesson Notes which describe the diesel generator, System Lesson Notes #33, do not list these four trips. The facility should update its reference material so that the material will be accurate, consistent and complete.
QUESTION 7.15b What action should be taken if the running HPSI pumps are not maintaining this minimum flow rate?
FACILITY COMMENT:
Another acceptable answer could be as follows:
"If an increase in flow is not indicated, imediately stop the pump."
Reference:
Attachment 14 SOP-3, Palisades Nuclear Plant System Operating Procedure, Safety Injection and Shutdown Cooling System, Section 7.1.1, Page 5 9
NRC RESPONSE:
Agree. The question did not stipulate the circumstances under which the HPSI pump was operating: during pump performance testing or during a loss of coolant accident. The answer was expanded to award full credit for the response: "immediately stop the pump."
QUESTION 8.22 In order to maintain PCS temperature above 325 F, 240 volt AC power panels No. I and 2 and their associated ACB breaker distribution system, located in the
, and 125 volt DC buses must be operable.
a.
auxiliary building; D10 and D20 b.
auxiliary building; No. 1 and 2 c.
switchyard; D10 and D20 d.
switchyard; No. 1 and 2 FACILITY COMMENT:
SOP-30 and Plant personnel routinely call DC buses D10 and D20 by the name of the DC Bus 1 and DC Bus 2, respectively. This would make both answers C and D correct.
Reference:
Attachment 15 l
SOP-30, Palisades Nuclear Plant System Operating Procedure, Station Power, Section 7.1.1.
Note Pages 15 and WD 950, sheet 17 1
NRC RESPONSE:
Agree. The answer was changed to award full credit for either choice "c" or "d".
QUESTION 8.29 Which of the following radioactive liquid monitors is addressed in Technical Specification Table 3.24-17 t
Steamgeneratorblowdownmonitor(RE-0707) a.
b.
Failed Fuel Monitor (RE-0202) c.
ComponentCoolingWaterMonitor(RE-0915) d.
Circulating Water Discharge Monitor (RE-1323)
FACILITY COMMENT:
RE-0202 is addressed in Technical Specifications Table 4.2.1.
Since both RE-0707 and RE-0202 (letdown) are possible choices, both should be allowed as answers.
Reference:
Attachment 16 Palisades Technical Specifications, Table 4.2.1, Item 1 1
i 10
I 1
l l
NRC RESPONSE:
i I
Agree. The question's intent was to detennine whether the examinee knew which radioactive liquid monitor was mentioned anywhere in Technical Specifications, not necessarily in Table 3.24-1.
The answer was expanded to grant full credit to choice "b".
l 3.
Exit Meeting On July 10, 1985, at the conclusion of the simulator examinations, the examiners met with the following utility personnel to discuss generic l
observations made during the simulator examinations:
f J. Onnen, Midland Training Center Supervisor R. Heimsath, Simulator Supervisor R. Simmons, Simulator Instructor L. Schmiedeknecht, Simulator Instructor The following topics were discussed:
a.
Completed Estimated Critical Position Forms corresponding to each startup initial condition need to be kept available in order to expedite startup scenarios.
b.
Checklists corresponding to each initial condition need to completed and kept on file to reduce the possibility of con'usion at the beginning of the scenario.
On July 11, 1985, at the conclusion of the plant walk-through examinations, the examiners met with the following utility and NRC personnel to discuss generic observations made during the plant walk through examinations:
J. G. Lewis, Plant Technical Director W. G. Merwin, Training Supervisor R. B. Heimsath, Simulator Supervisor D. F. Turcott, Training Consultant C. S. Kozup, Operations Superintendent A. F. Brookhouse, Plant Shif t Operations Supervisor J. R. Schepers, Plant Chemistry and Radioactive Waste Superintendent D. J. Fitzgibbons, Licensing Engineer E. R. Swanson, Senior Resident Inspector (NRC)
The following observations were made by the examiners during the course of the examinations:
l a.
Both instructor certification examinees passed their simulator and plant walk-through examinations, b.
Though the areas of the plant which have been cleaned in conjunction with a recently initiated plant cicanup program were clean, most j
l areas of the plant were in a poor state of cleanliness.
l 11 l
c.
A steam leak caused humidity and temperature to be so excessive that some of the portions of the auxiliary building could only be entered for extremely short periods of time. The humidity from this steam leak caused condensation in the Shift Supervisor's office which resulted in damage to the false ceiling.
d.
The copy of Volume 10 of the Code of Federal Regulations maintained by the Shift Supervisor's office was out of date. The current edition is the January 1, 1985 revision; the copy in the Shift Supervisor's office was revised as of January 1, 1978, e.
No procedure for shutting one Main Steam Isolation Valve was maintained in the cabinet which contained the Main Steam Isolation Valve controls, f.
The last-minute withdrawal of the only examinee taking the Reactor Operator examination caused some confusion and delay at the beginning of the written examination. Though the licensee is commended for withdrawing individuals whose prospects for passing are marginal, had the NRC been notified several days in advance, the delay and confusion which existed at the beginning of the written examination would have been avoided, g.
Only two instructor certification examinations, and no license examinations, were conducted. Had requalification examinations not been administered at the same time, the examination trip would have been inefficient use of scarco NRC examiner resources.
In the future, examination trips will not be scheduled if only two examinees will be administered examinations.
h.
The portions of the recualification examination prepared by the licensee, Section 1 anc 5, were comprehensive and relevant, but lacked in-depth questions. The questions in the licensee-prepared sections addressed the "what," but did not sufficiently sample the examinees' knowledge of the "why" or "how" of reactor theory or heat transfer.
I 12
t l
I MASTER l
U. S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION i
FACILITYt PALISADES REACTOR TYPEt PWR-CE l
j DATE ADMINISTEREDI 85/07/44-63 EXAMINER:
T CURDICl; APPLICANT!
INSTRUCTIONS TO APPLICANT!
i t
Use seperate paper for the answers.
Write answers on one side only.
l Staple question sheet on top of the answer sheets.
Points for each question are indicated in parentheses after the question. The passins grade rnquires at least 70% in each category and a final grade of et loast 80%.
Examination papers will be picked up six (6) hours after tho enanination starts.
t
% OF CATECORY
% OF APPLICANT'S CATECORY l
VALUE TOTAL SCORE VALUE CATECORY f
20 0
...I.0....'5 00 1.
PRINCIPLES OF NUCLEAR F0WER I.I..
PLANT OPERATION, THERMODYNAMICS,
(
HEAT TRANSFER AND FLUID FLOW
. bIbb... bIbb 2.
PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS I b...
Ibb 3.
INSTRUMENTS AND CONTROLO Ibb...
Ibb 4.
PROCEDURES - NORMAL, A0 NORMAL, EMERGENCY AND RADIOLOGICAL CONTROL i
100.00 100 00 TOTALS
[
...a.......
r FINAL GRADE.................%
All ucr>. done on this enas.ination is my own. I have neither 31 von nor, received sid.
APPLICANT'S SIGNATURE 1
5 I
h
1 l
1.
PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 2
~~~~i5Ek5665U55565~~UE55~TR5U5fER 5 6~fE 56~fE6U
~
1 QUESTION 1 01 (1.00)
What is an inverse evitiplication plot?
DUESTION 1.02 (1 00)
What is the definition of Shutdown Margin?
QUESTION 1 03 (2.50)
- a. What are the three reasons for establishing regulating group insortion limits? (1.5)
- b. What is the four pump :ero-power rod insertion limit? (1 0)
DUESTION 1.04 (1.00) f What is Ovadrant Power Tilt?
L QUESTION 1.05 (1 00)
What is Anial Offset?
OUESTION 1 06 (1 00)
What are the two reasons that the reactivity effect of Honon 135 is 3reater that that of samarivn 1497 QUESTION 1.07 (1.00)
What is the equilibrivni valve of Henon reactivity at 100% power?
f GUESTION 1 08 (1.00)
Nou does the concentration of Samstioni 149 change af ter a reactor trip froni pcuor?
(smses CATEGORY 01 CONTINUED ON NEXT PACE sas**)
f I
i e
r i
l 1.
PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 3
l
-~~ isiEA55isisiCi? Aisi fiAAiFEE AA5 FEUi5 FE50 t
i.
I 00ESTION 1.09 (1.00) l Why must PCS hydro 3en concentration be reduced below 5 cc/kg prior to cpening the PCS?
t GUESTION 1.10 (1 00)
What is DND7 l
l QUESTION 1.11 (2 00)
Although DND is not an observable parameter, four observable parameters are rolated to it.
Name these four parameters.
QUESTION 1.12 (2.00)
What would the pressurizer relief valves discharge temperature be if quench tank temperature is 5 psige there is a steam bubble in the pressurizer and PCS pressure ist s.
2035 pois (1.0)
~
- b. 885 psig (1.0)
DUESTION 1 13 (2 00)
If the moisture content of steam from the steam generator is excessively i
high, will the power level calculated using the heat balance be erroneously
[
high or low?
Explain.
GUESTION 1.14 (2.00)
H:w do the available NPSH and the required NPSH change as the flow rate through the pump increases?
DUESTION 1 15 (1 00)
Nate two indications of pump cavitation.
t (assau CATEGORY 01 CONTINUED ON NEXT PAGE massa) l 1
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1.
PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 4
-"isiEA667EARici! REXi isAsiffs AA6 fCGI5 fC50 QUESTION 1.16 (1.50)
Name sin indications of void formation in the PCS, other than erratic indication on the startup neutron detectors.
QUESTION 1.17 (1.00)
Tho reactor power level is 10% and increasing at.5 decades per minute.
What will the power level be in one minute?
OVESTION 1.18 (1.00)
State whether the fuel temperature coefficient becomes more negative, less negative or remains the same as the core ages.
l 00ESTION 1.19 (1.00)
What causes the embrittlement of the metal in the reactor vessel as the roactor operates?
l l
(usans END OF CATEGORY 01 mamma) l i
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2.
PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 5
QUESTION 2.01
(.50)
Which one of the following is most decorat.P?
- a. air blast breaker operation is limited to within ten seconds f ollowirig the selection of the breaker to be operaterf.
- b. 345 MV sit blast breakerse with the etaeption of 25H9 (main generator breaker), are equipped with relays to perfarm automatic reclosure.
- c. The breaker f eedback supervisory sys*,e si will send a f ollowup prieumatic signal to open or close a breaker if the breaker f 4 tis to respored to a signal after a time delay.
l
- d. 345 KV alt blast breakers contain redundant sets of kontacts to ensure continued reliable power even if one pair of corit ects are danieged.
QUESTION 2.02
(.50)
Which orie of the following is most accurate?
- a. Iricoming 4160 vac breakers can be operated from the switchgear if the brea6or mode switch is tri test.
- b. Power may be backfed throV3h th'
- sin transformer when tke turbine is out of service for an entended period if the gerierster en.fitettore circuit discorinoct links are t enioved.
- c. Automatic f ast load transf er between the startup arid station tr arisf ormer takes place where either suf f ern a f ault or the turbirie or generator trip
- d. Interlocks prevent parallel 11ng double ended 400 vac load centers through tie breakers because doing so would onceed feeder brealer trip r e t i rig s.
(esses CATECORY 02 CONTINUED UN NFXT PAGE asuss) 6
2.
PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 6
DUESTION 2.03
(.50)
Which one of the following is most accurate?
- o. The diesel generator is designed to start and be fully loaded within 20 seconds.
- b. Cooling water jacket and stator winding heaters are provided to maintain the generator in ' start readiness'.
- c. Each diesel has sufficient fuel capacity to run under worst case condi-tions for 28 hours3.240741e-4 days <br />0.00778 hours <br />4.62963e-5 weeks <br />1.0654e-5 months <br /> before fuel transfer is necessary.
- d. The diesel may be operated for 35 minutes at 2500 HW without service I
unter available if the cooling water Jacket temperature is 120 deg. or less at startup.
1 QUESTION 2.04
(.50)
Which one of the following n,ost accurately represents diesel generator i
l limitations?
- a. 3125 MW st 0.9 power factor for continuous operation.
- b. 2750 KW overload limit for two hours.
- c. 3525 HW overload limit for 1/2 hour.
- d. 3750 HW overload limit for 5 minutes.
QUESTION 2.05
(.50)
Which one of the fo110 win 3 most accurately represents diesel generator centrol?
- a. The engine governor controls the air flow to the engine thereby controlling engine speed'and load.
- b. The UNIT mode of governor control allows the diesel generator to operate isochronous.
- c. An electrical governor backs up the mechanical governor and is set at a s113htly higher speed.
- d. Modulation of air flow to the engine is governed by the speed of the turbocharger.
(sussa CATEGORY 02 CONTINUED ON NEXT PAGE manus)
2.
PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 7
GUESTION 2.06
(.50)
Which one of the followin3 is most accurate in regard to diesel generator protection?
- a. The overspeed trip will actuate if engine speed attains 990-1035 rpm for 120 seconds or more.
b.
The overcrank relay has a 35 second time delay from the initiation of c diesel start.
- c. The overspeed trip incorporates a solenoid operated plunger which overrides the governor to stop the engine.
- d. The engine lobe oil pressure trip is actuated at 40 psis following a 20 second delay after the alarm at 60 psi 3+
QUESTION 2.07
(.50)
Which one of the following is most accurate?
- s. Manual closure of the diesel generator output breaker is blocked if the synchronizing equipment is bypassed for dead bus transfer.
b.~ Automatic-closure of the diesel generator output breaker is blocked by the overcurrent and differential relays which do not override manual operation.
c.
Electrical fault relays trip the diesel generator breaker, exciter and shut off fuel to the engine.
- d. Auton.atic closure of the DG output breaker is blocked and a trip signal initiated for 15 seconds upon initiation of fast transfer.
9 1
i (xxxxx CATEGORY 02 CONTINUED ON NEXT PAGE xxxxx)
2.
PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 8
OllESTION 2.08
(.50)
Which one of the following is most accurate in regard to Containment Spray?
- a. The system consists of three pump and heat exchanger sets and all necessary piping, instruments and accessories.
b.
The system is designed so that one of the three pumps will limit the containment pressure to less than the design value following DBA.
c.
Containment spray must be cooled since the hydrazine in solution would vaporire readily and could not control PH of the water.
d.
The systen, is arranged in standby status so that on containment high pressure conditions it is only necessary to start the containment spray punip and open the header isolation valves.
QUESTION 2.09
(.50)
Choose the one that is most accurate in regard to the instrument and service air systeni.
a.
All air conpressors are fitted with teflon piston rings to eliminate the need for oil Ivbrication of the cylinders.
b.
Air dryers use electric heaters to drive moisture from the air before the air enters the instrument air header.
c.
Each compressor is loaded and unloaded individually by seperate pressure switches which are backed up by a common pressure switch.
d.
When a compressor is operated in the hand mode it will run loaded constantly to carry the base load.
(***** CATEGORY 02 CONTINUED ON NEXT PAGE
- )
2.
PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 9
l l
00ESTION 2.10
(.50)
Which one of the following is most accurate in regard to the main senerator seal oil system?
a.
The seal oil system is designed to maintain normal hydrogen pressure with a 2 psi differential between the oil and sas pressure.
l bl The primary seal oil backup source is the main shaft oil pump when the turbine is above 2/3 synchronous operating speed.
c.
The main senerator output capability is primarily dependent upon the pres sure developed by the seal oil source during operation.
- d. The normal seal oil pressure is in an operating range of 60 to 75 psis.
i l
GUESTION 2.11
(.50)
Which one of the following is most accurate in regard to the Engineered Safeguards and Emergency Power s y s t e ni?
a.
2400 vac buses 1C and 1D feeder breakers can be operated at the switch gear in the operating position.
- b. The Engineered Safeguards system includes two 2400 vac buses, two 480 l
vac load centers, and two motor control centers, two preferred ac buses and two 125 vde distribution centers.
c.
Automatic closure of a 2400 vac station power or startup transformer incoming breaker to buses 1C and 1D will occur when voltage is t
restored to the transformer.
d.
During norn.a1 operations both de buses are interconnected by a manual breaker and the battery on each bus is kept fully charged.
(***** CATEGORY 02 CONTINUED ON NEXT PAGE
- )
2.
PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 10 QUESTION 2.12
(.50)
Which one of the followins is most accurate in regard to fire protection?
- c. The fire protectiion system provides a backup water supply to critical service water, main feed water and the spent fuel pool.
b.
The Jockey pump cycles intermittently to maintain a 90 - 100 psig pressure on the fire main header.
c.
The hose reels are located throughout the plant such that all areas of the turbine and auxiliary buildings are within 75 feet of a 35 psig fos no::le.
- d. The diesel fire pump uses two 12 vde batteries wired in parallel to provide adequate starting current.
QUESTION 2.13
(.50)
Which one of the following is mest accurate in regard to plant communica-tions?
a.
The public address system is powered from the startup transformer to assur e reliability for pasing but does not require power for station to station communication.
- b. A continuous siren is a fire alarm indicating personnel should remain where they are whereas a broken siren is a plant evacuation signal.
- c. The plant has radio communications links with the NRC, state police, Kalamazoo and the Jackson power controller.
- d. The control room can initiate public address pasing to any of five site areas which overrides any transmission from another station.
(***** CATEGORY 02 CONTINUED ON NEXT PAGE *****)
2.
PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 11
. QUESTION 2.14
(.50)
Which one of the following is most accurate in regard to heating, venti-lation, and air conditining systems.
- s. The control room ventilation system automatically goes into full recirculation for hiSh containment pressure or radiation or full purse for fire.
- b. The containment air cooling system is sized such that two of the four units will limit containment pressure to less than design following a DBA.
c.
The containment air cooling units employ two matched fans with direct connected motors of which one operates normally while both oper ate during post accident conditions.
d.
A leaking containment air cooling unit coil is detected through the use of a level switch should the leak rate exceed 20 spm.
QUESTION 2.15
(.50)
Which one of the followins is most accurate regarding radioactive waste disposal?
- c. The radwaste evaporator reduces the concentration of all radioactive isotopes e:: cept tritium and seperates the boric acid from the processed waste.
b.
The distillate from the radweste evaporator is normally processed through a polishing deminerali=er to further reduce the boron and tritioni concentrations.
c.
The clean radioactive liquid waste section is distinguished from the dirty waste section by the fact that it handles the low activity effluents.
d.
Unwanted or poor quality boric acid is sent to the treated waste monitor ing tank.s for teniporary storage and eventual disposal.
(xxxxx CATEGORY 02 CONTINUED ON NEXT PAGE xxxxx)
- T'
2.
PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 12 QUESTION 2.16
(.50)
Which one of the following is most accurate in regard to the area radiation monitoring system.
a.
Area monitor readouts display individual channel outputs using a red scale for mrem per hout and cpm on a black scale which have numerous selectable ranges.
b.
Area monitor readouts display individual channel outputs using a red scale for the eight decade scale and a black scale for any one of several.selectable three decade scales all of which are in mrem per hour c.
Containment area monitors, RIA 2316-2317, are in use only during power operations and have key operated on-off switches.
d.
The fail / reset pushbutton/ light is normally lighted and extinguishes if the detector is placed in the source check mode.
DUESTION-2.17
(.50)
Which one of the following is most accurate in regard to the process radiation monitoring system?
- a. The process radiation monitoring system utilices GM tubes for gamma detection and scintillation detectors for beta radiation.
b.
An air particulate radiation monitor employs a replaceable cartridge filter to remove partriculate from the sample stream for counting.
c.
Offline process monitors have sample flow alarms to indicate the loss of sample flow which renders the process monitor inoperable.
moving filter tape to remove particulate d.
Gaseous process nionitors use a n.atter from the sample stream before measuring for activity.
(*****
CATEGORY 02 CONTINUED ON NEXT PAGE
- )
T'-
7 r
-r- - - -
9
2.
PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 13 QUESTION 2.18
(.50)
Which one of the following is most accurate in regard to the fuel pool cooling system?
- a. The water in the refuelins cavity can be cooled and clarified with or without the spent fuel cooling function in pro 3ress.
b.
The shutdown coolin3 system may be used as a backup for fuel pool coolin3 any time shutdown cooling is not required for core cooling.
- c. The fuel coolins r,ystem takes a suction off the bottom of the pool to ensure that solids do not accumulate but are filtered out.
- d. Of the total coolins system flow, a small portion is diverted to the heat e:: changer for temperature control while the remainder is filtered.
QUESTION 2.19
(.50)
Which one of the following is most accurate regarding the fuel handling system?
.a.
The refueling machine interlocks include an upmotion hoist stop if the local area monitor exceeds a predetermined radiation setpoint.
n b.
In order to receive a new fuel bundle in the new fuel elevator the interlock for raising the elevator to the surface of the pool must be overridden.
c.
Withdrawal, insertion and transfer procedures for control rods are identical to those for fuel except the mast must be rotated 180 desrees with respect to the angular position used for handling fuel bundles.
d.
Fuel transfer interlocks require that both tilt machines be in the horizontal position to perform a transfer and transfcr trevc1 will be stopped if cable tension enceeds the high limit.
(xxxxx CATEGORY O2 CONTINUED ON NEXT PAGE xxxxx) i 1
2.
PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 14 DUESTION 2.20
(.50)
Which one of the following is most accurate regarding the safety injection system?
- a. SIS equipment that is required to operate following a DBA is designed for ambient conditions of 283 degrees F, 55 psis and 100% relative humidity.
- b. The safety injection flowpath to the reactor vessel is through a no::le on each of the four cold les pipes.
c.
The SIT's are passive components which flood the reactor core with borated water under 250 psis of pressure via check valves and penetrations on the RCS cold les pipes.
- d. The SIT's contain borated water at a concentration of 1720 ppm which is sufficient to maintain the core suberitical by three percent at 60 deg.
f.
with all control rods out.
QUESTION 2.21
(.50)
Which one of the followins is most accurate regarding the safety injection system?
a.
The LPSI pumps are designed to provide a sma'll quantity of borated water at low pressure whereas the HPSI pumps are designed to provide larse quantities of borated water at high pressure.
- b. Spirlage out a PCS break is limited to a maximum of 40% by use of the flow meters in each injection line and the throttlins capability of each safety injection valve.
c.
The recirculation actuation signal opens the containment sump valves and closes the SIRW tank valves with overlapping stroke times to ensure mixins and adequate NPSH during the transfer.
d.
During the accident, if the recirculation mode is actuated, the operator takes precautions to prevent the HPSI pumps from overpressurizing the RCS.
(xxxxx CATEGORY 02 CONTINUED ON NEXT PAGE xxxxx)
2.
PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 15 GUESTION 2.22
(.50)
Which one of the followins is most accurate regarding the shutdown coolins system?
a.
The.LPSI pumps must be slowly brovsht to equilibrium temperature with the PCS when beins placed in service so as not to exceed thermal
' desisn transient limits.
b.
Relief valves are provided in the system to prevent overpressuri=ation due to thermal expansion of fluids in isolated sections of pipins.
c.
HPSI, LPSI or CS pumps can be used to transfer water from the SIRWT to the reactor cavity via the SDCS and also from the cavity back to the SIRWT.
d.
The SDCS is used during the early stages of plant startup to control the primary coolant system temperature but must be discontinued when the PCS reaches 270 deg.
F.
and 325 psis.
QUESTION 2.23
(.50)
Which one of the followins is most accurate regarding the chemical and volume control systeni?
- s. Letdown flow is depressurized in two stases before being cooled down l
in two stases prior to entering the demineralizers.
b.
Boration at end-of-life results in excessive amounts of waste when using the feed and bleed method and boration via ion exchange is more suitable.
c.
The blendins system will supply borated makeup to the SIRWT at 1720 ppm at a maximum rate of approximately 120 spm.
d.
The regener ative heat e:: changer is designed to maintain a letdown outlet temperature below 250 deg.
F.
under normal operating conditions.
(xxxxx CATEGORY 02 CONTINUED ON NEXT PAGE xxxxx)
2.
PLANT DESIGN-INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 16 GUESTION 2.24
(.50)
Tha volume control tank is designed to accomodate a ____ power reduction without makeup system operation and the accumulation of ____ sallons of water durin3 dilution.
o.-100%,'100 b.
50%, 10000
- c. 75%, 1000 d.
100%, 1000 QUESTION 2.25
(.50)
The variable speed chargins pump has a capacity of ____ to ____ spm and a nominal flowrate of ____ spm.
- o. 30, 60, 40
- b. 30, 55, 44
- c. 33, 53, 44 d.
35, 55, 45 GUESTION 2.26
(.50)
Concentrated boric acid storage tanks provide a source of ____ weight porcent boric acid at ____ deg.
F.
- c. 6.25, 100
- b. 6.5, 180
- c. 6.25, 140 d.
6.5, 120 (xxxxx CATEGORY 02 CONTINUED ON NEXT PAGE xxxxx)
O
2.
PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 17 GUESTION 2.27
(.50)
Primary coolant pumps
- e. Use a high inertia flywheel to prevent reverse flow when the pump is idle.
- b. Use three shaft seals each of which can withstand one third of normal system pressure.
- c. Prevent reverse rotation when idle which would be detrimental to the pump and motor due to a lack of lubrication.
d.
Provide a source of heat input to the primary coolant system.
QUESTION 2.28
(.50)
The quench tank normal operatin3 Parameters include ____ psis, ____ de3 F.
and ____ % level.
- e. 10, 120, 70 b.
5, 150, 50
- c. 3, 100, 50 d.
7, 90, 80 GUESTION 2.29
(.50)
The total control rod drive mechanism stroke is ____ inches at ____ inches per minute.
- a. 132, 46 b.
144, 36 c.
140, 40 d.
138, 30 (xx*** CATEGORY 02 CONTINUED ON NEXT PAGE xxxx*)
(
2.
PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 18 QUESTION 2.30 (2.00)
- o. State the total KW output from pressuri=er heaters.
b.
How can the heaters be used to force continuous pressuriner spray flow?
QUESTION 2 31 (2.00)
- a. Name the two buses that power the priniary coolant pumps.
- b. How would a loss of one bus affect the flow of primary coolant in each loop?
DUESTION 2.32 (2.00)
- a. Assumin3 it is in service, when will a deborating demineralizer no longer remove boron?
- b. HOW and WHERE is a check valve-in the CVCS system used as a relief valve?
QUESTION 2.33 (2.00)
- c. How can the atmospheric steam dumps be controlled manually if they were opened by the quick opening override bistable after a turbine trip?
b.
State the capacity of the secondary safety valves, atmospheric steam dumps and turbine bypasses in percent of total steam flow.
l GUESTION 2.34 (2.00)
- e. Which oil pump (s) provide auto stop oil pressure for the EH control system?
- b. What dictates whether the EH system is in speed control or load control?
1 l
l l
(*****
CATEGORY 02 CONTINUED ON NEXT PAGE
- )
i 2.
PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 19 GUESTION 2.35
(.50)
Which one of the following is most accurate regarding the component coolins water system?
- a. Three sets of pumps and heat exchansers each provide about 50% of the total heat removal capacity required during shutdown cooling.
b.
Valve stops were incorporated on the CCW heat exchanger critical service water outlet flow control valves to limit flow during a DE:A condition concurrent with a single failure of a diesel Senerator.
- c. The 16' butterfly outlet valves on the service water side of the CCW heat exchangers are used to maintain CCW temperature from day to day as heat loads change.
d.
CCW containment isolation valves close on a simultaneous SIAS and low CCW pressure but will fail open if control air is lost.
(xxxxx END OF CATEGORY 02 xxxxx) i
3.
INSTRUMENTS AND CONTROLS PAGE 20 QUESTION 3.01 (1.50)
- c. Where does the high power rate-of-change trip signal oriS nate from?
i b.~When is the high power rate-of-change trip bypassed?
- c. What are the two sources of bypass signals for the high power rate-of-change trip?
I QUESTION 3.02 (2.00)
% tw 4 c.What 44pn-types of detectors are used in the nuclear ins tr ument a t ior-systems?
- b. Why are there two detectors used in each of the power range safety channels?
DUESTION 3.03 (2.00)
State the meaning of the following colored matri:: lights for the given control rod.
COLOR ROD TYPE l
a.
white part length l
b.
blue shutdown l
00ESTION 3.04 (2.00) l l
l State the meaning of the following annunciator window conditions.
- c. fast flashin3 l-
- b. slow flashing GUESTION 3.05 (2.00)
What does it mean to ' time integrate' as described in the steam generator water level control system chapter?
Why is this necessary?
l l
(samur CATEGORY 03 CONTINUED ON NEXT PAGE xxxxx)
O
3.
INSTRUMENTS AND CONTROLS PAGE 21 QUESTION 3.06 (2.00)
Nace two EH system faults that will cause automatic shift of turbine control from operator auto Cimp in or speed control] to imp out or manual.
QUESTION 3.07 (1.50) 3.
How is the reSulation of steam pressure to the AFW pump turbine assured during a loss of instrument air?
- c. When is the FIC placed in the pseudo-automatic mode?
OUESTION 3.08 (2.00)
- a. How does an operator place a service water pump in standby?
- b. Why does the standby service water pump lose it's standby pump status after it starts?
- c. When is the standby pump feature not possible for service water?
- d. Why must the operator place the standby service water pump control switch to 'close' after an automatic start?
GUESTION 3.09 (2.00)
How does the component cooling water pump operation differ regarding the DE:A sequencer as conpared to the normal shutdown sequencer?
00ESTION 3.10 (2.00) n.
What is the meaning of a diesel Senerator local panel ' engine trouble' alarm lit and the absence of any other alarms.
- b. What parameter does the diesel generator exciter-resolator vary to control generator output voltage?
(wrums CATEGORY 03 CONTINUED ON NEXT PAGE
- )
l.
3.
INSTRUMENTS AND CONTROLS PAGE 22 DUESTION 3.11 (2.00)
Liet all control signals and setpoints that'
- e. Turn backup. heaters ON b.
Turn backup heaters OFF QUESTION 3.12 (2.00)
State five functions provided by the primary coolant system hot and/or cold les RTD's.
QUESTION 3.13 (2.00)
' List eight parameters or signals monitored on the primary coolant pump and motor assembly.
(xxxxx END OF CATEGORY 03 xxxxx)
-+_
4.
PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 23 R
~
~~~~~~~~~~~~~~ ~~~~~~~~~
~~~~ 5656L665C5L 6UUTR6L QUESTION 4.01 (2.00)
A ctanding order concerning the introductioin of water into the turbine from feedwater heaters recommends that the operator NOT trip the turbine until it reaches 14 mils vibration. Explain why this is necessary.
QUESTION 4.02 (2.00)
A problen. with meeting Technical Specifications for the concentrated boric acid storage tant's was identified when a loss of one diesel generator is assumed with a concurrent loss of offsite power.
- a. What is the temporary resolution to this problem?
- b. Why is this a necessar y action?
QUESTION 4.03 (2.00)
State the reason for disabling the PORV's above 325 deg. F.
QUESTION 4.04 (2.00) a.
How often are recorder charts checked?
b.
Whtt is verified on a recorder chart check?
- c. How are these checks documented?
d.
What'is required if changes are made to the recorder chart time or scale?
~
QUESTION 4.05 (2.00)
- c. What is the difference between the Reactor Logbook and the Control Room Losbook?
b.
Who normally maintains each ons?
(xxxx* CATEGORY 04 CONTINUED ON NEXT PAGE ***xx)
4.
PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 24
~~~~ I65 E UEC E~66UTR6E~~~~~~~~~~~~~~~~~~~~~~~~
R GUESTION 4.06 (2.00)
Whst are the prerequisites for removing one DG from service when the plant is less than 325 des. F.?
-QUESTION 4.07 (1.50) 3.
What two types of system valves are operations staff NOT required to operate?
b.
Name two cases where valves require locks.
c.
Name two acceptable valve locking methods.
QUESTION 4.08 (2.00)
- a. What must be done before repositioning a valve or breaker found to be in a position other than that specified. E1.03
- b. Can a repositioner and a verifier be the san.e person for the same job?
E.53 c.
What is done with the lock of a breaker positioned in other than it's normally locked position? E.53 OUESTION 4.09 (1.50)
- s. What are the heatup AND cooldown rates for the primary coolant system AND the pressurizer?
- b. What is the minimum primary coolant system pressure for operating primary coolant pumps?
- c. What plant condition Eexcluding accidents] does not allow all primary coolant pumps in operation?
GUESTION 4.10 (2.00)
Under what conditions would an emergency boration NOT be required if the power dependent insertion limit alarm actuates while the reactor is critical?
(***** CATEGORY 04 CONTINUED ON NEXT PAGE xxxxx)
4.
PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 25
~~~~ d656L665CdL C60 TEEL'~~~~~~~~~~~~~~~~~~~~~~~
R
~
QUESTION 4.11 (2.00)
- a. Why should the boron concentration be equalized between the shutdown cooling system and the SIRW tank PRIOR to decreasing the PCS pressure below 300 psia?
- b. At what point in the draining of the primary cooling system does cavitation of the shutdown cooling system pumps become a concern?
DUESTION 4.12 (1.00)
What possible electrical transmission system disturbance can cause an excessive load increase according to procedure ONP 9?
GUESTIOh 4.13 (1.00)
- LOSS OF COOLANT ACCIDENT' procedure E0P 8.1 includes the high startup rete alarm and high power level reactor trip as symptoms. Why?
DUESTION 4.14 (2.00)
- a. Why does the procedure for natural circulation require the operator to wait ten minutes after tripping the primary coolant pumps before verifying that natural cirevlation has been established?
- b. What could cause T cold to be higher than T hot in the idle loop while cooling down using natural circulation on the opposite loop?
(***** END OF CATEGORY 04
- )
(xxxxxxxxxxxxx END OF EXAMINATION ***************)
yksTER 1.
PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 26
--- isEss557sERICs-REEi iEEssFEE ER5 FEUi5 FE5E l
ANSWERS -- PALISADES
-85/07/09-T BURDICK ANSWER 1.01 (1.00)
Tha plot of counts initial over new counts (1/M) versus a reactivity condition such as rod height or fuel loaded or boron concentration.
REFERENCE 12.2-2 ANSWER 1.02 (1.00)
Instantaneous amount of reactivity by which the reactor is subcritical or would be suberitical from its present condition assuming all control rods are fully inserted (.5) except for the most reactive rod which is assumed to be withdrawn. (.5)
REFERENCE Technical Specification 1.1 ANSWER 1.03 (2.50)
~
- c. Shutdown margin (.50); _ individual rod worth (.50);
hot channel factors (.50) c.
43% inserted on group 2 OR
[T.S.]
70 inches withdrawn on group 2 OR [T.S.3 8 inches withdrawn on group 3 OR ED.L.3 88 inches withdrawn on group 2 ED.L.3 (1.0)
REFERENCE a.
Technical Specification 3.10.5.a b.
Technical Specification 3.10 Basis
- c. Technical Spacification Figure 3-6 Technical Data Book, Figure 1.9 ANSWER 1.04 (1.00)
Tha difference between reactor power in any core quadrant and the average in all quadrants. (1.0)
REFERENCE TGehnical Specification 1.1 I
r-1.
PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 27 TAERbd6YU555C5""UE5T TRIO 5FER dU6"ELU 6"_FL6U
~
~
~~~~
ANSWERS -- PALISADES
-85/07/09-T BURDICK ANCHER 1.05 (1.00)
Tho difference between the power in the lower half of the core and the upper half of the core divided by the sum of the powers in the lower half cnd upper half of the core.
REFERENCE Technical Specification 1.1 ANSWER 1.06 (1.00)
Xanon 135 has a higher absorption cross section (.5) and a hi 3 er fission h
yield. (.5)
REFERENCE Reactor Theory, Chapter 20, p 10.1-2 ANSWER 1.07 (1.00) 2 63 %
REFERENCE Technical Data Book Figure 2.1 ANSWER 1.08 (1.00)
The concentration of samarium 149 builds up to a maximum value in appro::imately 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> af ter the trip.
REFERENCE R2setor Theory, Chapter 20, p 10.5-3 l
L
1.
PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 28
~~~~ 5ER566Y IU5C5,~55dT TRdU5E5R d 6~ELU56~FLUU
~
~
T ANSWERS -- PALISADES
-85/07/09-T BURDICK ANSWER 1.09 (1.00)
Hydrosen solubility decreases when PCS pressure is reduced. (.5)
Opening tho PCS st high hydrogen concentration will cause hydrogen to come out of solution, creatins an explosion hazard. (.5)
REFERENCE SDP 1 step 7.1.5.m ANSWER 1.10 (1.00)
Haot flux above which there is a sharp reduction in the heat transfer coefficient.
REFERENCE TGchnicel S ecification 2.1 P
ANSWER 1 11 (2.00)
Roactor poweri PCS flow, temperature and pressure REFERENCE Technical Specification 2.1 ANSWER 1.12 (2.00)
- s. 230 F (1.0) b.
310 F (1.0)
REFERENCE EUP 0 1 step 3 5.d Steas Tables t
l l
i i
L
l l
1.
PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 29
--- TAEER557sARIEE-AEKi iEsssFEE AR5 FCGi5 FE5s ANSWERS -- PALISADES
-85/07/09-T BURDICK ANSWER 1.13 (2 00)
Erroneously hish. (.5)
The energy content per mass of steam will actually be lower than that assumed in the heat balance calculation, which assunies that the steam leaving the steam senerator is nearly 100% quality (no mois-tore content). (1.5)
REFERENCE GOP 12 Stean. Tables ANSWER 1.14 (2 00)
Avcilable NPSH decreases (1.0)
Required NPSH increases (1.0)
REFERENCE Westinshouse Thermal Hydraulic Principles and Applications to the PWR II, p 10-56 H
n ANSWER 1.15 (1.00)
Two of the following:
- 1. excessive noise (.5) 2.
excessive vibration (.5) 3.
Iow suction pressure (.5) 4.
fivetuating pump amps (.5) 5.
fivetuating discharge pressure
(.5)
- 6. encessively low flow (.5)
REFERENCE Wastin3 house Thermal Hydraulic Principles and Applications to the PWR II, p 10-54
1.
PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 30
~~~~ U5R566YUd5EC5I~5Edi TRdU5EER EU6"ELUE6~EL6U
~
T ANSWERS -- PALISADES
-85/07/09-T BURDICK ANSWER 1.16 (1 50)
Six of the following:
- 1. Core outlet temperatures higher than saturation. (.25)
- 2. Core differential temperature greater than 47 F.
(.25)
- 3. Incore thermocouples showins erratic indication. (.25)
- 4. Hot les temperature erratic or increasing. (.25)
- 5. Cold les temperature erratic. (.25)
- 6. Chargins a known volume of water into the PCS does not result in a corresponding increase in pressurizer level. (.25)
- 7. Pressurizer level increases more than expected when using auxiliary spray. (.25)
- 8. Unanticipated letdown flow 3reater than charsing flow. (.25)
REFERENCE ONP 21 step 4.16 ANSWER 1.17 (1.00) 31.6%
REFERENCE Reactor Theory, 16, page 6.4-2 ANSWER 1.18 (1.00) core negative REFERENCE page 9.1-2 Recctor Theory, 19,
ANSWER 1 19 (1.00)
Fact neutron irradiation of the metal.
REFERENCE T.S. 3.1.2 m
2.
PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 31 ANSWERS -- PALISADES
-85/07/09-T BURDICK ANSWER 2.01
(-.50)
O.
REFERENCE chapter 32 ANSWER 2.02
(.50) d.
REFERENCE chapter 33 page 10 ANSWER 2.03
(.50) c.
REFERENCE SFD 9-4-1, paSes 5 & 6 ANSWER 2.04
(.50) b.
REFLRENCE
'SFD 9-4-l' PaSe 6 ANSWER 2.05
(.50) b.
REFERENCE SFD 9-4-1' Pase 22 ANSWER 2.06
(.50) b.
1 t
l
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2.
PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 32 ANSWERS -- PALISADES
-85/07/09-T BURDICK
. REFERENCE SFD 9-4-1, paSes 24,25,26 ANSWER 2.07
(.50) c.
REFERENCE SFD 9-4-2, page 7 ANSWER 2.08
(.50) d.
. REFERENCE chspter 26, pages 2,3,13 ANSWER 2.09
(.50) c.
REFERENCE SFD 6.2.1 ANSWER 2.10
(.50) b.
REFERENCE chapter 31 ANSWER 2.11
(.50)
O.
REFERENCE chapter 33, page 6
i
,1 Y
't
'q s'
tg 2.
PLANT DESIGN INCL DING SAFETY AND EMERG2NCY SYSTEMS "PAGE 33
________________ _____ + ___________________.___________
C.NSWERS -- P ALIS ADES, ' 1 l'f
-85/07/09-T'BCRDICK hi
(
ANSWER 2.12
(.50) t.
(,
t c.
REFERENCE i
chcpter 34, page 3 ANSWER 2.13
(.50) d.
i REFERENCE chcpter 35, page 4 9
ANSWER 2.14
(.50) d.
?
y i;'.
I REFERENCE j,
\\
chcpter 23,1 page 22 g,
r s-ANSWER 2.15
(.50) j t
a.
e REFERENCE s
chopter 37 s
ANSWER 2.16
(.50) b.
REFERENCE 2
s i
chepter 38
\\
ANSWER 2.17
(.50) g c.
i e
\\
4 s
t i g
9
/
5.
\\
,s -
t s
i
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e e.
s s
C
. i.
2.
PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 34 ANSWERS -- PALISADES
-85/07/09-T BURDICK REFERENCE chcpter 38 ANSWER 2.18
(.50) c.
' REFERENCE chopter 40 l
ANSWER 2.19
(.50) be MA 0 REFERENCE SFD 1-11 ANSWER 2.20
(.50) b.
REFERENCE chepter 10 AN3WER 2.21
(.50) c.
REFERENCE chcpter 10 ANSWER 2.22
(.50) b.
REFERENCE chcpter 9
2.
PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 35 ANSWERS -- PALISADES
-85/07/09-T BURDICK ANSWER 2.23-(.50) c.
REFERENCE chspter16 ANSWER 2.24
(.50) ld.
I REFERENCE chepter 6, page 26 ANSWER 2.25
(
.50)'
c-REFERENCE chapter 6,
page 28 ANSWER 2.26
(.50)
'c.
REFERENCE chapter 6, page 34
(
ANSWER 2.27
(.50) d.
REFERCNCE chapter 4, page 4 ANSWER 2.28
(.50) c.
2.
PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 36
' ANSWERS -- PALISADES
-85/07/09-T BURDICK REFERENCE chcpter 3, page 23 ANSWER 2.29
(.50)
I I
St REFERENCE chcpter 2, page 3 I
ANSWER 2.30 (2.00)
I
- c. 1500 KW
- b. By placing backup heaters in manual.
REFERENCE chcpter 5, page 7, 10 ANSWER 2.31 (2.00)
{
s.
1A and 1B
- b. One pump in each loop is lost reducing the flow in both.
REFERENCE chepter 4,
page 13 16 ANSWER 2.32 (2.00) a.
When it is boron saturated. E1.03 b.
The check valve is spring loaded closed and opens when pressure is Steater than spring force.E.53 It is used on the charsing line at the letdown heat exchanSer. E.53 REFERENCE chapter 6, page 42 9
2.
PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 37 ANSWERS -- PALISADES
-85/07/09-T BURDICK ANSWER 2.33 (2.00)
- e. Reset the turbine trip relay 30 seconds after the trip.
b.
1.
safeties - 9% each OR-104% total 2.
atmospheric - 7% each OR 30 % total 3.
bypass - 5%
REFERENCE SFD 5.3 ANSWER 2.34 (2.00) a.
Main oil pump E.53 and seal oil backup pump. E.53 b.
The position of the generator. output breaker.
REFERENCE chapter 19 ANSWER 2.35
(.50) b.
REFERENCE SFD 1-11
3.
It'STRUMENTS AND ' CONTROLS PAGE 38 ANSWERS -- PALISADES
-85/07/09-T BURDICK ANSWER 3.01 (1.50)
- o. wide ranSe ID3rithniic channels E.53
- b. below 10^-4 percent E.253 and above 15 percent E.253 c.
wide range logrithmic E.253 and power range safety channels E.253 REFERENCE chapter 11, page 6 and 7 ANSWER 3.02 (2.00) a a.4-preeoctinn=1 count @
2.
fission chamber 3.
uncompensated. ion chamber
, _h 4.
rhodium wire EsE& each]
- b. To allow measurement and ccmparison of the upper and lower halves of the core.
REFERENCE chapter 11, pages 7-11 ANSWER 3.03 (2.00)
- a. moving
[1.03
- b. between the upper and shutdown control rod insertion limits E1.03 REFERENCE chopter 13, page 7 ANSWER 3.04 (2.00)
- a. incoming alarm before acknowledgement b.
return to normal 1 forc actr.;wled ccentf 5
REFERENCE chspter 14, page 25 i
I I
l I
l
3.
INSTRUMENTS AND CONTROLS PAGE 39 ANSWERS -- PALISADES
-85/07/09-T BURDICK ANSWER 3.05 (2.00)
' Time integration' is an amplificatiion of the process deviation over time.
E1.03 It is necessery to maintain the desired setpoint constant. E1.03 REFERENCE chspter 17, page 7
. ANSWER 3.06 (2.00)
- a. If the speed reference deviates 600 rpm from actual speed.
b..If the load reference output is 30% less than impulse pressure trans-mitter output when the systen. is in the IMP mode.
c.
If the impulse pressure transmitter is out of it's normal operating band.
- d. If the load reference counter output is 30% higher than impulse pressure t r a ns nii tte r output and VPL has not been reached.
REFERENCE chapter 19, page 36 ANSWER 3.07 (1.50)
- c. nitro 3en accumulator backup to instrument air b.
both in automt. tic c.
when the HIC is in manual REFERENCE SFD 5.7, page 6
.g--
3.
INSTRUMENTS AND CONTROLS PAGE 40 ANSWERS -- PALISADES
-85/07/09-T BURDICK ANSWER 3.08 (2.00)
- a. The manual pushbutton for that pump is actuated.
b..To prevent autoniatic restart if the pump should fail to start the first time.
~~~)3
- c. When only one pump is running 4 d.
To establish the pump's trip alarm circuit.
[ 76'each]
REFERENCE chapter 24, paSe 12 J
ANSWER 3.09 (2.00)
The DBA sequencer automatically starts CCW pumps whereas the normal shut-down sequencer does not.
REFERENCE SFD 1-11, page 11 ANSWER
.3.10 (2.00) c.
loss of de control power to the DG b.
DG field current REFERENCE SFD 9-4-1, page 23 and 28 ANSWER 3.11 (2.00) c.
1.
Low pressuricer pressure of 1970 psia.
incr e a s ing.2 fl 0 w<-f 2.
Pressurizer level deviation of +4.6%
b.
1.
High pressurizer pressure of 1985 psia.
2.
Pressurirer level deviation of +4.6% decreasing.
3.
Low pressurizer level of 36%
E5 at
.4 each3
3.
INSTRUMENTS AND CONTROLS PAGE 41 ANSWERS -- PALISADES
-85/07/09-T BURDICK REFERENCE chepter 5, page 8 ANSWER 3.12 (2.00) g, p (; Q g.,QLcN $AtWn 1.
T averaSe input s
- 2. Delta-T input
'D g, D Y e.L 6,,2pt w. m
. m ;;
a
- 3. Thermal marsin/ lou pressure trip 4.
indication / alarm 5.
PORV low pressure setpoint REFERENCE chapter 3, pages 29-30 ANSWER 3.13 (2.00) 1.
lower seal cavity temperature
- 2. controlled bleed off temperature
- 3. controlled bleed off flow rate 4.
upper seal cavity pressure 5.
middle seal cavity pressure 6.
Iower seal cavity pressure
- 7. motor stator temperature 8.
opper guide bearing temperature 9.
lower guide bearing temperature
- 10. upward thrust bearin3 temperature
- 11. downward thrust bearing temperature
- 12. upper motor oil level 13 lower motor oil level
- 14. assembly vibration
- 15. CCW flow
- 16. reverse rotation
- 17. motor oil lift pressure 08 0.25 each]
IS, ssu b-a,o REFERENCE chepter 4, table 4-1
l j
4.
PROCEDURES - NCRMAL, ABNORMAL, EMERGENCY AND PAGE 42
~~~~ d656L55iEst C5UTR5L
~~~~-------
R ANSWERS -- PALISADES
-85/07/09-T BURDICK ANSWER 4.01 (2.00)
Tripping the turbine earlier may result in worse damase as it passes through the critical speed zone.
REFERENCE S.O.
18 ANSWER 4.02 (2.00)
- o. Anytime routine evolutions will reduce a CBAST level to less than T.S.
requirements then use "B'
tank.
b.
'A' tank is available for injection when either diesel is DOS with a loss of offsite power.
REFERENCE S.0.
28 ANSWER 4.03 (2.00)
To prevent a possible LOCA during a fire in the cable spreading room.
REFERENCE S.0.52 ANSWER 4.04 (2.00)
- o. At least once per shift. E.53
- b. Check to see that marking is clearly visible E.25] and that timing is correct E.253.
c.
Mark the chart with the time and date. E.53 d.
Note changes on the chart. [.5]
REFERENCE 4.01, page 15
4.
PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 43 RA5iSL55i5AL C5sTR5L
~~~~
ANSWERS -- PALISADES
-85/07/09-T BURDICK ANSWER 4.05 (2.00)
- o. The Reactor Logbook is for primary systems E.5] while the Control Room Logbook is for secondary systems E.5].
b.
CO 2 maintains the Reactor Logbook E.5] and CD 1 maintains the Control Room Logbook E.5].
REFERENCE 4.01 ANSWER 4.06 (2.00)
At least one service water pump E1] and one component cooling water pump
[1] must be operable on the operable diesel generator train.
REFERENCE 4.01, page 20 ANSWER 4.07 (1.50)
- c. sample valves [.253 and instrument valves E.25]
b.
1.
valves in a safety system 2.
manual containment isolation valves
- 3. valves in the main flowpath of a safety system 4.
vents and drains that could result in greater than 5% of main flow
- 5. vents and drains that receive no routine inspection
[2 9.25 each]
c.
1.
lead seal
- 2. chain and padlock
- 3. key switch
[2 9.25 each]
REFERENCE 4.02, page 1-3
I I.
4.
PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 44
~~~~
~~~~~~~~~~~~~~~~~~~~~~~~
l RA65UL6656AL'66 TRUL CNSWERS -- PALISADES
-85/07/09-T BURDICK ANSWER 4.08 (2.00)
O.
get SS authorization first
- b. no c.
leave it unlocked REFERENCE 4.02, page 3 ANSWER 4.09 (1.50)
M##Y'N c.
- 1. PCS - 60 degrees per hout E.253
- 2. PZR - 150 degrees per hour E.253 og 104 Y[/A T.3, f
- b. 250 psiga E0.53 9
- c. PCS less than 400 degrees
[0.53 l
l REFERENCE SDP 1, pages 2 and 3 ANSWER 4.10 (2.00) l during an emergency power reduction REFEREFCE SDP 2A, 3.0.f.
ANSWER 4.11 (2.00)
- o. To prevent opening the SI check valves.
c
~
~
- b. When the level reaches the top of the hot les.7 CUIdl 1]s hadk' g
ANSWER 4.12 (1.00)
Icw system frequency l
I i
7 l
4.
PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 45
~~~~ I6I6[66565L 66aTR6t R
ANSWERS -- PALISADES
-85/07/09-T BURDICK REFERENCE ONP 9, 3.2.e ANSWER 4.13 (1.00)
LOCA due to a rod ejection REFERENCE E0P 8 1.J and k.
l l
ANSWER 4.14 (2.00)
- o. Due to increased loop transport time.
- b. Heat input to PCS from the idle steam generator.
REFERENCE ONP-21, 4.2 and 4.12 l
l
CONSUMERS POWER CG'PANY NUCLEAR TRAINING CENTER Instructor 1,esson Plan Pr:gra:n
Title:
Nuclear Operator Training Lesson Plan N5.
7/3/85 Cdurse :
R. O. Requal Exam & Key Module:
Section 1 Tapic:
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FG30NAL AND CONFIDENTIAZ, NOTD EXAMINATION COVER SIEET Social Security No j
Name Please Circle 06*02 CF Co Employee Consumer Power Company M
N W O3 h Q Q W e Company Work Location __
Palisades EIS No 600421 D:p:rraent Annual Requal Exam gy1 No 06*26/19 Course 7/3/85 Exam No 1
of 1
Class No Instructor Rav rification Dato Administered 7/3/R5 Administered by NRC Dato Graded Graded by Grcda sha'11 be cause for disciplinary action in accordance with the applicable "Ch: sting on an na Ge:cral Order or Working Agreement.
All incidents of cheating shall be reported to the cogu and shall reau aant supervisor (s) and the Director - Nuclear Operations Training Department, in immediate forf eiture of the student's essa."
I was given the opportunity to review the correct responses to this e 4antion.
Signed Date
---,,,-~n,.
a
EQUATION SHEET f = as y = s/t Cycle efficiency = (Network out)/(Energy in) 2
- V t + 1/2 at w = ag2 o
xE E = ac 2
a = (Vg - V,)/t A = AN A = A,e KE = 1/2 av PE = man w = 9/t A = An2/t1/2 = 0.693/t1/2 Vf = V, + a t W = v AP t
en =
1/2NY 1/2
[(t1/2) * ("b)l I = I,,-h Ag = 931 as
-px h = bpAt I = I,e h=UAAt I = I,10 */ M
~
Pwr = W ah TVI. = 1.3/p g
P = P,10'"*(")
P = P,e /T SCR = S/(1 - K,gg) t SUR = 26.06/T CR, = S/(1 - K,gg,)
(1 - keH2)
SUR = 26p/1* = (p - p)T CRg (1 - K,ggg)=CR2 T = (1*/P) + (($ - P)/Xp]
M = 1/(1 - K,gg) = CR /CR, g
T = 1*/0 M = (1 - K,g,)/(1 - K,ggg)
T = ($ - p)/(h)
SDM = (1 - K,gg)/K,gg
-5 1* = 10 second.1 P = (K,gg-1)/K,gg = AK,gg/K,gg
-I X = 0.1 seconds p=((1*/(TK,gg)]+(J,gg/(1+XT)]
Id11=Id22 P=(I$V)/(3xigo)
Id 2,gd gg 22 I = oW 2
R/hr = (0.5 CE)/d (,,g,,,)
R/hr = 6CE/d2 (g,,g)
Miscellaneous Conversions Water Parameters 10 1 curie = 3.7 x 10 dps 1 gal = 8.345 lba 1 kg = 2.21 lbe 1ga}=3.78 liters 1hp=2.54xlofBtu/hr 1 ft = 7.48 gal 3
I sw = 3.41 x 10 Btu /hr Density = 62.4 lb /ft 9
1 in = 2.54 cm Density = 1 as/cm Heat of vaporization = 970 Btu /lbe (At Ata, Press)
- F = 9/5*C + 32 Reat of fusion = 144 Btu /lba
- C = 5/9 (*F-32) 1 BTU = 778 ft-lbf l
1Ata=14.7 psi =29.9gnHs 1ftH0=0.4335lbf/gn 3
1 in H3 = 0.491 lbf/in
Figura 8.2, Paga 1 of 2, Rav 0,
FORMULA SHEET I.
Boron Addition
)
A.
HOT 5 77 X 10 in (B.A.T.k. PPM-PC(Initial)
V Gal.
B.A.
=
(B.A.T.k. PPM-PC(Final) 8.h8 X 10 in (B.A.T.k. PPM-PC(Initial)
V Gal.
B.A.
=
(B.A.T.k. PPM-PC(Final) s I
C.
V Gal.
B.A.
for Gal. of Water Desired PPM
=
to Borate X
increase desired PPM increase B.A.T.k.
PPM II.
Dilution A.
HOT V Gal. PMW = 5 77 X 10 in (PC Initial)_
~
(PC Final)
,/
B.
COLD V Gal. PMW = 8.h8 X 10 in (PC Initial)_
(PC Final)
III.
Blend Ratio B.A.T.k. PPM - 1 = #of Gal. PMW PC PPM 1 Gal.
B.A.
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SECTION 1 RO EXAM 1.1 For equal reactivity additions at BOC and EOC state which point in' core life would result in a higher S.U.R. (ie. BOC or EOC).
(1.0)
/ ' ~~'
f 1.2 State the reason for overlap of control rod groups 1-4 for withdrawal and insertion.
(1.0)
/*,'
1.3 A.
State how the fuel temperature coefficient changes over core life.
(ie. more negative, less negative, remains constant)
(.5)
B.
State how (ie, more negative, less negative, remains constant) the fuel temperatura defect changes over core life.
(.5) 1.4 The plant is operating at 100% steady state power with a primary boron concentration of 323 ppa. Using the graphs provided, calculate the mellons of boron that will need to be added to reduce reactor power to 50%.
(Show all work) (Assume BAST conc. = 12,000 ppa.)
(2.0) 1.5 What effect (increase, decrease, remains the same) will'a 20'F decrease in main condenser cireviating water inlet temperature have on the following plant parameters.(assume 100% power, condenser back pressure is 4" Hg).
(2.0)
A.
Condenser vacuum B.
Main generator output C.
Plant efficiency D.
Turbine work 1.6 Which of the statements below describes the result of installing two identical centrifugal pumps in parallel? Assume discharge is to atmosphere.
(1.0) i A.
Total discharge flow of the two is the same as the discharge of a single pump, but output pressure is doubled.
B.
Total discharge flow of the two is twice that of a single pump, but r
the output pressure remains the same as the single pump.
C.
Total discharge flow and the output pressure of the two is twice that of a dingle pump.
D.
Total discharge flow of the two is the same as the discharge of a i
single pump, but the output pressure is squared.
}
l 1
miO685-0021a-nib I
~
1.7 In which case would the individual rod worth be higher?
(1.0)
Case 1: All rods are fully withdrawn and rod #33 drops into the core.
Case 2: All rods are fully inserted except for rod #33 which is fully withdrawn.
1.8 With the plant at 0% power. Tave at 532*F and steam generator, pressure at 900 psia, a steam leak is suspected in an instrument line from 'A' S/G. Using the Mollier diagram provided, answer the following questions.
A.
State the temperature of the water in the steam generator.
(.25) 5.
State the temperature of the steam exiting the leak in the steam generator.
(.25)
C.
Is the steam exiting the leak subcooled, saturated or superheated.
(.25) 1.9 The plant was operating at 100% power for the past two (2) sonths and tripped off due to a loss of 'A' and 'B' 4160 V busses. For the following variables, state how the primary system flow rate will be effected.
(*ie, increase, decrease or remain the same).
Assume di other parameters constant and 15 minutes after trip.
A.
An atmospheric steam dump valve sticks open and depressurised 'A' S/G to 700 psia.
(.5)
Y,-
B.
Primary System pressure decreases to 1700 psia.
(.5)
A5 C.
Using the Auxiliary Feedwater System, both S/G 1evels are increased from 20% to 40%.
(.5)
.i 1.10 The plani: is operating at 100% and decreasing to 50% power for mainte-nance activities. One secondary code safety lifts at 55% power level.
Choose one of the following actions that could best aid in ressating the code safety.
(.75)
- ~
A.
Increase Tave and decrease Turbine Load B.
Maintain Tave constant and decrease Turbine Load C.
Decrease Tave and increase Turbine Load D.
Increase Tave and maintain Turbine Load constant miO685-3021a-nib
(
1.11 The graphs below were made by equal positive reactivity additions in a suberitical reactor. Choose the graph that indicates being closest to I,$
approaching criticality.
( /. 6)
A B
C L
lilll 11 lill!
y W
3.i -
IlliLl
~
hilll l
Illlll I
I!Illllll N e u t r o n C o u n t R a t e ->
1.12 For a reactor trip after operating at 100% power for the past two (2) months.
A.
Stata the value for dec.sy heat in % power one (1) minute af ter the trip.
(.5) i, ?,
B.
State the amount of tim, to reach peak Xenon after the trip.
(.5) f' C.
State the amount of boron required to be added to compensate for one i
control rod that failed to fully insert during the trip.
(.5)
D.
State the expected SUR 'af ter the prompt drop.
(.5) m10685-0021a-nib
(,
:perience a r ecr i ticality ever, though all control rods are inserted and the proper boron concentration is n.aintained.
(***** CATEGORY 05 CONTINUED ON NEXT PAGE mummm) i 1
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15.
THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 3
QUESTION 5.06 (1.00)
- e. When is the Guadrant Power Tilt limit applicable? (.5)
- 6. What action must be taken if Ovadrant Power Tilt exceeds 15% when the the Quadrant Power Tilt limit is applicable? (.5)
GUESTION 5.07 (2.00)
E:: pain why the peak xenon worth after a reactor trip from 100% power is n2ctly twice that of a reactor trip from 50% power, even though the equili-brium xenon worth at 100% power is much less than twice the equilibrium nanon worth at 50% power.
QUESTION 5.08 (1.00)
A positive reactivity addition occurs in the core after a trip fron. Power because of the increase in concentration of a certain fissile isotope.
What is the name of this fissile isotope and why does its concentration ircrease after a trip?
GUESTION 5.09 (1.00)
PCS pH centrol is provided by lithium 7 hydroxide.
Why is lithium 7 hydr o::i de used instead of 11thivr. hydroxide made from natural lithium?
DUESTION 5.10 (1.00)
One niethod of introducing lithium 7 into the PCS is by charging using the ch2mical add) tion tank.
Name two other ways in which lithlun. 7 enters the PCS.
(xxxxx CATEGORY 05 CONTINUED ON NEXT PAGE unaux)
5.
THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 4
QUESTION 5.11 (2.00)
Hydra:ine is added to the PCS for oxygen control durinS PCS heatup (when PCS temperature is between 230 and 250 F) and hydrogen is added to the PCS fd? oxygen control when the reactor is operating,
Why isn't hydra ine used for oxygen control when the reactor is operating? (1.0)
GUESTION 5.12 (1.00)
Nana two automatic trips provided to prevent the core from violating DNE:.
QUESTION 5.13 (1.00)
What would the pressurizer relief valves discharge temperature be if quench tenk pressure is 5 psis, there is a steam bubble in the pressuricer and PCS pressure ist s
- o. 2035 psis (.5)
- b. 885 psis (.5)
DUCSTION 5.14 (1.00)
How do the available NPSH and the required NPSH change as the flow tste through the pump increases?
OVESTION 5.15 (1.00)
What is pump run-out?
DUESTION 5.16 (1.00)
Ncce two indications of pump cavitation.
(*****
CATEGORY 05 CONTINUED ON NEXT PAGE mummm)
5.
THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 5
qg DUESTION 5.17 (1.00)
Explain why the pressure / temperature limits curves must be redrawn periodically to account for increased radiation exposure of the reactor
,vossel.
GUESTION 5.18 (1.00)
What is meant by the term " r e f l u:: boiling'?
DUESTION 5.19 (1.00)
After severe fuel clad damage has occurred, excessive core flow may E::P ain why.
l adversely affect core cooling.
(*****
END OF CATEGORY 05
- )
9
6.
PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 6
' QUESTION 6.01 (1.00)
Whct three trips will be defeated by the zero power mode bypass?
QUESTION 6.02 (2.00)
Whare are the following neutron detectors used at Palisades?
- o. Boron tri-fluoride proportional counter (.5) b.
Fission chamber (.5)
- c. Ion chamber (.5)
- d. Rhodium detector (.5)
QUESTION 6.03 (1.00)
What will cause the incore detectors to generate a signal when the reactor is shutdown and soberitical?
DUESTION 6.04 (1.00.1 Describe the effects of the following reactor protective system faults
- s.
Shortir3 of a logic s.atr i:: to ground. (.5) 6.
Loss of power to a logic matti :. (.5)
QUESTION 6.05 (2.00)
Give two reasons why an anti-reverse rotation device is necessary in the dasign of the Primar y Coolant Pumps.
QUESTION 6.06 (1.00)
Naae the three relief valves which discharge to the Guench Tank.
(*x*** CATEGORY 06 CONTINUED ON NEXT PAGE xxumm)
6.
PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 7
OUESTION 6.07 (1.00)
What is the advantage of using the deborating ion e:: changer for_ reducing PCS boron concentration at EOL?
DUESTION 6.08 (1.00)
Why is a relief valve needed between the shutdown cooling system isolation valves (MO-3015 and 3016)?
DUESTION 6.09-(2.00)
- s. Under what condition will the atmospheric steam dump valves be stroked rapidly to their full open position? (1.0)
- b. Why would an error in the steam dump controller setting not cause an uncontrolled PCS cooldown? (1.0)
GUESTION 6.10 (1.00)
How does a turbine trip affect the feedwater regulating valves and the feed putop turbines?
f 00ESTION 6.11 (1.50)
E>:p l a in t he auton. etic starting sequence for the AFW pumps upon receipt of so Auto Feed Actuation Signal (AFAS).
QUESTION-6.12 (1.00)
Describe the steani generator recirculation flow path during cold shutdown.
OllESTION 6.13 (1.50)
E::P ain how a safety injection actuation signal in conjunction with a loss l
of site power affects the component cooling water system.
(***u*
CATEGORY 06 CONTINUED ON NEXT PAGE xxxxx)
6.
PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 8
OUESTION 6.14 (1.00)
What two signals will cause the isolction of non-critical service water
.from critical service water?
QUESTION 6.15 (2.00) 3.
What two chen.icals are added to the containment spray system and why is each added? (1.0)
- b. When, after the initiation of containment spray, are each of these chon.icels added? (1.0)
GUESTION 6.16 (1.00)
What.is the starting sequence of the fire system pumps?
Include setpoints.
QUESTION 6.17 (1.00)
Why must the use of breathing air in containment be restricted if one of the F lant ncin air c o c.p r e s s o r s is running hot?
DUESTION 6.10 (1.00)
Whct is the purpose of the generator seal oil cooler service water booster pump P-44?
OUESTION 6.19 (1.00)
'What is the purpose of the cerdon system on the niain generator?
QUESTION 6.20 (1.00)
What three coriditions will cause the emergency diesel generator breaker to auton.atically open?
(*****
END OF CATEGORY 06 *****)
7.
PROCEDURES - NORMAL, A E:N OR M AL, EMERGENCY AND PAGE 9
~~~~ IDEUEUG5CEE~CUNTRUE-~~~~~~~~~~~~~~~~~~~~~~~
R GUESTION 7.01 (1.50)
Should personnel observing leakage from a potentially radioactive plant eystem shut upstream and downstream isolation valves in order to stop the leak?
E::p l a i n.
QUESTION 7.02 (1.00)
What immediate actions should personnel take if the red alarm light on a conctant air monitor comes on?
GUESTION 7.03
-(2.00)
Whct are the two major dif ferer ces between a critical approach with only one operable startup detector and a critical approach with two operable startup detectors?
OUESTION 7.04 (1.00)
'What action must be taken if pressurizer sprays are operated when the differer.tial temperature between spray water and pressuricer water e::c eed s 200 F?
DUESTION 7.05 (1.00)
When nivst low temperature over pressure protection be in service?
(wrurn CATEGORY 07 CONTINUED ON NEXT PAGE **mus)
7.
PROCEDURES - NORMAL, AE: NORM AL, EMERGENCY AND PAGE 10
~~~~ 56 ULU55CdL"66UTE6L'~~~~~~~~~ ~~~~~~~~~~~~~
R 00ESTION 7.06 (2.50)
- c. During power operation, a minimum differential temperature of ___ must be maintained betwean the pressurizer and the PCS loops. (.5)
- d. The minimum shutdown s arsin which must be niaintained when only three primary coolant punps are operatin3 at hot shutdown and above is
(.5)
GOESTION 7.07 (1.00)
What in-plant group siust be notified ar;d what r ecor d-keeping requir ements
. oust be met immediately after any emergency use of the atmospheric steam dumps?
OUESTION 7.08 (1.50)
Explain why control valve CV-0951 must not be open if either control valve CV-0950 or CV-0913 is open.
Refer to Figure 7.8.
QUESTION 7.07 (1.00)
Why are vented tanks containing boric acid prohibited froni being pressurized?
DUESTION 7.10 (1.00)
Why must the draining of a safety injection tank be stopped if tank
.prossure falls below 20 psig?
(xxx** CATEGORY 07 CONTINUED ON NEXT PAGE xxxxx)
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PROCEDURES - NORMAL, A E:N O RM AL, EMERGENCY AND PAGE 11
~~~~ 5656LU556AE~E6UTRUL'~~~~~~~~~~~~~~~~~~~~~~~
R GUESTION 7.11 (1.50)
Whsn punipin3 surplus water from the spent fuel pool to the SIRW tank SFP113 is shut and SFP127 is open.
Why must SFP127 be shut prior to opening SFP113 when restoring the spent fuel pool cooling systene to its nornial linevP?
Refer to Figure 7.11.
QUESTION 7.12 (1.00)
Why can't the refueling uachine's automatic hoist underload shutdown inter-lock be used when nioving a control rod?
QUESTION 7.13 (1.00)
If the turbine has not tripped and the Senerator breakers have not opened after a reactor trip, the turbine, ar.d then, if necessary, the generator, ore n.anually tripped.
Why is the turbine tripped first?
QUESTION 7 14 (1.00) 7 N a n.e two stear, generator indications which are indicative of s t c a n' se rie r a t o r dryout.
QUESTION 7.15 (1.50)
- c. What is the minimum required HPSI pump flow rate? (.5) b.
What action should be taken if the runnirig HPSI pumps are not maintaining this niininium flow rate? (1.0)
GUESTION 7.16 (1.00) l' Why nivst the safety injection tanks be vented or isolated two hours after a LOCA?
(mmuun CATEGORY 07 CONTINUED ON NEXT PAGE mummm)
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l 7.
PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 12
~~~~ 5656[66165E~66UTR6[~~~~~~~~~~~~~~~~~~~~~~~~
R QUESTION 7.17 (1.00)
Hcw can the reactor be cooled if no steam senerators are operable and PCS prossure is too high for shutdown cooling?
DUESTION 7.18 (1.00)
Why must PCS pressure be controlled at least 100 psi above steam ser.er a t or prossure.during a steam senerator tube rupture?
QUESTION 7.19 (1.50) l While at power, indication is lost on all wide range los recorders, power f
tense recorders, feed water regulation valve and turbine Sovernor valve position indicators.
- c. What failure has occurred? (.5) b.
What four immediate actions must be tak.en? (1.0)
DUESTICH 7.20 (1.00)
Why ar e the primary coolant pumps n.anually tripped 5 seconds after the l
reactor is tripped if a safety injection has occurred?
I i
l l
(***** END OF CATEGORY 07 mus**)
_m
8.
ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 13 QUESTION 8.01
(.50)
Which of the followins conditions is NOT required for containment intogrity?
- o. All non-automatic containment isolation valves are closed.
- b. The equipment door is properly closed and sealed.
- c. Both doors in each personnel air lock are properly closed and sealed.
- d. All autoniatic containment isolation valves are operable or are locked closed.
QUESTION 8.02
(.50)
After operating for 10 days in cycle 6 at 90% power, power is increased to 93% by boron dilution at the fastest permistible rate.
How long did this power increase take?
- o. six hours b.
th ee hours c.
one hour
- d. one-half hout DUESTION 8.03
(.50)
Above ____ power, the high level feedwater heater a l t r ai lights should stay cut.
If the level in any feedwater heater rises above the _______________
crid continues increasing, bypass the heater i nim e di a t e l y.
- o. 15%; top of the sight glass b.
15%i donip valve opening
- c. 25%i top of the sight slass
- d. 25%; dunip valve openins l
(musar CATEGORY 08 CONTINUED ON NEXT PAGE mamma)
8.
ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 14 OUESTION 8.04
(.50)
If no feedwater heaters are available, power operation isi
- o. limited to 600 MWe.
b limited to 300 MWe.
g c.
lisiited to 150 MWe.
- d. not permitted.
QUESTION 8.05
(.50)
Whan feedwater heaters must be bypassed at load, they should be bypassed
_____ the load is decreased so that the effectiveness of the shell drains will not be reduced due to the _______ extraction pressures at a lower lood.
c'.
before; decreased b.
beforei increased c.
afteri decreased d.
afteri increased 00ESTION C.06
(.50)
If a feedwater heater tube ruptures resulting in water induction into the turbine, trip the turbine _____, and _____ bypass the feedwater heater with tha ruptured tube and the nent higher pressure feedwater heater.
a.
immediatelyi immediately b.
if turbine vibration exceeds 14 milst immediately e.
i nim edi a t el y i after the turbine is tripped d.
if turbine vibration exceeds 7 mils; after the turbine is tripped (murum CATEGORY 08 CONTINUED ON NEXT PAGE musum) 1 e
j 1
l l_
l
B.
ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 15 QUESTION 8 07
(
.50)-
If the ice loading limits of the 345 KV transmission lines are enceeded:
- a. place the plant in hot standby.
b.-reduce power to 8% and take the turbine off the line.
c.
reduce power to 150 MWe.
d.
reduce power to 300 MWe.
QUESTION 8.00
(.50)
True or False.
When perforsiin3 Technical Specifications Surveillances, i
to be3 nning the surveil-i rodundant equipment must be test started prior lence unless specifically exen.pted by the test procedure.
QUESTION 8.09
(.50)
True or False.
A component underSoins re3ular surveillance is considered inoperable until its perfornisnce indicates it to be operable.
GUESTION 8.10
(.50)
Tave shall not exceed as measured by the averase of ___-.
- a. 560.8 F: all sixteen safety instrunients.
- b. 560.8 F for any loop; that loop's safety instruments.
- c. 562.8 F; all sixteen safety instruments.
d.
562.8 F for any loopi that loop's safety instruments.
(uswas EATEGORY 08 CONTINUED ON NEXT PAGE
- )
u-
8.
ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 16 GUESTION 8.11
(.50)
If the primary to secondary leak rate e:-:ceeds _____ for any period of ctoady state operation greater than 24 consecutive hours, imnie di a t el y
_____a c.
.1 sp ni; coninience a controlled plant shutdown.
b.
.1 spni trip the reactor and carryout EDP 1.
c.
.6 spnii c omnience a controlled plant shutdown.
d.
.6 spai trip the reactor and carryout E0P 1.
DUESTION 8.12
(.50)
Only the _____ has Upon finding people trapped in a stuck elevator tha authorization to open a stuck elevator car for the renioval of passengers.
o, manually nove the car to a position level with the nearest floori Shift Supervisor b.
manually move the. car to a position level with the nearest floori Duty and Call Superintendent c.
open the electrical breakers which supply power to operate the cari Shift Supervisor d.
open the electrical breakers which supply power to operate the cari
' Duty and Call Superintendent 00ESTION 8.13
(.50)
If a coniponent with a def eated or renioved overpressure protective device is placed in service, controls must be established to ensure that applied prossure is no greater thani j
- o. hydrostatic test pressure.
b.
relief valve setpoint.
- c. 75% of hydrostatic test pressure.
- d. 75% of relief valve setpoint.
(*****
CATEGORY 08 CONTINUED ON NEXT PAGE mammm)
8.~
ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 17 QUESTION 8.14
(.50)
Entries into the personnel air lock are administrative 1y controlled by
_____ only after authorization has been granted by the _____.
- c. use of a radiation work persiti Shift Supervisor.
b.
activating the entrance card reader for door 83Ai Shift Supervisor.
- c. use of a radiatiore work permiti Radiation Safety Supervisor.
d.
activating the entrance card reader for door 83Ai Radiation Safety Supervisor.
QUESTION 8.15
(.50)
PORU breakers shall be operi above _____ due to the possibility of _____.
- a. 200 Fi brittle fracture of the PCS.
b.
200 Fi fire in the cable spreading room.
- c. 325 Fi brittle fracture of the PCS.
- d. 325 Fi fire _in the cable spreading roor..
00ESTION 8.16
(.50)
If a feedwater regulating valve is pinned open where a low steam senerator pressure safety actuation occurs, the required action is to immediately trip the' O.
coriderisate punips.
b.
feedwater stop valves.
c.
feedwater regulatin3 valves.
d.
feedwater pumps.
(mmmum CATEGORY 08 CONTINUED ON NEXT PAGE suman) l i
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8.
ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 18 QUESTION 8.17
(.50)
Whsn LCO requirements cannot be satisfied because of circumstances in oncess of those addressed in Technical Specifications, within _____ action chall be taken to place the unit in _____.
- o. six hoursi at least cold shutdown within the ne::t 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> s.
b.
six houtsi at least hot standby within the next six hours.
- c. one houri at leact cold shutdown within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- d. one houri et least hot standby within the next six hours.
QUESTION 8.18
(.50)
True or False.
Erit t y into a plant condition for which all applicable LCOs cre riot met is allowed pr ovided applicable provisiores in the ACTION r equir enierits ar e niet.
QUESTION 8.19
(.50)
Containment integrity nivst be established if PCS temperature exceeds ____;
containment coolir'3 systenis must be oper able if r
a.
210 Fi the: reactor is critical.
b.
325 Fi the reactor is critics 1.
- c. 220 Fi PCS temperature exceeds 325 F.
d.
325 Fi PCS ten.perature exceeds 325 F.
(***** CATEGORY 08 CONTINUED ON NEXT PAGE
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ADMINISTRATIVE PROCEDURES, CONDITIONS, ANDil. IMITATIONS PAGE 19 y
QUESTION 8.20
(.50) p.
E:: cept f or containment ' leak rate tests, internal pressure shall not, e::ceed I
Baron dilution to less than _____ shutdown boron coneyntration i
chall not be made unless containn.ent integrity is established.
s m.
3 psis: refueling b..3 psisi cold c.
1 psisi refueling d.
1 psisi cold t
t.
QUESTION 8 21
(.50)
IS Which of the following one.NOT required to be operable in order to maintain PCS temperature above 325 F?
- a. Preferred AC bus Y10 b.
MCC number 5
- c. 480 volt distribution bus 11 d.
2400 volt bus 1E
\\
DUESTION 8.22 1.50)
In order to maintain PCS temperature above 325'F, 240 volt AC power panels No. 1 and 2 and their associated ACB breaker distribv?. ion system, located in the _____,,?nd 125 volt DC buses, _____ must'be operable.
- o. av::iliary building; DIO and D20
- b. avi:iliary building; No. 1 and 2 I
- c. switchyerdi D10 and D20 d.
switchyardi No. 1 and 2 x
i c
s u
(****r CATEGORY 08 CONTINUED ON NEXT PAGE unums) s e
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8.
. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 20 l
QUESTION
'8.23
(.50)
Which of the fo11owin3 conditions does NOT have to be satisfied i m n.e d i a t e l y prior to perfor ming ref ueling operations involving core geometry changes?
- a. Both control roon emer3ency air cleanup systenis operable.
bf PCS boron concentration of 1720 ppm or greater.
- c. Two source range neutron sionitors operable.
d.
Both shutdown coolin3 heat e:: changers in operation.
QUESTION 8.24
(.50)
Which of the following instrumentation systems is required to be operable uhor PCS temperature is below 325 F?
D.
Pressurizer code safety relief valve temperature monitor b.
Auxiliary feed flow rate meter
- c. Containnient hydrogen monitor d.~Pressuri:er code safety relief valve acoustic monitor QUESTION 8.25
(.50)
If the Safety Limit for PCS pressure is exceeded, Technical Specification 6.7.1 requires *
- c. the reactor to be shutdown imaediately.
- b. PCS pressure
+.o be reduced to noniinal operating pressure immediately.
c.
the reactor to be placed in cold shutdown within si:: hours.
d.
the reactor to be placed in hot stanoby within one hour.
(*****
CATECORY 08 CONTINUED ON NEXT PAGE
- )
8.
ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 21 OUESTION B.26
(.50)
Any time the specific activity of the PCS exceeds _____ microcuries per groa dose equivalent iodine 131 or the specific activity of the secondary-coolinf. in a steam generator exceeds _____ siicrocuries per gram, the reactor must be shutdown within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
c.
- 1. 0 '; 1.0 b.
40.0; 1.0 c.
1.05 0.1 d.
40.0; 0.1 00ESTION 8.27
(.50)
When PCS temperature is below 250 F a _____ high pressure safety injection pump (s) shall be operable.
- c. niinisium ~ of one b.
niinimum of two
.c.
manimum of one d.
nia n i mu m of two GUESTION 8.28
(.50)
Tha reactot can not be maintained above 2% power for more than one hour n,unless _____ safety inje.: tion tank.s and _____ secondary system safety Evalves are operable.
- e. 31 23 b.
41 23 c.
31 24
- d. 4; 24
(***** CATEGORY 08 CONTINUED ON NEXT PAGE ummax)
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8, ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 22 QUESTION 8.29
(.50) l Which of-the following radioactive liquid monitors is addressed in Tcchnical Specification Table 3.24-1?
o.1 Steam generator blowdown monitor (RE-0707)
- b. Failed Fuel Monitor (RE-0202)
I
- c. Component Cooling Water Monitor (RE-0915) 1
-d.
CirculatinS Water Discharge Monitor (RE-1323) l QUESTION 0.30
(.50)
What is the quarterly whole body radiation expcsure ada.inistrative lin.it c 17 year old employee?
- a. O n r e n.
b.
300 mrem
- c. 500 mreni d.
1250 mrent OUESTION 8.31
(.50)
The _____ must be activated for an Alert, but the _____ need not be ectivated for an Alert.
- o. EOFi TSC
- b. TSCi OSC
CATEGORY 08 CONTINUED ON NEXT PAGE
- )
i 8.
ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 23 QUESTION 8.32
(.50)
Which of the followins individuals will be located in the OSC?
- o. R.4diation Protection Supervisor b.
Reactor Engineer j
c.
Plant Operations Manager d.
Plant Operations Superintendent DilESTION 8.33
(.50)
Formission of the _____ is required prior to exceeding 10 CFR 20 dose licits during an emergency.
The emergency whole body radiation exposure limit for lifesaving actions i s _ _ _ _ _ REM 0.
Radiation Protection Supervisori 25 b.
Radiation Protection Supervisori 75 c.
Site Emergency Directori 25 d.
Site Emergency Directori 75 y
OUESTION 8.34
(.50)
True or False.
Potassium Iodide is a safety option provided to emergency workers -- they are not required to take it.
DUESTION 8.35
(.50)
Any valve may be locked with the approval of the _____.
- c. Shift Engineer
- b. Shift Supervisor c.
Operations Superintendent
- d. Engineering and Maintenance Manager (mxxxx CATEGORY 08 CONTINUED ON NEXT PAGE mummm) o i
m 8.
ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 24 QUESTION 8.36
(.50)
If, durin3 the performance of a System Checklist, a breaker is found to be iniproperly positioned, the _____ shall authorize it to be placed in its preper position.
- c. Shift En3ineer b._ Shift Supervisor
- c. Operations Superintendent d.
Plant Manager GUESTION 8.37
(.50)
All caution tags issued shall be controlled by the Caution Tas Los, encept those placed and removed in accordance with' O.
switching and tassins orders.
b.
maintenance orders.
c.
equipnient outage r equests,
d.
Technical Specification surveillance tests.
QUESTION 8.38
(.50)
All nuclear safety related interlocks / bypasses shall be approved by the except those _____.
- c. Plant Manager or Duty and Call Superintendenti left in place shorter than one shift.
b.
Plant Manager or Duty and Call Superintendenti installed usins built-in bypass controls.
c.
Shift Engineer or' Shift Supervisori left in place shorter than one shift.
d.
Shift En3 neer or Shift Supervisori installed usins bullt-in bypass i
controls.
(mmmmm CATEGORY 08 CONTINUED ON NEXT PAGE maamm)
8.
ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 25 QUESTION 8.39
(.50)
Trua or False.
Urgent maintenance is assigned a priority of 1 or 2.
QUESTION. 8.40
(.50)
Ad2inistrative Procedures prohibit caution tags froni being used to' O.
document a teniporary setpoint for installed plant equipsient.
b.
identif y equipnient which is unreliable.
c.
identify jumpers, links and bypesses.
d.
identify plugged floor drains.
QUESTION 8.41
(.50)
True or False.
CPIT stickers shall be used in place of caution tags on control-panels because caution ta3s could obstruct other indications.
QUESTION 8.42
(.50)
The quarterly verification of specified Red Works.en's Protective Tags siay ba waived by the __ __ if _____.
- c. Operations Superintendenti operability tests are perfornied on the specific con.ponent.
- b. Operations Superintendenti significant radiation exposure would result.
c.
Shift Supervisori operability tests are performed on the specific component.
d.
Shif.t Supervisori significant radiation exposure would result.
(**xxx CATEGORY 08 CONTINUED ON NEXT PAGE xxxxx)
8.
ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 26 QUESTION 8.43
(.50)
WhGn immediate action is required for unplanned work of short duration, paraission of the _____ is needed to authorize entry into a radiation centro 11ed area without an RWP.
Entry is permissible if _____.
c/ Duty and Call Superintendent or Health Physics Superintendenti dedicate.
Radiation Safety Technician coverage is provided.
- b. Duty and Call Superintendent or Health Physics Superintendenti an ALARA review is performed prior to the entry,
- c. Radiation Safety Supervisor or Shift Supervisor; dedicated Radiation Safety Technician coverage is provided.
d.
Radiation Safety Supervisor or Shift Supervisori an ALARA review is performed prior to the entry.
QUESTION 8.44
(.50)
Dose to fertile females shall be restricted to a manimum whole body dose of 500 mrem during any _____.
Females are to be considered _____ unless documented evidence to the contrary is received.
- o. quarteri fertile b.
quarteri infertile
- c. nine month periodi fertile d.
nine month periodi infertile QUESTION 8.45
(.50)
Thz secondary dosimetry device used to monitor whole body gamma radiation dose is the _____.
Operations personnel are _____ issued neutron TLDs.
- c. secondary TLDi normally
- b. secondary TLDi rarely
- c. pocket dosimeter; normally d.
pocket dosimeteri rarely (mumm
- CATEGORY 08 CONTINUED ON NEXT PAGE muzzz) 4
8.
ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 27 GUESTION 8.46
(.50)
Parmission to e>:ceed a whole body radiation dose of 5000 mres, per year roquires the approval of the Plant General Managere.the _____ and the Vice Prosident of Nuclear Operations.
t.
Radiological Services Manager Rb. Health Physicist Superintendent
- c. Director of Radiolo3ical Services
- d. Radiation Safety Supervisor QUESTION 8.47
(.50) ltue or False.
If a confined area is not on the list of confined spaces posted in the control room, a confined space entry permit is not needed to enter it.
QUESTION 8.48
(.50)
If an individual is required to enter a confined space in an emergency, he shall do all of the followins EXCEPT _____.
c.
notify the Shift Supervisor.
b.
complete a confined space entry permit.
c.
use an approved self contained breathing apparatus.
d.
wear a harness with an attached lifeline.
QUESTION 8.49
(.50)
Steps requiring inspection by a Radiation Safety Technician are designated by!
a.
a lower case
'e'.
b.
the word HOLDPOINT.
- c. the word CAUTION.
d.
a circle
'R*.
(***** CATEGORY 08 CONTINUED ON NEXT PAGE muxus)
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ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 28
_____~____________________________________________________
M QUESTION 8.50
(.50)
-Tha word NOTE is used to:
- a. specify contin 3ency action which may have to be taken.
b.
provide supplemental information.
c.
identify hazards to equips.ent.
d.
denote hazards to personnel.
9
(***** END OF CATEGORY 08 *****)
(************* END OF EXAMINATION ***************)
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MA5 FER 5.
THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 29 ANSWERS -- PALISADES
-85/07/09-HIGGINS, R.
ANSWER 5.01 (2.00)
Fr.om Figure 5.p, baron worth is 90 ppm per percent $#.
Since criticality was attained 70 ppm too early, the discrepancy between predicted and actual critical condition is (70) x (1%)/(90) = 77.8% dj0, which is equivalent to en orror of.00778.
( 1.,0 )
This error is greater than.0075, so the operator should maintain reactor pow 2r below 10-4% and recheck criticality calculations, boron concentration cnd control rod positions.
(1.0)
REFERENCE GCL 3 step 2.3.3 ANSWER 5.02 (2.00)
- 1. Power level atwhichthereacy.or is considered critical for administrative control is 10-(.5)
- 2. Lowest power level for power operation is 2%. (.5) 3.
P = P,10 exp (SUR x time)
(.2) 4.
P/P, 10 exp (SUR x time)
(.2)
=
5.
los P/P,
= SUR x time
(.2)
(los 2/10'Y)(1/.75)
(.2)
- 6. time = (los P/Pe)(1/SUR)
=
7.
time = 4.3/.75 = 5.73 minutes
(.2)
REFERENCE Technical Specification 1.1 Reactor Theory, Chapter 16, p 6.4-2 ANSWER 5.03 (1.50)
Centrol rod worth increases.'(.5)
Fuel burnsout and boron concentration is roduced (.5), making the core less absorptive and the rods relatively more absorptive. (.5)
REFERENCE Rocetor Theory, Chapter 20, p 9.5-1 l
n 4
15. - THEORY OF NdCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 30 gggggggggggggg--------------------------------------
ANSWERS -- PALISADES
-85/07/09-HIGGINS, R.
ANCHER 5.04 (2.00)
- c. Shutdown margin-(.33); individual rod worth (.33);
1 hot channel factors (.34) b.
When it.is necessary to rapidly reduce power.to avoid or minimize a situation harmful to plant personnel or equipment. (.5)
R
- md
^
ga(Hl)
- c. 43% inserted on Group 2 (Tech Spec); or so
,(5 70 inches withdrawn on Group 2 (Tech Spec); or CnpflAtave i
8 inches withdrawn on Group 3 (Data Logger); or
' ~ ' - ~ ~
88 inches withdrawn on Group'2-(Data Lo3Ser)
(.5)
REFERENCE.
. Technical Specification 3.10 Basis al 3./CV7 b.
- c. Technical Specification Figure 3-6 Technical Data Book, Figure 1.9 ANSWER 5.05 (1.50)
Core geometry becomes. altered-(.75) and boron can be removed from the core CS temperature falls or as coolant boils off. (.75)
REFERENCE Mitigation of Core Damage, p 12 ANSWER 5.06 (1.00)
- c. When power exceeds 50%. (.5)
- b. Place the reactor in hot standby within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. (.5)
REFERENCE.
Technical Specification 3.23.3
5.
THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 31 ANSWERS -- PALISADES
-85/07/09-HIGGINS, R.
ANSWER 5.07 (2.00)
Equilibrium xenon worth at power is not a linear function of power, since xenon burnout increases as power increases. (.5)
Peak xenon after a trip occurs because of the continuing production of xenon from iodine decay and the absence of xenon burnout. (.5)
Since the equilibrium value of iodine 135 is nearly a linear function of power, the iodine 135 inventory at 100% power will be almost twice as great as the inventory at 50% power. (.5)
With twice as much iodine to decay, xenon peak reactivity after a trip from 100% power will be almost twice as great as the peak after a trip from 50%
power. (.5)
REFERENCE Technical Data Book, Figure ?.2 Reactory Theory, Chapter 20, p 10.3-1 ANSWER 5.08 (1.00)
Plutonium 239, which builds up after a trip due to the decay of Neptunium 239.
REFERENCE Reactor Theory, Chapter 21, p 11.2-2 ANSWER 5.09 (1.00)
Lithium hydroxide made from natural lithium contains lithium 6 (.5), which has a high absorption cross section for thermal neutrons and will split into an alphe particle and tritium if it absorbs a neutron. (.5)
REFERENCE System Lesson Notes 46, p3 ANSWER 5.10 (1.00)
- 1. Displacement of lithium 7 from the cation resin of the mixed bed purification ion exchanger. (.F)
- 2. Absorption of a neutron by boron 10 and its subsequent decay by alpha emission. (.5)
5.-
THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 32 y
3 ANSWERS -- PALISADES
-85/07/09-HIGGINS, R.
REFERENCE System Lesson Notes 46, p 22 ANSWER 5.11 (2.00) 2.
Hydro 3en needs samma rays to cause it to react with oxygen. (.5)
The gamma flux after the reactor has been shutdown an appreciable length of time is too low to cause the hydro 3en to combine with the oxygen. (.5)
'b.
Hydra ine will decompose at.high temperatures. (.5)
Hydrazine which does not decompose will be completely removed by the purification ion
.enchangers. (.5)
REFERENCE Systen. Lesson Notes 46, p 7 ANSWER 5.12 (1.00)
Two of the following*
1.
High' power (.5)
- 2. Low PCS flow (.5)
- 3. TMLP (.5)
REFERENCE Technical Specifications 2.3.1, 2.3.2 and 2.3.4 ANSWER 5.13 (1.00)
- o. 230 F (.5)
.b.
310 F (.5)
REFERENCE EOP 8.1-step 3.5.d Steam Tables ANSWER 5.14 (1.00)
Available NPSH decreases (.5)
Raquired'NPSH increases (.5)
I b
"i.
THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 33 ANSWERS --' PALISADES
-85/07/09-HIGGINS, R.
REFERENCE Wastin3 house Thermal Hydraulic Principles and Applications to the PWR II,
'p 10-56
' ANSWER 5.15 (1.00)
A condition of siaximium flow in a pump occurrins when the punip head equals 2000.
REFERENCE Westinghouse Thernial Hydraulic Principles and Applications to the PWR II, p 10-81 ANSWER 5.16 (1.00)
Two of.the followins*
- 1. excessive noise (.5)
- 2. excessive vibration (.5) 3.
Iow suction pressure (.5)
~
4.
fivetuatins punip an;ps (.5)
U. fivetuatins dischar3e Pressure
(.5) 6.
e::cessively low flow (.5)
REFERENCE-Westinshouse Thermal Hydraulic Principles and Applications to the PWR II, p 10-54 l
l ANSWER 5.17 (1.00)
Fast neutron irradiation of the reactor vessel will raise its reference transitinre temper atur e.
l REFERENCE l
Technical Specification 3.1.2 i
ANSWER 5.18 (1.00)
Boiling in the core such that steani flows through the hot les to the steani Sonerator tubes, condenses into a liquid, then flows back down the hot Ics into the core.
5.
THEORY OF. NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 34
'NSWERS -- PALISADES
-85/07/09-HIGGINS, R.
A REFERENCE'
. Natural Circulation Lesson Plan, Drawins 41
-ANSWER
- 5 19
- (1.00)
~ Core geometry may be disturbed, blocking flow through the core.
REFERENCE' Mitisation of Core Damase, p 12 o
D
6.
PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 35 ANSWERS -- PALISADES
-85/07/09-HIGGINS, R.
ANSWER 6.01 (1.00)
S/G pressure (.33)
Low PCS flow (.33)
T6LP (.34)
REFERENCE Exam 43 Key, Module 28b, question 4.b System Lesson Notes $14, p 23 ANSWER 6.02 (2.00)
- a. Baronometer (.5)
- b. Startup range channel (.25) and Wide ranSe channel (.25)
- c. Power ranSe channel (.5) d.
Incore detector (.5)
REFERENCE System Lesson Notes 46, p 20, and til, p 8, 11 System Lesson Plan 28a, p 1
' ANSWER 6.03 (1.00)
.Incore temperature at the. axial location exceeding 600 F.
REFERENCE Mitigation of Core Damage, p 25 ANSWER 6.04 (1.00
- a. No effect (ground detector circuit indication) (.5)
- b. Initiates a trip (.5)
REFERENCE System Lesson Notes $14, p6 l
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6.
PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 36 ANSWERS -- PALISADES
-85/07/09-HIGGINS, R.
ANSWER 6.05 (2.00)
- 1. Limit backflow throV3h an idle pump (.5),
thus reducing core bypass flow. (.5) 2.
Prevent starting a pump which is reverse rotatins (.5),
limiting the amount of time the motor experiences starting current. (.5)
REFERENCE Polisades NOTD' exam 41, Mod 24d, question 2 ANSWER 6.06 (1.00)
Lotdown line relief (RV 'J006) (.33)
Sofety injection tanks drain relief (RV-3161) (.33)
Shutdown cooling relief (RV-3164
(.34)
E EN
/
3 M-201 sheet 3 '
Y ANSWER 6.07 (1.00)
To reduce the amount of water which must be processed by the radwaste cystem.
REFERENCE System Lesson Plan 25a, p 15 ANSWER 6.08 (1.00)
Protect the piping between the shutdown cooling isolation valves (.5) from prossure developed due to a sudden temperature increase inside of'the containment. (.5)
REFERENCE System Lesson Notes 49, p 11
6.
PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 37
-ANSWERS -- PALISADES
-85/07/09-HIGGINS, R.
ANSWER 6.09 (2.00)
- o. When the plant is operatin3 above 557 F Tavs (.5) at the time of a turbine trip. (.5)
- b. The narrow ranse temperature instrument is used, which has a minimun.
output corresponding to 515 F.
(1.0)
REFERENCE Systeni Lesson Notes $18, System Functional Description 5.3, p 13 and 14 ANSWER 6 10 (1.00)
Foodwater regulatin3 valves fail as is (.5), while the feedwater pump turbines ramp down to a speed adequate for excess heat removal. (.5)
REFERENCE System Lesson Notes 417, p3 ANSWER 6.11 (1 50) 1.
5 seconds after the AFAS, pump F8A starts (.5) 2.
If PBA fails to start or flow is less than 50 spm within 15 seconds of the AFAS, pump PBC starts (.5) 3.
If P8C fails to start of if flow is less than 50 spm within 80 seconds after the AFAS, the steam control valves for P8B set an open signal (.5)
REFERENCE System Lesson Plan 19b, p8 ANSWER 6.12 (1.00)
Water flows out the bottom blowdowns (.2), through the steam senerator blowdown pumps
(.2), the blowdown heat exchanger
(.2), the 43 demin (.2) cnd back into the steam senerator at the former surface blowdown connection. (.2)
REFERENCE System Lesson Notes 428, p6 e
l l
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c 6.
PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 38 ANSWERS -- PALISADES
-85/07/09-HIGGINS, R.
ANSWER 6.13 (1.50)
- 1. P-52A and B start after 23 seconds (.5)
- 2. P-52C is placed in standby after 40 seconds (.5), then starts if
-pressure is less than 80 psis (.5)
REFERENCE Syetem Lesson Plan 15b, p.7 ANSWER 6.14 (1.00)
Containment hiSh pressure (.5) and Safety Injection (.5)
REFERENCE System Lesson Plan 15a, p8 ANSWER 6.15 (2.00)
- c. Hydrazine - to enhance iodine removal by containment spray (.5)
Sodium Hydroxide - to raise the pH of the recirculated water to enhance iodine retention (.5)
- b. Hydra:ine - added at the initiation of containment spray (.5)
Sodium Hydroxide - added during recirculation (.5)
REFERENCE System Lesson Notes _426, p 2 and 4 ANSWER 6.16 (1.00)
P9A - 90 psi 3 Fire System Header Pressure (.33) 50
(.33)r6{f4"1F
(.33) ed P90 - 75 psis Fire System Header Pressure P41 - 60 psis Fire System Header Pressure REFERENCE System Lesson Notes $34, p 17 30P-3lQ 7.l ANSWER 6.17 (1.00)
Tho teflon rin3s will release toxic fumes.
l l
6.
PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 39 ANSWERS -- PALISADES
-85/07/09-HIGGINS, R.
REFERENCE Systes.. Lesson Notes $27, System Functional Description 6.2.1, p6 ANSWER 6.18 (1.00)
Insure service water pressure is Greater than seal oil pressure in case os o leak in the seal
- t--
heat exchanger.
Af REFERENCE Syotem Lesson Plan 15a, p 11 ANSWER 6.19 (1.00)
To provide carbon dioxide for pursins the main senerator of air prior to fillins with hydro 3en (.5) and purgins the main senerator of hydrogen in cece it is necessary to open the generator f o r m a i n t e n a nc e. (,'I)
REFERENCE Systeni Lesson Notes $31, p 15 ANSWER 6.20 (1.00)
Loss of generator excitation (.33)
Overload (.33)
Generator differential relay action (.34)
REFERENCE System Lesson Notes $33, p 15 qty. E t 7, M a.
M e%L n $
I f
i l
r-7.
PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 40 RA656E66 CAE~C6UTE6L'~~~~~~~~~~~~~~~~~~~~~~~
~~~~
ANSWERS -- PALISADES
-85/07/09-HIGGINS, R.
ANSWER 7.01 (1.50)
No. (.5)
Shutting valves may:
- 1. damase system components (1.0) 2.
increase leakage (1.0) 3.
increase personnel exposure (1.0)
Any one of the three explanations, or other reasonable e:.planation, will be awcrded full credit.
REFERENCE Adain Proc 7.00 step 2 0.a.1 ANSWER 7.02 (1.00) 1.
Proceed to the change room at access control (.5)
- 2. Perform a whole body frisk (.5)
REFERENCE Adain Proc 7.00 step 5 0.b n
ANCWER 7.03 (2.00) 1.
An inverse multiplication plot must be used if only one startup detector is operable (.5)f it is optional if 2 startup detectors are operable (.5).
REFERENCE GCL 3 steps 2.3 and 2.4 ANSWER 7.04 (1.00)
LoS the time, differential temperature and pressurizer pressure in the rocetor logbook.
REFERENCE SOP 1 step 4.0.m l
7.
PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 41
~~~~~~~~~~~~~~~~~~~~~~~~
~~~~ 5656E66565E~C6UiR6L R
CNSWERS -- PALISADES
-85/07/09-HIGGINS, R.
1 CNSWER 7.03 (1 00)
Orso of the following situations:
1.' PCS pressure is below 300 F and 400 psi
=2.
shutdown cooling isolation valves MO-3015 and 3016 are open
- 3. shutdown cooling cooling system is in service REFERENCE SOP 1 step 4.0 9 SDP 3 step 4.0 9 ANSWER 7.06 (2 50)
- o. 250 psia
- b. 250 F
- c. 32 F.
- d. 3.75%
- o. 1250 psia REFERENCE SOP 1 steps 4.0.c, 4.0.o, 5.0.e, 5.0 9 E0P 8 1 step 3 3 ANSWER 7.07 (1 00) notify the chemical laboratory to sample the steam generators for activity
(.5) rocord in the control room logbook the length of time the dumps are open
(.5)
REFERENCE SDP 7 step 5.0.d ANSWER 7.00 (1.50)
Provent dumpin3 the contents of the component coolin3 system directly into l
tho lake.
i l
l l
\\
l l
6 6
7.
PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 42
~~~~~~~~~~~~~~~~~~~~~~~~
RA656L66fCAE~66NTR6L
~~~~
ANSWERS -- PALISADES
-85/07/09-HIGGINS, R.
REFERENCE SDP 15 step 5.0 AliSWER 7.09 (1.00)
Ovorpressurization and rupture of the tank con occur if the vent is plugged with buric acid.
REFERENCE SDP 17A step 5.6 ANSWER 7.10
-(1.00)
Provent drawing a vacuum and imploding the safety injection tank.
REFERENCE SOP 3 step 7.5.4.a ANSWER 7.11 (1 50)
Provent. overflowing the spent fuel pool.
REFERENCE SDP 77 ster 6.1.5.10 ANSWER 7.12 (1 00)
A control rod is too light.
REFERENCE SDP 20 step 5.5 ANSWER 7.13 (1.00)
To maintain a load on the turbine to slow it down faster.
OR To maintain main generator eueitation in order to keep the primary coolant pumps energized so PCS flow will be maintained longer.
l l
l
l-L 7.-
PROCEDURES - NORMAL,-ADNORMAL, EMERGENCY AND PAGE 43
~
-~~~-----~------~~~-----
~~~~ 5656E665E5L C60iR5L R
ANSWERS -- PALISADES
-85/07/09-HIGGINS, R.
REFERENCE E0P 1 step.3 System Lesson Notes 433, p 5-ANSWER 7.14 (1.00)
- 11. wide range level below -1257. (.5)
- 2. steam generator pressure below the saturation pressure of the PCS (.5)
REFERENCE E0P 1 step 4 7 ANSWER-7.15 (1.50)
- a. 30 spm (.5) b.
Trip the charging pumps one at a time until the flow rate of the running HPSI pumps exceeds 30 spni. (.5)
If all charging pumps are tripped and HPSI flow remains below 30 spm, trip one HPSI pump if both are running and is needed. (.5) uEr(h&orietf a H MZ,W ll')
i E0P 8.1 step 4.15.b.1 L,
SOf 3,+D P 7 8 l G
l ANSWER 7.16 (1 00)
Provent the introduction of noncondensable gases into the PCS.
REFERENCE EDP 8.1 step 4 16 ANSWER 7.17 (1.00)
Run at least one HPSI pump and open both pressurizer PORVs.
REFERENCE E0P 8 1 attachment 6 i
i.
i h
l
7.
PROCEDURES'- NORMAL, ABNORMAL, EMERGENCY AND PAGE 44
~~~~E5656L665C5L C6 TR6L
~
~~~~~~~~~~~~~~~~~~~~~~~~
ANSWERS -- PALISADES
-85/07/09-HIGGINS, R.
1 ANSWER 7.18 (1.00)
-Provent dilution of the PCS REFERENCE E0P 8.2 step 4.7 ANSWER 7.19 (1.50)
'o.
Loss of Instrument Bus YO1 (.5) b.
1.
Trip the reactor (.25)
- 2. Isolate letdown (close CV-2001) (.25)
- 3. Close the primary coolant pump controlled bleedoff containment isolation valve (CV-2083) and insure the primary coolant pump controlled bleedoff relief,stop valve (CV-2191) is open. (.25)
- 4. Activate the site emergency plan (.25)
REFl:RENCE ONP 24 5 step 3.0 ANSWER 7 20 (1 00)
Roduce inventory loss out of a hot les break.
REFERENCE Mitigation of Core Dama3e' P 33 i
e
~.
8.
ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 45 ANSWERS -- PALISADES
-85/07/09-HIGGINS, R.
ANSWl:R 8.01
(.50) c-REFERENCE Toch Spec 1 4 ANSWER 8.02
(.50) b REFERENCE Stending Order No. 8 ANSWER 8 03
(.50) d REFERENCE t
Stcnding Order No. 14, 2.A and C ANSWER 8.04
(.50) d RLfERENCE Stonding Order No. 14, 3.C ANSWER 8.05
(.50) 0 REFERENCE Standing Order No. 14, 3.A C.NSWER 8.06
(.50) b
r l
l 8.
ADMINISTRATIVE PROCEDURESe CONDITIONSe AND LIMITATIONS PAGE 46 ANSWERS -- PALISADES
-85/07/09-HIGGINSe R.
REFERENCE Stcnding Order No. 18 ANSWER 8.07
(.50) 0 REFERENCE Standing Order No. 22 ANSWER 8.08
(.50)
False REFERENCE Standing Order No. 35 ANSWER 8 09
(.50)
Folse l
REFERENCE Standins Order No. 35 ANSWER 8 10
(.50) l c
REFERENCE
'Standin3 Order No. 40 ANSWER 8.11
(.50)
O REFERENCE Standin3 Order No. 41 I
l
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_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _' L I M I 8.
ADMINISTRATIVE PROCEDURES, CONDITIONS, AND PAGE 47 CNSWERS -- PALISADES
-85/07/09-HIGGINS, R.
, ' 's X
'. ANSWER 8.12
(.50) c REFERENCE Stending Order No. 41 ANSWER 8 13
(.50)
L d
l s
. REFERENCE Standing Order No. 43 b'
h s
t ANSWER-8.14
(.50)
)'
i" b
REFIREHCE
' 's
('
Stendin3 Order No. 44 i
t s
ANSWER 8 'e 15
(.50) t -b y
s d
],_
REFERENCE Stcoding Order No. 52 t 3.
ANSWER'4T 8.16
(.50)
O s
REFERENCE Standing Order No. 55 ANSWER B.17
(.50) d e
L k
r
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k
(
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l' 8.
ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 48 I'
CNSWERS -- PALISADES
-85/07/09-HIGGINS, R.
t REFERENCE Tcchnical Specification 3.0.3 ANSWER 8.18
(-.50) l Felse REFERENCE Tochnical Specification 3.0.4 CNSWER 8.19
(.50) c REFERENCE Stending Order No. 54, 3.4 1; Tochnical Specifications 1 1,
3.6 1.a ANSWER B.20
(.50) d REFERENCE Stendin3 Order 54, 3.6 ANSWER 8.21
(.50) b
-REFERENCE Storidin3 Order No. 54, 3.7 1 ANSWER 8 22
(.50) c n
REFERENCE Standing Order No. 54, 3.7 1 50f 30 7, l. I
i 1
8.
ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 49 ANSWERS -- PALISADES
'-85/07/09-HIGGINS, R.
ANSWER 8.23
(.50) d REFERENCE Technical Specifications 1.1 and 3.8.1 i
Stending Order No. 54, 3.8.1.1 and 3.14.1 l
l ANSWER 8.24
(.50) c REFERENCE Stending Order No. 54, Table 3.17.4, Numbert 23 and 24 Technical Specification Table 3.17.4, No. 9 ANSWER 8.25
(.50) a REFERENCE
~
Technical Specification 6.7.1 ANSWER 8.26
(.50) d REFERENCE Tochnical Specifications 3.1.4 and 3.1.5 ANSWER 8.27
(.50) c REFERENCE Technical Specification 3.3.2.s
~
'I
I 8.'__ ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 50 ANSWERS -- PALISADES
-85/07/09-HIGGINS, R.
l l
l ANSWER 8.28
(.50) b REFERENCE Technical Specification 3.1.7.c and 3.3.1.b ANSWER 8.29
(.50)
- ~1 h e
REFERENCE Technical Specification Table 3.24-1 Systen Lesson Notes #38, p 18 sM Wit <>n Gik 4..:L. I, & I ANSWER 8.30
(.50) a REFERENCE Adain Procedure 7.04 step 5.1.b ANSWER 8.31
(.50) d REFERENCE Site Esiergency Plan, 3.0 ANSWER 8.32
(.50)
C REFERENCE Site Esiersency Plan 5.3.3 l'-
8.
ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 51 ANSWERS -- PALISADES
-85/07/09-HIGGINS, R.
' ANSWER 8.33
(.50)
'd REFERENCE
-EI -'12.3 step 5.8 ANSWER 8.34
(.50)
True REFERENCE EI - 12.3 step 5.9.2 ANSWER 8.35
(.50) c REFERENCE Admin Proc 4.02 step 5.1.e ANSWER 8.36
(.50) b REFERENCE Admin Proc 4.02 step 7.2.1 ANSWER 8.37
(.50) d REFERENCE Admin Proc 4.03 step 8.1 ANSWER 8.38
(.50) b
8.
ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 52 ANSWERS -- PALISADES
-85/07/09-HIGGINS, R.
REFERENCE Adain Proc 4.03 step 9.2 ANSWER 8.39
(.50)
False REFERENCE Adain Proc 5.01 step 8.2 ANSWER 8.40
(.50) d REFERENCE Adain Procedures 4.03 steps 8.0, 9.1.1.b and 9.2, and 5.05 step 5.1 ANSWER 8.41
(.50)
Felse REFERENCE Admin Proc 4.03 step 11.0 ANSWER 8.42
(.50) b REFERENCE Adain Proc 4.03 step 6.5.2 ANSWER 8.43
(.50) c REFERENCE Adain Proc 7.03 step 5.3 h
8.
ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 53 ANSWERS -- PALISADES
-85/07/09-HIGGINS, R.
ANSWER 8.44
(.50) c REFERENCE Adain Proc 7.04 step 5.2.a ANSWER 8.45
(.50) e REFERENCE Admin Proc 7.04 steps 5.3.2.a and 5.4.d ANSWER 8.46
(.50) c REFERENCE Admin Proc 7.04 Table 1 ANSWER 8.47
(.50)
False REFERENCE Admin. Proc 8.07 step 5.1
-ANSWER 8.48
(.50) b REFERENCE Admin Proc 8.07 step 9.3 ANSWER 8.49
(.50) d
8.
ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 54 ANSWERS -- PALISADES
-85/07/09-HIGGINS, R.
REFERENCE Adain Proc-10.41 step 5.6 ANSWER 8.50
(.50) b REFERENCE 2
Admin Proc 10.41 step 5.6 e
-g-., - -. -, -
m
i CONSUMERS POWER CQ:PANY NUCLEAR TRAINING CENTER Instructor I,esson Plan Proy,,ra:n
Title:
Nuclear Operator Training Lesson Plan N5. SRO 7/3/85 SRO Requal Exam & Key Course :
Sketion 5 Fbdule:
Topic:
0 Ravision:
fh,'&
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. Ie#1msa 7/1/85 Date Crigira. tor
~
R. B oo i 7/2/85 Suojet Matter - Technical (./eviewer Date B. Doty Lu Uu b[// D 7/2/85 i
Approved - Training Supervisor Date 6
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PERSONAL AND CONFIDENTIAL NOTD EIAMINATION COVER SEEIT Social Security No Name Please Circle 06*02 CF Co Employee consumerhowerCompany WN M*03N M Q W e Company Work Location _
Palisades EIS Wo 600421 D;p rtment Annual Requal Exam UTI No 06*2';/19 Cours3 7/3/85 Ezam No _
1 of~
1 Class No Instztactor Revarification.
l Dato Administered 7/3/85 Administered by NRC Graded by i
D ta Graded Gr:dc "Chocting on osans sha'11 be cause for disciplinary action in accordance with the applicable All incidents of cheating shall be reported to the cogni General Order or Working Agreement.
sant supervisog(s) and the Director - Nuclear Operations Training Department, and shall resul in immediate forfeiture of the student's exam."
I was given the opportunity to review the correct responses to this avamination.
Signed Date
EQUATION SHEET f = ma v = s/t Cycle efficiency = (Network ut)/(Energy in)-
2
- V t + 1/2 at w = ag2 o
x E = sc A = A,e '
KE = 1/2 av a = (V - V,)/t A = AN f
PE = agn Vf = V, + at w = O/t A = An2/t1/2 = 0.693/t1/2 W = v AP t
eff =
1/2 b d 1/2
[(t1/2)
- IE ))
b AE = 931 on I = I,e"
~E*
h=aCpat I = I,e h = UAAt I = I,10 */
~
Pwr = W ah TVL = 1.3/p f
EVL = -0.693/p sur(t)
P = P,e"I SCR = S/(1 - K,ff)
SUR = 26.06/T CR,= S/(1 - K,gg,)
(1 - keff2)
SUR = 26p/1* = ($ - p)T CR3 (1 - K,ff g)=CR2 T = (1*/p) + [($ - p)/Xp]
M = 1/(1 - K,ff) = G /CR, 3
T = t*/p M = (1 - K,ff,)/(1 - K,ffy)
T = (S - p)/(h)
SDM = (1 - K,gg)/K,gg
-5 1* = 10 seconda P*I eff"I)/Ieff eff/ eff
~1 E = 0.1 seconds p=[(1*/(TK,ff)],+[J,ff(1+XT)]
/
91 Id 22 P = (I$V)/(3 x 1010) 2 Id
=Id gg 22 I = UN R/hr = (0.5 CE)/d (meters)
R/hr = 6CE/d (feet)
Water Parameters Miscellaneous Conversions 10 1 gal = 8.345 lba 1 curie = 3.7 x 10 dps 1 kg = 2.21 lba 1ga}=3.78 liters 3
1 ft = 7.48 gal 1 hp = 2.54 x 10 Stu/hr 3
1 aw = 3.41 x 10 Btu /hr Density =62.4lbg/ft Density = 1 sm/cm 1 in = 2.54 cm Heat of vaporizat.fon = 970 Btu /lba (At Ata, Press)
- F = 9/5'c + 32 Heat of fusion = 144 Btu /lba
'C = 5/9 (*F-32) 1 BTU = 778 ft-lbf 1Ata=14.7 psi =29.9{nHg 1 ft H,0 = 0.4335 lbf/gn l
R An HE - 0.491 lbf/in
SECTION 5 SRO EXAM 5.1 State the reason for overlap of control rod groups 1-4 for withdrawal
-and insertion.
(1.0)
.47 5.2 State three (3) reasons why tritium is more of a problem than other radioactive isotopes found in the plant.
(1.0) n o,
5.3 For EOC conditions, is there a difference in the net reactivity for a l'F.
change in moderator temperature where the moderator temperature is 70*F.
as opposed to 500*F.? If there is a difference, at which temperature is the most negative reactivity inserted?
(1.5) 5.4 What effect does the buildup of Pu-239 over core life have on reactor control for equal reactivity additions at BOC and EOC?
(1.0) 5.5 State three (3) reasons for control rod power dependent insertion limits.
(1.5) 5.6' a.
Is the reciprocal boron worth greater at the BOC or EOC?
(.75)
- b. Does fuel temperature defect become more negative, or less negative over core life?
(.75) 5.7 List three ways in which gammas react with matter.
(1,0) 5.8 True or False (1.5) a.
The leak rate from a closed system can be reduced by reducing pressure within the system.
b.
The definition of enthalpy is the sum of internal energy.and ex-ternal energy of a substance.
c.
The definition of natural convection is heat flow as a result of density changes in a working fluid.
-5.9 With the plant operating at 100 percent power, the water level in SA and B feedwater heaters (shell side) increases above the normal control level, would you expect tha temperature of the water exiting the tube side to remain constant, increase or decrease?
(.5) mi0785-0002a-tab
---~r-~--,
,-w--
-c-,
-v--
,-r.-
.,,,r-,
s,
-v
5.10 True or False Pump discharge head is proportional to the change in speed
(.5)
/
squared for a centrifugal pump in a system.
b.
Neutron flux causes steel in the reactor vessel to become more ductile at given temps.
(.5)
^
5.11 In regards to a restriction type flow measuring device, the following questions deal with the relationship of flow to pressure and pressure to velocity.
Which of the following accurately describes the relationship between a.
flow and pressure through the restriction?
(.5) 1.
Flow = A Pressure Flow = APressure 2
3.
Flow = Pressure 4.
Flow = (APressure b.
Which of the following describes the relationship of Pressure (P) and Velocity (V) through a restriction?
(.5) 1.
Pt V+
2.
P+ Vt 3.
P+ V+
4.
Pt Vt 5.12 List the two Reactor Protection System trips which protect against
~
Departure from Nucleate Boiling.
(1.5) 5.13 Indicate for the following events if the Cooling Tower pump motor amps will increase, decrease or remain the same.
a.
Increase cire.ulating water temp by 20*F.
(.25)
'N b.
Decrease in voltage on
'F' and 'G' busses.
(.25)
.t c.
Increase in Stator Temp.
(.25)
,V-d.
Throttle discharge valve to increase pump suction basin level.
(.25)
C mi0785-0002a-tgb
SECTION 5 SRO EXAM KEY 5.1 State the reason for overlap of control rod groups 1-4 for withdrawal and insertion.
(1.0)
ANSWER To allow a smooth and continuous rate of change of reactivity or prevent the rates of reactivity change and the worth of individual control rods from exceeding the selected limiting values.
Reference:
FSAR 5.1-12, 7.5-6 Tech Specs 3.10 Adv Sys LP 26A, Objective 1 and 26B, Objective 10 5.2 State three (3) reasons why tritium is more of a problem than other radioactive isotopes found in the plant.
(1.0)
ANSWER a.
Any two of the following at.33 each 1.
Tritium emits a low-energy beta and is hard to detect 2.
Tritium has a 12 year half life of relatively long T 3.
Tritium can diffuse through metal 4.
Tritium is an isotope of hydrogen, so it cannot be filtered or chemically removed 5.
Tritium can easily enter a human's body
Reference:
Tech Specs, Nuclear Physics, Chemistry 1
mi0785-0002b-tgb
m 5.3 For EOC conditions, is there a difference in the net reactivity addition for a l'F. change in moderator temperature where the moderator temperature is at 70*F. as opposed to 500'F.? If there is a difference, at which temperature is the most negative reactivity inserted?
(1.5)
ANSWER Yes
(.75) 500'F.
(.75)
Reference:
LP NOT 4.4-02-17, Obj F, I LP NOT 4.4-02-18, Obj B i
5.4 What effect does the buildup of Pu-239 over core life have on reactor control for equal reactivity additions at BOC and EOC?
(1.0)
ANSWER (1.0)
For equal reactivity additions, the SUR would be higher at EOC than BOC.
(Higher SUR = Shorter Period.)
f
Reference:
LP NOT 4.4-02-20, Obj D-3 LP NOT 4.4-02-15, Obj B-2 5.5 State three (3) reasons for control rod power dependent insertion (1.5) limits.
ANSWER l
1.
Ensure shutdown margin limits are satisfied
(.5) 2.
Limit individual rod worth
(.5)
)
3.
Limit hot channel factors
(.5)
Reference:
Technical Specification 3-60 Advanced System Lesson Plan 26B, Objective 8 mio785-0002b-tab i
4 5.6 a.
Is the reciprocal boron worth greater at the BOC or EOC7
(.75) b.
Does fuel temperature defect become more negative or less negative over core life?
(.75)
ANSWER a.
(.75) b.
Less negative
(.75)
Reference:
Tech Data Book LP NOT 4.4-02-21, Obj B 4
5.7 List three ways in which gammas react with matter.
(1.0)
ANSWER Photoelectric effect
(.33)
Comptons scattering
(.33)
Pair production
(.33)
Reference:
LP NOT 4.4-02-04, Obj C mio785-0002b-tsb
5.8 True or False (1.5) a.
The leak rate from a closed system can be reduced by reducing pressure within the system, b.
The definition of enthalpy is the sum of internal energy and ex-ternal energy of a substance, c.
The definition of natural convection is heat flow as a result of density changes in a working fluid.
ANSWER a.
True
(.5) b.
False
(.5) c.
True
(.5)-
Reference:
LP NOT 4.4-08-01, Obj A-2-d LP NOT 4.4-08-01, Obj 6a LP NOT 4.4-08-01, Obj C-1.a.1 5.9 With the plant operating at 100 percent power, the water level in 5A and B feedwater heaters (shell side) increases above the normal control level, would you expect the temperature of the water exiting the tube side to remain constant, increase or decrease?
(.5)
ANSWER Decrease
Reference:
Advanced System Lesson Plan 18C, Objective 5
\\
mi0785-0002b-tgb
5.10 True or False Pump discharge head is proportional to the change in speed
(.5) a.
squared for a centrifugal pump in a system.
b.
Neutron flux causes steel in the reactor vessel.co become more ductile at given temps.
(.5)
ANSWER a.
True
_(.5) b.
False
(.5)
Reference:
LP NOT 4.4-08-03, Obj B-1.d.2.b LP NOT 4.4-08-03, Obj B 5.11 In regards to a restriction type flow measuring device, the following questions deal with the relationship of flow to pressure and pressure to velocity.
a.
Which of the following accurately describes the relationship between flow and pressure through the restriction?
(.5) 1.
Flow = A Pressure
" " APressure 3.
Flow = Pressure 4.
Flow = /APressure ANSWER 4
Reference:
I&C 07-01-02 mi0785-0002b-tgb
e-<--
b.
Which of the following describes the relationship of Pressure (P) and Velocity (V) through a restriction?
(.5) 1.
Pt V+
2.
P4 Vt 3.
P+ V+
4.
Pt Vt ANSWER 2
Reference:
I&C 07-01-02 5.12 List the two Reactor Protection System trips which protect against Departure.from Nucleate Boiling.
(1.5)
ANSWER 1.
Low Flow
(.75) 2.
TMLP
(.75)
Reference:
TS Sect 2.3 mi0785-0002b-tgb i
l
5.13 Indicate for the following events if the Cooling Tower pump motor amps will increase, decrease or remain the same.
a.
Increase circulating water temp by 20*F.
(.25)
ANSWER Decrease
Reference:
LP NOT 4.4-08-03, Objective B Advanced System Lesson Plan 17C, Obj 2 b.
Decrease in voltage on 'F' and 'G' busses.
(.25)
ANSWER Increase
Reference:
LP NOT 4.4-03-01, Obj A Adv Systems LP 17, Obj 2 c.
Increase in Stator Temp.
(.25)
ANSWER Increase
Reference:
LP NOT 4.4-03-01, Obj D Adv Systems LP 17, Obj 2 d.
Throttle discharge valve to increase pump suction basin level.
(.25)
ANSWER Decrease
Reference:
LP NOT 4.4-08-03, Obj B Adv Sys LP 17, Obj 2 mi0785-0002b-tgb
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